User Input for NJOY2012.82. Search down for the desired module in caps: NJOY, RECONR, BROADR, UNRESR, HEATR, THERMR, GROUPR, GAMINR, ERRORJ, COVR, MODER, DTFR, CCCCR, MATXSR, RESXSR, ACER, POWR, WIMSR, PLOTR, VIEWR, MIXR, PURR, LEAPR, GASPR NJOY njoy.2 : program njoy njoy njoy.3 : !----------------------------------------------------------------------- njoy njoy.4 : ! njoy njoy.5 : ! NJOY Nuclear Data Processing System njoy newv.7 : ! Version 2012.82 njoy njoy.7 : ! njoy njoy.8 : !----------------------------------------------------------------------- njoy njoy.9 : ! njoy njoy.10 : ! NJOY is a system of processing modules intended to convert evaluated njoy njoy.11 : ! nuclear data in the ENDF format into forms useful for practical njoy njoy.12 : ! applications. It consists of a number of independent processing njoy njoy.13 : ! modules that perform various processing tasks and this main program njoy njoy.14 : ! (njoy) that runs the modules in the desired order. The modules njoy njoy.15 : ! currently available are the following: njoy njoy.16 : ! njoy njoy.17 : ! reconr...reconstruct pointwise cross sections from ENDF/B resonance njoy njoy.18 : ! parameters and interpolation schemes. njoy njoy.19 : ! njoy njoy.20 : ! broadr...doppler broaden and thin pointwise cross sections. njoy njoy.21 : ! njoy njoy.22 : ! unresr...compute effective pointwise self-shielded cross sections in njoy njoy.23 : ! the unresolved energy range. njoy njoy.24 : ! njoy njoy.25 : ! heatr....compute heat production cross sections (kerma) and damage njoy njoy.26 : ! energy production. njoy njoy.27 : ! njoy njoy.28 : ! thermr...generate neutron scattering cross sections and njoy njoy.29 : ! point-to-point scattering kernels in the thermal range for njoy njoy.30 : ! free or bound atoms. njoy njoy.31 : ! njoy njoy.32 : ! groupr...generate self-shielded multigroup cross sections and njoy njoy.33 : ! group-to-group scattering and photon production matrices. njoy njoy.34 : ! njoy njoy.35 : ! gaminr...compute multigroup photon interaction cross sections, njoy njoy.36 : ! scattering matrices, and heat production. njoy njoy.37 : ! njoy njoy.38 : ! errorr...construct multigroup covariance matrices. njoy njoy.39 : ! njoy njoy.40 : ! covr.....process covariance data from errorr. njoy njoy.41 : ! njoy njoy.42 : ! moder....convert between ENDF/B standard coded mode and the njoy njoy njoy.43 : ! blocked binary mode. njoy njoy.44 : ! njoy njoy.45 : ! dtfr.....output and plot multigroup data for discrete ordinates njoy njoy.46 : ! transport codes. njoy njoy.47 : ! njoy njoy.48 : ! ccccr....format multigroup data into the CCCC standard interface njoy njoy.49 : ! files ISOTXS, BRKOXS, and DLAYXS. njoy njoy.50 : ! njoy njoy.51 : ! matxsr...convert multigroup data into the comprehensive MATXS njoy njoy.52 : ! cross section interface format. njoy njoy.53 : ! njoy njoy.54 : ! resxsr...prepare a CCCC-like file of pointwise resonance njoy njoy.55 : ! cross sections for thermal flux calculations. njoy njoy.56 : ! njoy njoy.57 : ! acer.....prepare library for the Los Alamos continuous energy njoy njoy.58 : ! Monte Carlo code MCNP. njoy njoy.59 : ! njoy njoy.60 : ! powr.....convert multigroup data into libraries for the thermal njoy njoy.61 : ! power reactor codes EPRI-CELL and EPRI-CPM. njoy njoy.62 : ! njoy njoy.63 : ! wimsr....convert multigroup data into libraries for the reactor njoy njoy.64 : ! assembly codes WIMS-D or WIMS-E. njoy njoy.65 : ! njoy njoy.66 : ! plotr....plot ENDF, PENDF, GENDF, or experimental cross sections, njoy njoy.67 : ! distributions, or matrices. njoy njoy.68 : ! njoy njoy.69 : ! viewr....view plots from plotr, dtfr, covr, etc. in Postscript. njoy njoy.70 : ! njoy njoy.71 : ! mixr.....mix file 3 cross sections (for example, to make elemental njoy njoy.72 : ! cross sections) for plotting, etc. njoy njoy.73 : ! njoy njoy.74 : ! purr.....generate unresolved-resonance probability tables for the njoy njoy.75 : ! MCNP Monte Carlo code. njoy njoy.76 : ! njoy njoy.77 : ! leapr....generate S(alpha,beta) for thermal moderators. njoy njoy.78 : ! njoy njoy.79 : ! gaspr....add gas production (MT203-207) to PENDF tape. njoy njoy.80 : ! njoy njoy.81 : ! Each processing module is implemented as a Fortran-90 module with njoy njoy.82 : ! only one public subroutine named as above. The modules have the njoy njoy.83 : ! names as given above with "m" instead of "r". Processing modules njoy njoy.84 : ! communicate through I/O units, and their internal data and njoy njoy.85 : ! subroutines are kept private to reduce the possibility of side njoy njoy.86 : ! effects between modules. There are also some modules providing njoy njoy.87 : ! common capabilities to all the processing modules: njoy njoy.88 : ! njoy njoy.89 : ! module description njoy njoy.90 : ! --------- -------------------------------------------- njoy njoy.91 : ! version contains the current version information njoy njoy.92 : ! locale contains localization parameters njoy njoy.93 : ! mainio contains the main I/O unit numbers njoy njoy.94 : ! util contains utility subroutines used by modules njoy njoy.95 : ! endf contains routines for handling ENDF files njoy njoy.96 : ! math contains math routines used by other modules njoy njoy.97 : ! physics contains common physics constants njoy njoy.98 : ! njoy njoy.99 : !---input specifications (free format)---------------------------------- njoy njoy.100 : ! njoy njoy.101 : ! card 1 module option njoy njoy.102 : ! njoy njoy.103 : ! module six character module name, e.g., reconr. njoy njoy.104 : ! it is not necessary to use quotes. njoy njoy.105 : ! njoy njoy.106 : ! repeat card 1 for each module desired, and njoy njoy.107 : ! use the name "stop" to terminate the program. njoy njoy.108 : ! njoy njoy.109 : ! See the comments at the start of each module for its specific input njoy njoy.110 : ! instructions. njoy njoy.111 : ! njoy njoy.112 : !----------------------------------------------------------------------- njoy RECONR reconr.53 : subroutine reconr reconr reconr.54 : !------------------------------------------------------------------- reconr reconr.55 : ! reconr reconr.56 : ! Reconstruct pointwise cross sections reconr reconr.57 : ! reconr reconr.58 : ! Resonance cross sections are calculated using methods from the reconr reconr.59 : ! earlier versions of NJOY (which are descended from those of reconr reconr.60 : ! the early RESEND code) or the methods developed for the SAMMY reconr reconr.61 : ! R-matrix fitting code, depending on the format used. reconr reconr.62 : ! reconr reconr.63 : ! This program generates an energy grid which is the union of an reconr reconr.64 : ! input grid (if any), the resonance energies (if any), and the reconr reconr.65 : ! energies of cross sections in mf3 and mf13 (or mf23). The reconr reconr.66 : ! pointwise cross sections are then computed on this grid and reconr reconr.67 : ! points are added so that the resonance cross sections and any reconr reconr.68 : ! cross sections represented by non-linear interpolation are reconr reconr.69 : ! reproduced within a specified tolerance by linear interpolation. reconr reconr.70 : ! Psi-Chi reconstruction can be used if desired. Sections which reconr reconr.71 : ! are not cross sections (mubar,nubar) and photon multiplicities reconr reconr.72 : ! (MF12) are not processed. Redundant reactions are reconstructed reconr reconr.73 : ! to be the sum of their parts. The pendf tape contains point reconr reconr.74 : ! cross sections in MF3 and MF13 (or MF23) and a description of reconr reconr.75 : ! the processing in MF1. The MF1 dictionary is updated. The reconr reconr.76 : ! C1 and C2 fields of the second card in MF1 contain the temper- reconr reconr.77 : ! ature and reconstruction tolerance, respectively. An MF2 reconr reconr.78 : ! appropriate to no resonance parameters is constructed with reconr reconr.79 : ! the potential scattering length added. reconr reconr.80 : ! reconr reconr.81 : ! If unresolved parameters are present, the infinitely dilute reconr reconr.82 : ! cross sections are computed on a special energy grid chosen to reconr reconr.83 : ! preserve the required interpolation properties. This table is reconr reconr.84 : ! added to the pendf tape using a special format in MF2/MT152, reconr reconr.85 : ! and the table is also used to compute the unresolved contribu- reconr reconr.86 : ! tions in MF3. This allows resolved resonance cross sections reconr reconr.87 : ! which overlap the resolved range to be recovered by subtraction. reconr reconr.88 : ! reconr reconr.89 : !---input specifications (free format)--------------------------- reconr reconr.90 : ! reconr reconr.91 : ! card 1 reconr reconr.92 : ! nendf unit for endf tape reconr reconr.93 : ! npend unit for pendf tape reconr reconr.94 : ! card 2 reconr reconr.95 : ! tlabel 66 character label for new pendf tape reconr reconr.96 : ! delimited with quotes, ended with /. reconr reconr.97 : ! card 3 reconr reconr.98 : ! mat material to be reconstructed reconr reconr.99 : ! ncards number of cards of descriptive data for new mf1 reconr reconr.100 : ! (default=0) reconr reconr.101 : ! ngrid number of user energy grid points to be added. reconr reconr.102 : ! (default=0) reconr reconr.103 : ! card 4 reconr reconr.104 : ! err fractional reconstruction tolerance used when reconr reconr.105 : ! resonance-integral error criterion (see errint) reconr reconr.106 : ! is not satisfied. reconr reconr.107 : ! tempr reconstruction temperature (deg kelvin) reconr reconr.108 : ! (default=0) reconr reconr.109 : ! errmax fractional reconstruction tolerance used when reconr reconr.110 : ! resonance-integral error criterion is satisfied reconr reconr.111 : ! (errmax.ge.err, default=10*err) reconr reconr.112 : ! errint maximum resonance-integral error (in barns) reconr reconr.113 : ! per grid point (default=err/20000) reconr reconr.114 : ! (note: the max cross section difference for reconr reconr.115 : ! linearization, errlim, and for reconstruction, reconr reconr.116 : ! errmin, are also tied to errint. to get maximum reconr reconr.117 : ! accuracy, set errint to a very small number. reconr reconr.118 : ! for economical production, use the defaults.) reconr reconr.119 : ! card 5 reconr reconr.120 : ! cards ncards of descriptive comments for mt451 reconr reconr.121 : ! each card delimited with quotes, ended with /. reconr reconr.122 : ! card 6 reconr reconr.123 : ! enode users energy grid points reconr reconr.124 : ! reconr reconr.125 : ! cards 3, 4, 5, 6 must be input for each material desired reconr reconr.126 : ! mat=0/ terminates execution of reconr. reconr reconr.127 : ! reconr reconr.128 : !------------------------------------------------------------------- reconr BROADR broadr.23 : subroutine broadr broadr broadr.24 : !------------------------------------------------------------------- broadr broadr.25 : ! broadr broadr.26 : ! Doppler broaden and thin neutron point cross sections broadr broadr.27 : ! broadr broadr.28 : ! A modified version of the kernel broadening method developed broadr broadr.29 : ! for SIGMA1 (D.E.Cullen, LLNL) is used. Cross sections for low broadr broadr.30 : ! threshold reactions are unionized on the grid of the total broadr broadr.31 : ! cross section, then broadened and thinned in parallel. broadr broadr.32 : ! High threshold reactions are not broadened. the total and broadr broadr.33 : ! nonelastic are reconstructed to equal the sum of parts. broadr broadr.34 : ! broadr broadr.35 : ! The output energy grid for broadened cross sections is broadr broadr.36 : ! constructed adaptively (as in reconr) so that the results broadr broadr.37 : ! represent the true function within the given tolerance. broadr broadr.38 : ! Energy values are either removed from the original grid, or broadr broadr.39 : ! new values are added between the original points. Thus, a broadr broadr.40 : ! given energy range can have more or fewer points than the broadr broadr.41 : ! original energy grid. broadr broadr.42 : ! broadr broadr.43 : ! For high temperatures and low energies where the original broadr broadr.44 : ! SIGMA1 breaks down, a new direct expansion of the Doppler broadr broadr.45 : ! integral is used. broadr broadr.46 : ! broadr broadr.47 : ! If the temperature is close to 293.6 K (.0253 eV), broadr broadr broadr.48 : ! computes and displays thermal cross sections, Maxwellian broadr broadr.49 : ! integrals (one-group thermal cross sections), g-factors, broadr broadr.50 : ! integral ratios (eta, alpha), the K1 integral and the broadr broadr.51 : ! corresponding 1/v-equivalent, and resonance integrals. broadr broadr.52 : ! broadr broadr.53 : ! The results are written out in pendf format with each broadr broadr.54 : ! temperature represented as a different MAT. Dictionaries broadr broadr.55 : ! are corrected to reflect the effects of thinning. broadr broadr.56 : ! broadr broadr.57 : !---input specifications (free format)--------------------------- broadr broadr.58 : ! broadr broadr.59 : ! card 1 broadr broadr.60 : ! nendf input endf tape (for thermal nubar only) broadr broadr.61 : ! nin input pendf tape broadr broadr.62 : ! nout output pendf tape broadr broadr.63 : ! card 2 broadr broadr.64 : ! mat1 material to broadened and thinned broadr broadr.65 : ! ntemp2 number of final temperatures (default=1) broadr broadr.66 : ! istart restart (0 no, 1 yes, default 0) broadr broadr.67 : ! istrap bootstrap (0 no, 1 yes, default 0 broadr broadr.68 : ! temp1 starting temperature from nin (default=0K) broadr broadr.69 : ! card 3 broadr broadr.70 : ! errthn fractional tolerance for thinning broadr up75.21 : ! thnmax max.energy for broadening and thinning broadr up75.22 : ! (default = 0, but see comments below) broadr broadr.73 : ! errmax fractional tolerance used when integral criterion broadr broadr.74 : ! is satisfied (same usage as in reconr) broadr broadr.75 : ! (errmax.ge.errthn, default=10*errthn) broadr broadr.76 : ! errint parameter to control integral thinning broadr broadr.77 : ! (usage as in reconr) (default=errthn/20000) broadr broadr.78 : ! set very small to turn off integral thinning. broadr broadr.79 : ! (A good choice for the convergence parameters broadr broadr.80 : ! errthn, errmax, and errint is the same set of broadr broadr.81 : ! values used in reconr) broadr broadr.82 : ! card 4 broadr broadr.83 : ! temp2 final temperatures (deg Kelvin) broadr broadr.84 : ! card 5 broadr broadr.85 : ! mat1 next MAT number to be processed with these broadr broadr.86 : ! parameters. Terminate with mat1=0. broadr broadr.87 : ! broadr broadr.88 : !---input options------------------------------------------------ broadr broadr.89 : ! broadr broadr.90 : ! The output tape will contain the ntemp2 final temperatures broadr broadr.91 : ! specified. It is necessary to have temp1.le.temp2(1). broadr broadr.92 : ! if temp2.eq.temp1, the data will be thinned only. broadr broadr.93 : ! broadr broadr.94 : ! restart Continue broadening an existing pendf tape. All broadr broadr.95 : ! temperatures are copied through temp1. Additional broadr broadr.96 : ! final temperatures are added by starting with the broadr broadr.97 : ! data at temp1. broadr broadr.98 : ! broadr broadr.99 : ! bootstrap If bootstrap is not requested, each final tempera- broadr broadr.100 : ! ture is generated by broadening directly from broadr broadr.101 : ! temp1 to temp2. If bootstrap is requested, each broadr broadr.102 : ! final temperature is broadened from the preceding broadr broadr.103 : ! temperature. This option is faster due to the broadr broadr.104 : ! thinning in the previous step. However, errors broadr broadr.105 : ! accumulate. broadr broadr.106 : ! broadr broadr.107 : ! thnmax A possible upper limit for broadening and thinning. broadr up75.24 : ! Beginning with NJOY2012.75, if the default thnmax broadr up75.25 : ! value is used (default thnmax = 0): broadr up75.26 : ! - (i) and there is a resolved resonance region we broadr up75.27 : ! Doppler broaden to the top of that region. any broadr up75.28 : ! threshold reactions below this upper limit are also broadr up75.29 : ! broadened, but any non-zero cross section for energies broadr up75.30 : ! below the reaction threshold are zeroed. broadr up75.31 : ! - (ii) and there is no resolved resonance region but broadr up75.32 : ! there is an unresolved resonance region we Doppler broadr up75.33 : ! broaden to the beginning of the urr. broadr up75.34 : ! - (iii) and there are no resolved or unresolved broadr up75.35 : ! resonance parameters, we broaden to the lessor of broadr up75.36 : ! 6.5 MeV or the first threshold energy. broadr up75.37 : ! broadr up75.38 : ! As before, a negative value for thnmax forces the broadr up75.39 : ! Doppler broadening upper limit to be abs(thnmax) broadr up75.40 : ! irrespective of the other conditions. broadr up75.41 : ! broadr up75.42 : ! Caution: The magnitude of thnmax must be chosen to broadr up75.43 : ! keep the number of broadenable reactions less than or broadr up75.44 : ! equal to the maximum of ntt (160). broadr broadr.128 : ! broadr broadr.129 : !------------------------------------------------------------------- broadr UNRESR unresr.21 : subroutine unresr unresr unresr.22 : !-------------------------------------------------------------------- unresr unresr.23 : ! unresr unresr.24 : ! compute unresolved resonance cross-sections unresr unresr.25 : ! unresr unresr.26 : ! The method of ETOX is used to compute self-shielded unresr unresr.27 : ! unresolved resonance cross-sections on the energy grid of unresr unresr.28 : ! the unresolved parameters. Subsequent interpolation is unresr unresr.29 : ! to be on the cross-sections and not on the parameters. unresr unresr.30 : ! Additional energy grid points are added at quarter lethargy unresr unresr.31 : ! intervals if only three or fewer grid points are found. unresr unresr.32 : ! The accurate Hwang quadrature set is used for the integrals. unresr unresr.33 : ! unresr unresr.34 : !---input specifications (free format)--------------------------- unresr unresr.35 : ! unresr unresr.36 : ! card 1 unresr unresr.37 : ! nendf unit for endf tape unresr unresr.38 : ! nin unit for input pendf tape unresr unresr.39 : ! nout unit for output pendf tape unresr unresr.40 : ! card 2 unresr unresr.41 : ! matd material to be processed unresr unresr.42 : ! ntemp no. of temperatures (default=1) unresr unresr.43 : ! nsigz no. of sigma zeroes (default=1) unresr unresr.44 : ! iprint print option (0=min, 1=max) (default=0) unresr unresr.45 : ! card 3 unresr unresr.46 : ! temp temperatures in Kelvin (including zero) unresr unresr.47 : ! card 4 unresr unresr.48 : ! sigz sigma zero values (including infinity) unresr unresr.49 : ! cards 2, 3, 4 must be input for each material desired unresr unresr.50 : ! matd=0/ terminates execution of unresr. unresr unresr.51 : ! unresr unresr.52 : !-------------------------------------------------------------------- unresr HEATR heatr.45 : subroutine heatr heatr heatr.46 : !------------------------------------------------------------------- heatr heatr.47 : ! heatr heatr.48 : ! Compute heating kerma (kinetic energy release in material) heatr heatr.49 : ! and radiation damage energy production. heatr heatr.50 : ! heatr heatr.51 : ! The prompt kerma is computed pointwise on the grid of the heatr heatr.52 : ! total cross section from the input pendf tape and written heatr heatr.53 : ! onto the output PENDF tape at infinite dilution using the heatr heatr.54 : ! 300 series of MT numbers. All temperatures on the input PENDF heatr heatr.55 : ! tape for the desired material are processed. The dictionary heatr heatr.56 : ! is revised. Reaction Q values are obtained from the ENDF heatr heatr.57 : ! tape unless the user enters his own value. Partial kermas heatr heatr.58 : ! can be requested for self-shielding calculations or other heatr heatr.59 : ! purposes. The code uses the energy balance method where heatr heatr.60 : ! photon files are available and deposits all photon energy heatr heatr.61 : ! locally when files are not available. This assures heatr heatr.62 : ! consistency between neutron heating and energy deposition by heatr heatr.63 : ! subsequent photon interactions. An exception is made for heatr heatr.64 : ! capture where recoil is computed by momentum conservation. heatr heatr.65 : ! Photon files are used to estimate the average photon momentum heatr heatr.66 : ! when available. A diagnostic message is printed if the heatr heatr.67 : ! momentum calculation leads to a significant error in heatr heatr.68 : ! energy conservation. heatr heatr.69 : ! heatr heatr.70 : ! If desired, the energy-balance kerma factors can be compared heatr heatr.71 : ! with conservative kinematic limits (set iprint=2). heatr heatr.72 : ! A plot file for viewr can be automatically prepared. heatr heatr.73 : ! heatr heatr.74 : ! Damage energy is computed using the Lindhard electronic heatr heatr.75 : ! screening damage function with a displacement threshold heatr heatr.76 : ! from a table of default values for important elements heatr heatr.77 : ! or a value provided by the user. heatr heatr.78 : ! heatr heatr.79 : !---input specifications (free format)--------------------------- heatr heatr.80 : ! heatr heatr.81 : ! card 1 heatr heatr.82 : ! nendf unit for endf tape heatr heatr.83 : ! nin unit for input pendf tape heatr heatr.84 : ! nout unit for output pendf tape heatr heatr.85 : ! nplot unit for graphical check output heatr heatr.86 : ! card 2 heatr heatr.87 : ! matd material to be processed heatr heatr.88 : ! npk number of partial kermas desired (default=0) heatr heatr.89 : ! nqa number of user q values (default=0) heatr heatr.90 : ! ntemp number of temperatures to process heatr heatr.91 : ! (default=0, meaning all on pendf) heatr heatr.92 : ! local 0/1=gamma rays transported/deposited locally heatr heatr.93 : ! (default=0) heatr heatr.94 : ! iprint print (0 min, 1 max, 2 check) (default=0) heatr heatr.95 : ! ed displacement energy for damage heatr heatr.96 : ! (default from built-in table) heatr heatr.97 : ! card 3 for npk gt 0 only heatr heatr.98 : ! mtk mt numbers for partial kermas desired heatr heatr.99 : ! total (mt301) will be provided automatically. heatr heatr.100 : ! partial kerma for reaction mt is mt+300 heatr heatr.101 : ! and may not be properly defined unless heatr heatr.102 : ! a gamma file for mt is on endf tape. heatr heatr.103 : ! special values allowed-- heatr heatr.104 : ! 303 non-elastic (all but mt2) heatr heatr.105 : ! 304 inelastic (mt51 thru 91) heatr heatr.106 : ! 318 fission (mt18 or mt19, 20, 21, 38) heatr heatr.107 : ! 401 disappearance (mt102 thru 120) heatr heatr.108 : ! 442 total photon ev-barns heatr heatr.109 : ! 443 total kinematic kerma (high limit) heatr heatr.110 : ! damage energy production values-- heatr heatr.111 : ! 444 total heatr heatr.112 : ! 445 elastic (mt2) heatr heatr.113 : ! 446 inelastic (mt51 thru 91) heatr heatr.114 : ! 447 disappearance (mt102 thru 120) heatr heatr.115 : ! cards 4 and 5 for nqa gt 0 only heatr heatr.116 : ! card 4 heatr heatr.117 : ! mta mt numbers for users q values heatr heatr.118 : ! card 5 heatr heatr.119 : ! qa user specified q values (ev) heatr heatr.120 : ! (if qa.ge.99.e6, read in variable qbar heatr heatr.121 : ! for this reaction) heatr heatr.122 : ! card 5a variable qbar (for reactions with qa flag only) heatr heatr.123 : ! qbar tab1 record giving qbar versus e (1000 words max) heatr heatr.124 : ! heatr heatr.125 : !------------------------------------------------------------------- heatr THERMR thermr.35 : subroutine thermr thermr thermr.36 : !------------------------------------------------------------------- thermr thermr.37 : ! thermr thermr.38 : ! Generate neutron scattering cross sections and point-to-point thermr thermr.39 : ! scattering kernels in the thermal range. The coding can thermr thermr.40 : ! generate incoherent inelastic cross sections and distributions thermr thermr.41 : ! for a free gas, incoherent inelastic cross sections and thermr thermr.42 : ! distributions from read-in S(alpha,beta,T) data, coherent thermr thermr.43 : ! elastic scattering cross sections for crystalline materials, thermr thermr.44 : ! and incoherent elastic cross sections and angular distributions thermr thermr.45 : ! for hydrogenous solids. thermr thermr.46 : ! thermr thermr.47 : ! The pointwise scattering cross sections and distributions are thermr thermr.48 : ! added to an existing PENDF tape. Cross sections are added in thermr thermr.49 : ! MF3 and distributions are written in MF6, both using mtref for thermr thermr.50 : ! inelastic and mtref+1 for elastic (if any). thermr thermr.51 : ! thermr thermr.52 : ! Multiple scattering types (i.e., H free and H in H2O) can be thermr thermr.53 : ! written on one PENDF tape by using different values of mtref thermr thermr.54 : ! for each thermr run. If data for one mtref is already on the thermr thermr.55 : ! tape, it will be replaced with the new cross sections. thermr thermr.56 : ! thermr thermr.57 : ! The energy grid for coherent scattering is determined thermr thermr.58 : ! adaptively so as to represent the sharp Bragg edges to a thermr thermr.59 : ! specified tolerance using linear interpolation. No angular thermr thermr.60 : ! information is provided for coherent scattering. It can be thermr thermr.61 : ! deduced by subsequent processing from the Bragg edges in the thermr thermr.62 : ! cross section. thermr thermr.63 : ! thermr thermr.64 : ! The incident energy grid for incoherent inelastic scattering thermr thermr.65 : ! is fixed in the code, although it is scaled to higher values thermr thermr.66 : ! for very large incident energies. There are two options for thermr thermr.67 : ! representing the energy and angle distributions for secondary thermr thermr.68 : ! inelastic neutrons. thermr thermr.69 : ! thermr thermr.70 : ! The standard approach is to generate an energy grid for the thermr thermr.71 : ! secondary energy distribution integrated over angle thermr thermr.72 : ! adaptively. The angular distribution for each secondary thermr thermr.73 : ! energy is given using a set of equally probable emission thermr thermr.74 : ! cosines. This is E-E'-mu ordering, and it is represented thermr thermr.75 : ! using a special format in MF6. thermr thermr.76 : ! thermr thermr.77 : ! An alternate approach introduced in NJOY2010 produces E-mu-E' thermr thermr.78 : ! ordering using MF6/Law7. A grid of mu values is generated thermr thermr.79 : ! adaptively for linear interpolation. In addition, secondary thermr thermr.80 : ! energy grids are determined adaptively for each mu value. thermr thermr.81 : ! thermr thermr.82 : ! The sections of File 6 produced by thermr have several thermr thermr.83 : ! special features. The LIP flag is used to identify the thermr thermr.84 : ! various kinds of thermal data: LIP=-1 means incoherent thermr thermr.85 : ! inelastic data, LIP=-2 means incoherent inelastic data, and thermr thermr.86 : ! LIP=-nbrag means coherent elastic data with nbrag Bragg thermr thermr.87 : ! edges. For incoherent elastic or inelastic data using thermr thermr.88 : ! LAW=1, the angular data are equally probable cosines. thermr thermr.89 : ! thermr thermr.90 : ! For ENDF 3 to 5 formats, the constants used for coherent thermr thermr.91 : ! elastic, incoherent elastic, and short-collision-time calcu- thermr thermr.92 : ! lations are obtained from internal data statements based on thermr thermr.93 : ! the original general atomic report on the evaluations thermr thermr.94 : ! (GA-8774 revised, ENDF-269, July 1978). thermr thermr.95 : ! thermr thermr.96 : ! For ENDF-6 format libraries, these constants are included thermr thermr.97 : ! in the format. thermr thermr.98 : ! thermr thermr.99 : !---input specifications (free format)-------------------------- thermr thermr.100 : ! thermr thermr.101 : ! card 1 thermr thermr.102 : ! nendf endf tape for mf7 data thermr thermr.103 : ! nin old pendf tape thermr thermr.104 : ! nout new pendf tape thermr thermr.105 : ! card 2 thermr thermr.106 : ! matde material desired on endf tape thermr thermr.107 : ! matdp material desired on pendf tape thermr thermr.108 : ! nbin number of equi-probable angles thermr thermr.109 : ! ntemp number of temperatures (default = 1) thermr thermr.110 : ! iinc inelastic options thermr thermr.111 : ! 0 none thermr thermr.112 : ! 1 compute as free gas thermr thermr.113 : ! 2 read s(a,b) and compute matrix thermr thermr.114 : ! icoh elastic options thermr thermr.115 : ! 0 none thermr thermr.116 : ! 1 compute using ENDF6 format data thermr thermr.117 : ! --------or for earlier formats thermr thermr.118 : ! 1 graphite thermr thermr.119 : ! 2 beryllium thermr thermr.120 : ! 3 beryllium oxide thermr thermr.121 : ! 11 polyethylene thermr thermr.122 : ! 12 h(zrh) thermr thermr.123 : ! 13 zr(zrh) thermr thermr.124 : ! iform output format for inelastic distributions thermr thermr.125 : ! 0 E-E'-mu ordering (MF6 special) thermr thermr.126 : ! 1 E-mu-E' ordering (MF6/Law7) thermr thermr.127 : ! natom number of principal atoms thermr thermr.128 : ! mtref mt for inelastic reaction (221-250 only) thermr thermr.129 : ! iprint print option (0=minimum, 1=maximum, thermr thermr.130 : ! 2=max. normal + intermediate results) thermr thermr.131 : ! (default=0) thermr thermr.132 : ! card 3 thermr thermr.133 : ! tempr temperatures (kelvin) thermr thermr.134 : ! card 4 thermr thermr.135 : ! tol tolerance thermr thermr.136 : ! emax maximum energy for thermal treatment thermr thermr.137 : ! (for temperatures greater than 3000, thermr thermr.138 : ! emax and the energy grid are scaled by thermr thermr.139 : ! temp/3000. free gas only.) thermr thermr.140 : ! thermr thermr.141 : ! nendf can be ENDF6 format (e.g., from leapr) while thermr thermr.142 : ! nin and nout are ENDF4 or 5 format, if desired. thermr thermr.143 : ! thermr thermr.144 : !------------------------------------------------------------------- thermr GROUPR groupr.99 : subroutine groupr groupr groupr.100 : !------------------------------------------------------------------- groupr groupr.101 : ! groupr groupr.102 : ! compute self-shielded group-averaged cross sections groupr groupr.103 : ! groupr groupr.104 : ! Produces self-shielded cross sections, neutron scattering groupr groupr.105 : ! matrices, and photon production matrices. Scattering and groupr groupr.106 : ! photon matrices may be self-shielded if desired (see init). groupr groupr.107 : ! Bondarenko weighting is normally used. Optionally, the flux groupr groupr.108 : ! can be computed for an infinite mixture of heavy absorber groupr groupr.109 : ! and light moderator. Delayed neutron data and thermal groupr groupr.110 : ! scattering matrices are handled specially. groupr groupr.111 : ! groupr groupr.112 : ! The integration over initial energy is handled in the same groupr groupr.113 : ! way for all reaction types by using the integrand groupr groupr.114 : ! feed*xsec*flux . groupr groupr.115 : ! Feed is the source into final energy group gprime and groupr groupr.116 : ! Legendre order l from initial energy e (see getff). For groupr groupr.117 : ! vectors, the feed is 1. or a yield (nubar, mubar). For two groupr groupr.118 : ! body scattering, a center-of-mass Gaussian integration is used groupr groupr.119 : ! to obtain accurate results even for small Legendre components groupr groupr.120 : ! of the group-to-group scattering. Additional initial energy groupr groupr.121 : ! quadrature points are added to integrate the known polynomial groupr groupr.122 : ! order of this feed function. Feed for tabulated continuum groupr groupr.123 : ! reactions is computed exactly on the endf grid points and groupr groupr.124 : ! then interpolated at e. A special projection interpolation groupr groupr.125 : ! scheme is used for thermal matrices (see getaed). The feed groupr groupr.126 : ! for analytic continuum reactions is exact. groupr groupr.127 : ! groupr groupr.128 : !---input specifications (free format)--------------------------- groupr groupr.129 : ! groupr groupr.130 : ! card1 groupr groupr.131 : ! nendf unit for endf tape groupr groupr.132 : ! npend unit for pendf tape groupr groupr.133 : ! ngout1 unit for input gout tape (default=0) groupr groupr.134 : ! ngout2 unit for output gout tape (default=0) groupr groupr.135 : ! card2 groupr groupr.136 : ! matb material to be processed groupr groupr.137 : ! if ngout=0, matb<0 is an option to automatically groupr groupr.138 : ! process all the mats on the endf input tape. groupr groupr.139 : ! otherwise, matb<0 is a flag to add mts to and/or groupr groupr.140 : ! replace individual mts on gout1. groupr groupr.141 : ! ign neutron group structure option groupr groupr.142 : ! igg gamma group structure option groupr groupr.143 : ! iwt weight function option groupr groupr.144 : ! lord legendre order groupr groupr.145 : ! ntemp number of temperatures (default=1) groupr groupr.146 : ! nsigz number of sigma zeroes (default=1) groupr groupr.147 : ! iprint long print option (0/1=minimum/maximum) groupr groupr.148 : ! (default=1) groupr groupr.149 : ! card3 groupr groupr.150 : ! title run label (up to 80 characters delimited by *, groupr groupr.151 : ! ended with /) (default=blank) groupr groupr.152 : ! card4 groupr groupr.153 : ! temp temperatures in kelvin groupr groupr.154 : ! card5 groupr groupr.155 : ! sigz sigma zero values (including infinity) groupr groupr.156 : ! groupr groupr.157 : ! if ign=1, read neutron group structure (6a and 6b) groupr groupr.158 : ! card6a groupr groupr.159 : ! ngn number of groups groupr groupr.160 : ! card6b groupr groupr.161 : ! egn ngn+1 group breaks (ev) groupr groupr.162 : ! groupr groupr.163 : ! if igg=1, read gamma group structure (7a and 7b) groupr groupr.164 : ! card7a groupr groupr.165 : ! ngg number of groups groupr groupr.166 : ! card7b groupr groupr.167 : ! egg ngg+1 group breaks (ev) groupr groupr.168 : ! groupr groupr.169 : ! weight function options (8a,8b,8c,8d) groupr groupr.170 : ! card8a flux calculator parameters (iwt.lt.0 only) groupr up4.15 : ! fehi break between computed flux and bondarenko flux groupr up4.16 : ! (must be in the resolved resonance range) groupr groupr.173 : ! sigpot estimate of potential scattering cross section groupr groupr.174 : ! nflmax maximum number of computed flux points groupr groupr.175 : ! ninwt tape unit for new flux parameters (default=0) groupr groupr.176 : ! note: weighting flux file is always written binary groupr groupr.177 : ! jsigz index of reference sigma zero in sigz array groupr groupr.178 : ! (default=0) groupr groupr.179 : ! alpha2 alpha for admixed moderator (def=o=none) groupr groupr.180 : ! sam admixed moderator xsec in barns per absorber groupr groupr.181 : ! atom (def=0=none) groupr groupr.182 : ! beta heterogeneity parameter (def=0=none) groupr groupr.183 : ! alpha3 alpha for external moderator (def=0=none) groupr groupr.184 : ! gamma fraction of admixed moderator cross section in groupr groupr.185 : ! external moderator cross section (def=0) groupr groupr.186 : ! card8b tabulated (iwt=1 or -1 only) groupr groupr.187 : ! wght read weight function as tab1 record. groupr groupr.188 : ! end with a /. groupr groupr.189 : ! card8c analytic flux parameters (iwt=4 or -4 only) groupr groupr.190 : ! eb thermal break (ev) groupr groupr.191 : ! tb thermal temperature (ev) groupr groupr.192 : ! ec fission break (ev) groupr groupr.193 : ! tc fission temperature (ev) groupr groupr.194 : ! card8d input resonance flux (iwt=0 only) groupr groupr.195 : ! ninwt tape unit for flux parameters (binary) groupr groupr.196 : ! groupr groupr.197 : ! card9 groupr groupr.198 : ! mfd file to be processed groupr groupr.199 : ! mtd section to be processed groupr groupr.200 : ! mtname description of section to be processed groupr groupr.201 : ! repeat for all reactions desired groupr groupr.202 : ! mfd=0/ terminates this temperature/material. groupr groupr.203 : ! card10 groupr groupr.204 : ! matd next mat number to be processed groupr groupr.205 : ! matd=0/ terminates groupr run. groupr groupr.206 : ! groupr groupr.207 : !---options for input variables---------------------------------- groupr groupr.208 : ! groupr groupr.209 : ! ign meaning groupr groupr.210 : ! --- ------- groupr groupr.211 : ! 1 arbitrary structure (read in) groupr groupr.212 : ! 2 csewg 239-group structure groupr groupr.213 : ! 3 lanl 30-group structure groupr groupr.214 : ! 4 anl 27-group structure groupr groupr.215 : ! 5 rrd 50-group structure groupr groupr.216 : ! 6 gam-i 68-group structure groupr groupr.217 : ! 7 gam-ii 100-group structure groupr groupr.218 : ! 8 laser-thermos 35-group structure groupr groupr.219 : ! 9 epri-cpm 69-group structure groupr groupr.220 : ! 10 lanl 187-group structure groupr groupr.221 : ! 11 lanl 70-group structure groupr groupr.222 : ! 12 sand-ii 620-group structure groupr groupr.223 : ! 13 lanl 80-group structure groupr groupr.224 : ! 14 eurlib 100-group structure groupr groupr.225 : ! 15 sand-iia 640-group structure groupr groupr.226 : ! 16 vitamin-e 174-group structure groupr groupr.227 : ! 17 vitamin-j 175-group structure groupr groupr.228 : ! 18 xmas nea-lanl groupr groupr.229 : ! all new additional group structure with 7 significant groupr groupr.230 : ! decimal digits compatible with calendf groupr groupr.231 : ! 19 ecco 33-group structure groupr groupr.232 : ! 20 ecco 1968-group structure groupr groupr.233 : ! 21 tripoli 315-group structure groupr groupr.234 : ! 22 xmas lwpc 172-group structure groupr groupr.235 : ! 23 vit-j lwpc 175-group structure groupr groupr.236 : ! groupr groupr.237 : ! igg meaning groupr groupr.238 : ! --- ------- groupr groupr.239 : ! 0 none groupr groupr.240 : ! 1 arbitrary structure (read in) groupr groupr.241 : ! 2 csewg 94-group structure groupr groupr.242 : ! 3 lanl 12-group structure groupr groupr.243 : ! 4 steiner 21-group gamma-ray structure groupr groupr.244 : ! 5 straker 22-group structure groupr groupr.245 : ! 6 lanl 48-group structure groupr groupr.246 : ! 7 lanl 24-group structure groupr groupr.247 : ! 8 vitamin-c 36-group structure groupr groupr.248 : ! 9 vitamin-e 38-group structure groupr groupr.249 : ! 10 vitamin-j 42-group structure groupr groupr.250 : ! groupr groupr.251 : ! iwt meaning groupr groupr.252 : ! --- ------- groupr groupr.253 : ! 1 read in smooth weight function groupr groupr.254 : ! 2 constant groupr groupr.255 : ! 3 1/e groupr groupr.256 : ! 4 1/e + fission spectrum + thermal maxwellian groupr groupr.257 : ! 5 epri-cell lwr groupr groupr.258 : ! 6 (thermal) -- (1/e) -- (fission + fusion) groupr groupr.259 : ! 7 same with t-dep thermal part groupr groupr.260 : ! 8 thermal--1/e--fast reactor--fission + fusion groupr groupr.261 : ! 9 claw weight function groupr groupr.262 : ! 10 claw with t-dependent thermal part groupr groupr.263 : ! 11 vitamin-e weight function (ornl-5505) groupr groupr.264 : ! 12 vit-e with t-dep thermal part groupr groupr.265 : ! -n compute flux with weight n groupr groupr.266 : ! 0 read in resonance flux from ninwt groupr groupr.267 : ! groupr groupr.268 : ! mfd meaning groupr groupr.269 : ! --- ------- groupr groupr.270 : ! 3 cross section or yield vector groupr groupr.271 : ! 5 fission chi by short-cut method groupr groupr.272 : ! 6 neutron-neutron matrix (mf4/5) groupr groupr.273 : ! 8 neutron-neutron matrix (mf6) groupr groupr.274 : ! 12 photon prod. xsec (photon yields given, mf12) groupr groupr.275 : ! 13 photon prod. xsec (photon xsecs given, mf13) groupr groupr.276 : ! 16 neutron-gamma matrix (photon yields given) groupr groupr.277 : ! 17 neutron-gamma matrix (photon xsecs given) groupr groupr.278 : ! 18 neutron-gamma matrix (mf6) groupr groupr.279 : ! note: if necessary, mfd=13 will automatically change groupr groupr.280 : ! to 12 and mfd=16 will automatically change to 17 or 18. groupr groupr.281 : ! 21 proton production matrix (mf6) groupr groupr.282 : ! 22 deuteron production (mf6) groupr groupr.283 : ! 23 triton production (mf6) groupr groupr.284 : ! 24 he-3 production (mf6) groupr groupr.285 : ! 25 alpha production (mf6) groupr groupr.286 : ! 26 residual nucleus (a>4) production (mf6) groupr groupr.287 : ! 31 proton production matrix (mf4) groupr groupr.288 : ! 32 deuteron production (mf4) groupr groupr.289 : ! 33 triton production (mf4) groupr groupr.290 : ! 34 he-3 production (mf4) groupr groupr.291 : ! 35 alpha production (mf4) groupr groupr.292 : ! 36 residual nucleus (a>4) production (mf4) groupr groupr.293 : ! note: if necessary, mfd=21-26 will groupr groupr.294 : ! automatically change to 31-36. groupr groupr.295 : ! 1zzzaaam nuclide production for zzzaaam groupr groupr.296 : ! subsection from file 3 groupr groupr.297 : ! 2zzzaaam nuclide production for zzzaaam groupr groupr.298 : ! subsection from file 6 groupr groupr.299 : ! 3zzzaaam nuclide production for zzzaaam groupr groupr.300 : ! subsection from file 9 groupr groupr.301 : ! 4zzzaaam nuclide production for zzzaaam groupr groupr.302 : ! subsection from file 10 groupr groupr.303 : ! groupr groupr.304 : ! mtd meaning groupr groupr.305 : ! --- ------- groupr groupr.306 : ! -n process all mt numbers from the previous groupr groupr.307 : ! entry to n inclusive groupr groupr.308 : ! 221-250 reserved for thermal scattering groupr groupr.309 : ! 257 average energy groupr groupr.310 : ! 258 average lethargy groupr groupr.311 : ! 259 average inverse velocity (m/sec) groupr groupr.312 : ! groupr groupr.313 : ! automatic reaction processing options groupr groupr.314 : ! ------------------------------------- groupr groupr.315 : ! 3/ do all reactions in file3 on input pendf groupr groupr.316 : ! 6/ do all matrix reactions in endf dictionary groupr groupr.317 : ! 10/ do all isotope productions using mf8 groupr groupr.318 : ! 13/ do all photon production cross sections groupr groupr.319 : ! 16/ do all photon production matrices groupr groupr.320 : ! 21/ do all proton production matrices groupr groupr.321 : ! 22/ do all deuteron production matrices groupr groupr.322 : ! 23/ do all triton production matrices groupr groupr.323 : ! 24/ do all he-3 production matrices groupr groupr.324 : ! 25/ do all alpha production matrices groupr groupr.325 : ! 26/ do all a>4 production matrices groupr groupr.326 : ! groupr groupr.327 : !------------------------------------------------------------------- groupr GAMINR gaminr.26 : subroutine gaminr gaminr gaminr.27 : !------------------------------------------------------------------ gaminr gaminr.28 : ! gaminr gaminr.29 : ! compute multigroup photon cross sections gaminr gaminr.30 : ! gaminr gaminr.31 : ! Produce multigroup photon interaction cross sections gaminr gaminr.32 : ! and heating kerma factors using ENDF cross sections gaminr gaminr.33 : ! and coherent and incoherent form factors. Initial energy gaminr gaminr.34 : ! quadrature techiques are identical to those used in groupr. gaminr gaminr.35 : ! Secondary energy-angle quadrature is performed using Gaussian gaminr gaminr.36 : ! integration. gaminr gaminr.37 : ! gaminr gaminr.38 : !---input specifications (free format)--------------------------- gaminr gaminr.39 : ! gaminr gaminr.40 : ! card1 gaminr gaminr.41 : ! nendf unit for endf tape gaminr gaminr.42 : ! npend unit for pendf tape gaminr gaminr.43 : ! ngam1 unit for input ngam tape (default=0) gaminr gaminr.44 : ! ngam2 unit for output ngam tape (default=0) gaminr gaminr.45 : ! card2 gaminr gaminr.46 : ! matb material to be processed gaminr gaminr.47 : ! input materials in ascending order gaminr gaminr.48 : ! igg gamma group structure option gaminr gaminr.49 : ! iwt weight function option gaminr gaminr.50 : ! lord legendre order gaminr gaminr.51 : ! iprint print option (0/1=minimum/maximum) (default=1) gaminr gaminr.52 : ! card3 gaminr gaminr.53 : ! title run label up to 80 characters (delimited by ', gaminr gaminr.54 : ! ended with /) gaminr gaminr.55 : ! card4 (igg=1 only) gaminr gaminr.56 : ! ngg number of groups gaminr gaminr.57 : ! egg ngg+1 group bounds (ev) gaminr gaminr.58 : ! card5 (iwt=1 only) gaminr gaminr.59 : ! wght weight function as tab1 record gaminr gaminr.60 : ! card6 gaminr gaminr.61 : ! mfd file to be processed gaminr gaminr.62 : ! mtd section to be processed gaminr gaminr.63 : ! mtname description of section to be processed gaminr gaminr.64 : ! repeat for all reactions desired gaminr gaminr.65 : ! mfd=0/ terminates this material gaminr gaminr.66 : ! mfd=-1/ is a flag to process all sections present gaminr gaminr.67 : ! for this material (termination is automatic) gaminr gaminr.68 : ! card7 gaminr gaminr.69 : ! matd next mat number to be processed gaminr gaminr.70 : ! terminate gaminr run with matd=0. gaminr gaminr.71 : ! gaminr gaminr.72 : !---options for input variables---------------------------------- gaminr gaminr.73 : ! gaminr gaminr.74 : ! igg meaning gaminr gaminr.75 : ! --- ------- gaminr gaminr.76 : ! 0 none gaminr gaminr.77 : ! 1 arbitrary structure (read in) gaminr gaminr.78 : ! 2 csewg 94-group structure gaminr gaminr.79 : ! 3 lanl 12-group structure gaminr gaminr.80 : ! 4 steiner 21-group gamma-ray structure gaminr gaminr.81 : ! 5 straker 22-group structure gaminr gaminr.82 : ! 6 lanl 48-group structure gaminr gaminr.83 : ! 7 lanl 24-group structure gaminr gaminr.84 : ! 8 vitamin-c 36-group structure gaminr gaminr.85 : ! 9 vitamin-e 38-group structure gaminr gaminr.86 : ! 10 vitamin-j 42-group structure gaminr gaminr.87 : ! gaminr gaminr.88 : ! iwt meaning gaminr gaminr.89 : ! --- ------- gaminr gaminr.90 : ! 1 read in gaminr gaminr.91 : ! 2 constant gaminr gaminr.92 : ! 3 1/e + rolloffs gaminr gaminr.93 : ! gaminr gaminr.94 : !------------------------------------------------------------------ gaminr ERRORR errorr.130 : subroutine errorr errorr errorr.131 : !-------------------------------------------------------------------- errorr errorr.132 : ! errorr errorr.133 : ! Produce cross section covariances from error files in ENDF format errorr errorr.134 : ! errorr errorr.135 : ! First, the union energy grid of the users group structure errorr errorr.136 : ! and the ENDF covariance energies is determined. The array errorr errorr.137 : ! of coefficients for derived cross sections is also constructed. errorr errorr.138 : ! Then multigroup cross sections are computed on the union errorr errorr.139 : ! grid (see grpav), or they are read from a multigroup cross errorr errorr.140 : ! section library and then collapsed to the union grid. The errorr errorr.141 : ! methods of groupr are used for cross section averaging. ENDF errorr errorr.142 : ! covariances and the group cross sections are then combined errorr errorr.143 : ! to get the basic covariance matrices (see covcal). Finally, errorr errorr.144 : ! the basic matrices are combined to get covariances for errorr errorr.145 : ! derived reactions, the matrices are collapsed to the user's errorr errorr.146 : ! group structure, and the results are printed and/or written errorr errorr.147 : ! onto an output gendf tape for later use (see covout). errorr errorr.148 : ! errorr errorr.149 : ! If resonance parameter covariances are present (MF32), they errorr errorr.150 : ! are processed and combined with the MF33 covariances. This errorr errorr.151 : ! coding was taken from ERRORJ developed in Japan. errorr errorr.152 : ! errorr errorr.153 : ! Covariances for angular distributions (MF34) and secondary errorr errorr.154 : ! energy distributions (MF35) can also be processed. errorr errorr.155 : ! errorr errorr.156 : ! 9/17/2012 ... important changes errorr errorr.157 : ! - ngout = input gendf input tape errorr errorr.158 : ! - this tape may contain multiple temperatures, errorr errorr.159 : ! multiple Legendre moments and multiple sigma-0 errorr errorr.160 : ! data, but ... errorr errorr.161 : ! - only the first (infinitely dilute) sigma-0 errorr errorr.162 : ! data will be used. errorr errorr.163 : ! errorr errorr.164 : ! - card 3 is now REQUIRED and the specified temperature must errorr errorr.165 : ! be one of those on the gendf tape. errorr errorr.166 : ! - default values are mprint=1, tempin=300 errorr errorr.167 : ! errorr errorr.168 : !---input specifications (free format)--------------------------- errorr errorr.169 : ! errorr errorr.170 : ! card 1 errorr errorr.171 : ! nendf unit for endf tape errorr errorr.172 : ! npend unit for pendf tape errorr errorr.173 : ! ngout unit for input group xsec (gendf) tape errorr errorr.174 : ! (if zero, group xsecs will be calculated) errorr errorr.175 : ! (if iread eq 2 or if mfcov eq 31, 35 or 40 (see errorr errorr.176 : ! card 7), then ngout cannot be zero) errorr errorr.177 : ! (if mfcov eq 35 (see card 7), errorr errorr.178 : ! ngout cannot be zero) errorr errorr.179 : ! (default=0) errorr errorr.180 : ! nout unit for output covariance tape (default=0) errorr errorr.181 : ! nin unit for input covariance tape (default=0) errorr errorr.182 : ! (nin and nout must be both coded or both binary) errorr errorr.183 : ! nstan unit for ratio-to-standard tape (default=0) errorr errorr.184 : ! errorr errorr.185 : ! card 2 errorr errorr.186 : ! matd material to be processed errorr errorr.187 : ! ign neutron group option errorr errorr.188 : ! (ign definition same as groupr, except ign=19, errorr errorr.189 : ! which means read in an energy grid, as in ign=1, errorr errorr.190 : ! and supplement this with the endf covariance grid errorr errorr.191 : ! within the range of the user-specified energies) errorr errorr.192 : ! (default=1) errorr errorr.193 : ! iwt weight function option (default=6) errorr errorr.194 : ! iprint print option (0/1=minimum/maximum) (default=1) errorr errorr.195 : ! irelco covariance form (0/1=absolute/relative) (default=1) errorr errorr.196 : ! errorr errorr.197 : ! card 3 *** REQIURED for njoy2012_0917 & later *** errorr errorr.198 : ! mprint print option for group averaging (0=min., 1=max.) errorr errorr.199 : ! tempin temperature (default=300) errorr errorr.200 : ! errorr errorr.201 : !---for endf/b version 4 (iverf=4) only-------------------------- errorr errorr.202 : ! errorr errorr.203 : ! card 4 errorr errorr.204 : ! nek number of derived xsec energy ranges errorr errorr.205 : ! (if zero, all xsecs are independent) errorr errorr.206 : ! card 5 (omit if nek=0) errorr errorr.207 : ! ek nek+1 derived xsec energy bounds errorr errorr.208 : ! card 6 (omit if nek=0) errorr errorr.209 : ! akxy derived cross section coefficients, one row/line errorr errorr.210 : ! errorr errorr.211 : !---for endf/b version 5 or 6 (iverf=5 or 6) only------------------------ errorr errorr.212 : ! errorr errorr.213 : ! card 7 errorr errorr.214 : ! iread 0/1/2=program calculated mts/input mts and eks/ errorr errorr.215 : ! calculated mts plus extra mat1-mt1 pairs from input errorr errorr.216 : ! (default=0) errorr errorr.217 : ! mfcov endf covariance file (31, 33, 34, 35 or 40) to be errorr errorr.218 : ! processed (default=33). errorr errorr.219 : ! note--contribution to group cross section errorr errorr.220 : ! covariances from resonance-parameter uncertainties errorr errorr.221 : ! (mf=32) is included when mfcov=33 is specified. errorr errorr.222 : ! (mf=-33) high speed calc for test case errorr errorr.223 : ! (mf=333) hight speed calc for test case (faster) errorr errorr.224 : ! irespr processing for resonance parameter covariances errorr errorr.225 : ! (mf=32) (default=1) errorr errorr.226 : ! 0 = area sensitivity method errorr errorr.227 : ! 1 = 1% sensitivity method errorr errorr.228 : ! legord legendre order for calculating covariances (default=1) errorr errorr.229 : ! (if mfcov is not 34, legord is ignored) errorr errorr.230 : ! ifissp subsection of the fission spectrum covariance errorr errorr.231 : ! matrix to process (default=-1 which means process errorr errorr.232 : ! the subsection that includes efmean). The value errorr errorr.233 : ! for ifissp that appears in njoy's standard output errorr errorr.234 : ! will equal the subsection containing efmean. errorr errorr.235 : ! (if mfcov is not 35, ifissp is ignored) errorr errorr.236 : ! efmean incident neutron energy (eV). Process the covar- errorr errorr.237 : ! iance matrix subsection whose energy interval in- errorr errorr.238 : ! cludes efmean. if ifissp=-1 and efmean is not errorr errorr.239 : ! specified, set efmean=2.e6_kr. But if there is only errorr errorr.240 : ! one subsection, process it and if the input efmean errorr errorr.241 : ! was not within this subsection's energy range then errorr errorr.242 : ! redefine efmean to equal the average energy for errorr errorr.243 : ! this subsection. errorr errorr.244 : ! (if mfcov is not 35, efmean is ignored) errorr errorr.245 : ! dap user specified scattering radius uncertainty, given errorr errorr.246 : ! as a fraction (i.e., dap=0.1 means 10% uncertainty errorr errorr.247 : ! in the scattering radius). The default value is errorr errorr.248 : ! zero. This variable is only defined for mfcov=33 errorr errorr.249 : ! and if non-zero will be used in lieu of any data errorr errorr.250 : ! that might have been read from the nendf tape. errorr errorr.251 : ! errorr errorr.252 : ! following cards only if iread eq 1 errorr errorr.253 : ! card 8 errorr errorr.254 : ! nmt no. mts to be processed errorr errorr.255 : ! nek no. derived cross section energy ranges errorr errorr.256 : ! (if zero, all xsecs are independent) errorr errorr.257 : ! card 8a errorr errorr.258 : ! mts nmt mts errorr errorr.259 : ! card 8b (omit if nek=0) errorr errorr.260 : ! ek nek+1 derived cross section energy bounds errorr errorr.261 : ! card 9 (omit if nek=0) errorr errorr.262 : ! akxy derived cross section coefficients, one row/line errorr errorr.263 : ! errorr errorr.264 : ! following card only if iread eq 2 errorr errorr.265 : ! card 10 errorr errorr.266 : ! mat1 cross-material reaction to be added to errorr errorr.267 : ! mt1 covariance reaction list. errorr errorr.268 : ! repeat for all mat1-mt1 pairs desired errorr errorr.269 : ! terminate with mat1=0. errorr errorr.270 : ! errorr errorr.271 : ! following card only if nstan ne 0 errorr errorr.272 : ! card 11 errorr errorr.273 : ! matb standards reaction referenced errorr errorr.274 : ! mtb in matd. errorr errorr.275 : ! matc standards reaction to be errorr errorr.276 : ! mtc used instead. errorr errorr.277 : ! repeat for all standard reactions to be redefined. errorr errorr.278 : ! terminate with matb=0. errorr errorr.279 : ! note. if matb(1) and mtb(1) are negative, then matc(1) and errorr errorr.280 : ! mtc(1) identify a third reaction, correlated with matd thru errorr errorr.281 : ! the use of the same standard. covariances of all reactions errorr errorr.282 : ! in matd (which reference the standard) with the reaction errorr errorr.283 : ! matc(1)-mtc(1) will be produced. the standard reaction errorr errorr.284 : ! must be identified on card 10 and repeated as the negative errorr errorr.285 : ! entries on card 11. the group xsec tape ngout must include errorr errorr.286 : ! all covariance reactions in matd, plus matc(1)-mtc(1). errorr errorr.287 : ! errorr errorr.288 : ! card 12a (for ign eq 1 or ign eq 19) errorr errorr.289 : ! ngn number of groups errorr errorr.290 : ! card 12b errorr errorr.291 : ! egn ngn+1 group bounds (ev) errorr errorr.292 : ! card 13 (for iwt eq 1 only) errorr errorr.293 : ! wght weight function as a tab1 record errorr errorr.294 : ! card 13b analytic flux parameters (iwt=4 only) errorr errorr.295 : ! eb thermal break (ev) errorr errorr.296 : ! tb thermal temperature (ev) errorr errorr.297 : ! ec fission break (ev) errorr errorr.298 : ! tc fission temperature (ev) errorr errorr.299 : ! errorr errorr.300 : ! ---options for input variables------------------------------------ errorr errorr.301 : ! errorr errorr.302 : ! ign meaning errorr errorr.303 : ! --- ------- errorr errorr.304 : ! 1 arbitrary structure (read in) errorr errorr.305 : ! 2 csewg 239-group structure errorr errorr.306 : ! 3 lanl 30-group structure errorr errorr.307 : ! 4 anl 27-group structure errorr errorr.308 : ! 5 rrd 50-group structure errorr errorr.309 : ! 6 gam-i 68-group structure errorr errorr.310 : ! 7 gam-ii 100-group structure errorr errorr.311 : ! 8 laser-thermos 35-group structure errorr errorr.312 : ! 9 epri-cpm 69-group structure errorr errorr.313 : ! 10 lanl 187-group structure errorr errorr.314 : ! 11 lanl 70-group structure errorr errorr.315 : ! 12 sand-ii 620-group structure errorr errorr.316 : ! 13 lanl 80-group structure errorr errorr.317 : ! 14 eurlib 100-group structure errorr errorr.318 : ! 15 sand-iia 640-group structure errorr errorr.319 : ! 16 vitamin-e 174-group structure errorr errorr.320 : ! 17 vitamin-j 175-group structure errorr errorr.321 : ! 18 xmas 172-group structure errorr errorr.322 : ! 19 read in, supplemented with endf covariance grid errorr errorr.323 : ! errorr errorr.324 : ! iwt meaning errorr errorr.325 : ! --- ------- errorr errorr.326 : ! 1 read in smooth weight function errorr errorr.327 : ! 2 constant errorr errorr.328 : ! 3 1/e errorr errorr.329 : ! 4 1/e + fission spectrum + thermal maxwellian errorr errorr.330 : ! 5 epri-cell lwr errorr errorr.331 : ! 6 (thermal) -- (1/e) -- (fission + fusion) errorr errorr.332 : ! 7 same with t-dep thermal part errorr errorr.333 : ! 8 thermal--1/e--fast reactor--fission + fusion errorr errorr.334 : ! 9 claw weight function errorr errorr.335 : ! 10 claw with t-dependent thermal part errorr errorr.336 : ! 11 vitamin-e weight function (ornl-5505) errorr errorr.337 : ! 12 vit-e with t-dep thermal part errorr errorr.338 : ! errorr errorr.339 : !-------------------------------------------------------------------- errorr COVR covr.50 : subroutine covr covr covr.51 : !-------------------------------------------------------------------- covr covr.52 : ! covr covr.53 : ! Plot covariance data from errorr or make a condensed library. covr covr.54 : ! covr covr.55 : ! In the plot option, covr plots a matrix of correlation covr covr.56 : ! coefficients and an associated pair of standard deviation covr covr.57 : ! vectors, i.e.,a covariance matrix. The correlation covr covr.58 : ! matrix is plotted as a shaded contour plot and the vectors covr covr.59 : ! are plotted as semi-log plots, one rotated by 90 degrees. covr covr.60 : ! The log energy grids for the vector plots are identical covr covr.61 : ! to the grids for the matrix plot. This version plots covr covr.62 : ! through viewr. covr covr.63 : ! covr covr.64 : ! In the library option, covr produces a condensed bcd covr covr.65 : ! covariance library in the boxer format. This format is covr covr.66 : ! efficient for matrices of simple blocks. covr covr.67 : ! covr covr.68 : !---input specifications (free format)--------------------------- covr covr.69 : ! covr covr.70 : ! card 1 covr covr.71 : ! nin input tape unit covr covr.72 : ! nout output tape unit covr covr.73 : ! (default=0=none) covr covr.74 : ! nplot viewr output unit covr covr.75 : ! (default=0=none) covr covr.76 : ! covr covr.77 : ! ---cards 2, 2', 2a, and 3a for nout.le.0 only (plot option) covr covr.78 : ! covr covr.79 : ! card 2 covr covr.80 : ! icolor select color or monochrome style covr covr.81 : ! 0=monochrome (uses cross hatching) covr covr.82 : ! 1=color background and contours covr covr.83 : ! 2=color background and contours plus covr covr.84 : ! card 2' follows. covr covr.85 : ! (default=0) covr covr.86 : ! card 2' (only when icolor=2) covr covr.87 : ! nlev,(tlev(i),i=1,nlev) covr covr.88 : ! defines the number of correlation matrix covr covr.89 : ! intervals and their boundaries. Zero is covr covr.90 : ! assumed as the lower limit of the first covr covr.91 : ! boundary, but the User must specify unity covr covr.92 : ! as the upper limit of the last boundary. covr covr.93 : ! nlev is a positive integer .le. 9. covr covr.94 : ! default values (when icolor=1) are: covr covr.95 : ! 6,0.001,0.1,0.2,0.3,0.6,1.0 covr covr.96 : ! card 2a covr covr.97 : ! epmin lowest energy of interest (default=0.) covr covr.98 : ! card 3a covr covr.99 : ! irelco type of covariances present on nin covr covr.100 : ! 0/1=absolute/relative covariances covr covr.101 : ! (default=1) covr covr.102 : ! ncase no. cases to be run (maximum=60) covr covr.103 : ! (default=1) covr covr.104 : ! noleg plot legend option covr covr.105 : ! -1/0/1=legend for first subcase only/ covr covr.106 : ! legend for all plots/no legends covr covr.107 : ! (default=0) covr covr.108 : ! nstart sequential figure number covr covr.109 : ! 0/n=not needed/first figure is figure n. covr covr.110 : ! (default=1) covr covr.111 : ! ndiv no. of subdivisions of each of the covr covr.112 : ! gray shades (default=1) covr covr.113 : ! covr covr.114 : ! ---cards 2b, 3b, and 3c for nout gt 0 (library option) only-- covr covr.115 : ! covr covr.116 : ! card 2b covr covr.117 : ! matype output library matrix option covr covr.118 : ! 3/4=covariances/correlations covr covr.119 : ! (default=3) covr covr.120 : ! ncase no. cases to be run (maximum=ncasemx=100) covr covr.121 : ! (default=1) covr covr.122 : ! card 3b covr covr.123 : ! hlibid up to 6 characters for identification covr covr.124 : ! card 3c covr covr.125 : ! hdescr up to 21 characters of descriptive covr covr.126 : ! information covr covr.127 : ! covr covr.128 : ! ---cards 4 for both options--- covr covr.129 : ! covr covr.130 : ! card 4 covr covr.131 : ! mat desired mat number covr covr.132 : ! mt desired mt number covr covr.133 : ! mat1 desired mat1 number covr covr.134 : ! mt1 desired mt1 number covr covr.135 : ! (default for mt, mat1 and mt1 are 0,0,0 covr covr.136 : ! meaning process all mts for this mat covr covr.137 : ! with mat1=mat) covr covr.138 : ! (neg. values for mt, mat1, and mt1 mean covr covr.139 : ! process all mts for this mat, except for covr covr.140 : ! the mt-numbers -mt, -mat1, and -mt1. in covr covr.141 : ! general, -n will strip both mt=1 and mt=n. covr covr.142 : ! -4 will strip mt=1, mt=3, and mt=4, and covr covr.143 : ! -62, for example, will strip mt=1, mt=62, covr covr.144 : ! mt=63, ... up to and incl. mt=90.) covr covr.145 : ! repeat card 4 ncase times covr covr.146 : ! covr covr.147 : ! note---if more than one material appears on the input tape, covr covr.148 : ! the mat numbers must be in ascending order. covr covr.149 : ! covr covr.150 : !-------------------------------------------------------------------- covr MODER moder.14 : subroutine moder moder moder.15 : !------------------------------------------------------------------- moder moder.16 : ! moder moder.17 : ! Change the mode of an ENDF tape. moder moder.18 : ! moder moder.19 : ! Converts ENDF-type files between binary and text formats. moder moder.20 : ! Also works for PENDF, GENDF and covariance tapes. moder moder.21 : ! Moder can also be used to select materials from an ENDF-type moder moder.22 : ! tape, or to merge several materials into a new tape. moder moder.23 : ! moder moder.24 : !---input specifications (free format)--------------------------- moder moder.25 : ! moder moder.26 : ! card 1 unit numbers moder moder.27 : ! nin input unit moder moder.28 : ! nout output unit moder moder.29 : ! moder moder.30 : ! a positive unit is coded (mode 3). moder moder.31 : ! a negative unit is blocked binary (njoy mode). moder moder.32 : ! moder moder.33 : ! note: abs(nin) ge 1 and le 19 is a flag to select various moder moder.34 : ! materials from one or more input tapes, with or moder moder.35 : ! without mode conversion. the kind of data to be moder moder.36 : ! processed is keyed to nin as follows: moder moder.37 : ! nin=1, for endf or pendf input and output, moder moder.38 : ! 2, for gendf input and output, moder moder.39 : ! 3, for errorr-format input and output. moder moder.40 : ! moder moder.41 : ! cards 2 and 3 for abs (nin) ge 1 and le 19 only. moder moder.42 : ! moder moder.43 : ! card 2 moder moder.44 : ! tpid tapeid for nout. 66 characters allowed moder moder.45 : ! (delimited with *, ended with /) moder moder.46 : ! card 3 moder moder.47 : ! nin input unit moder moder.48 : ! terminate moder by setting nin=0 moder moder.49 : ! matd material on this tape to add to nout moder moder.50 : !------------------------------------------------------------------- moder DTFR dtfr.53 : subroutine dtfr dtfr dtfr.54 : !------------------------------------------------------------------- dtfr dtfr.55 : ! dtfr dtfr.56 : ! convert output of groupr to dtf format. dtfr dtfr.57 : ! dtfr dtfr.58 : ! Processes neutron and gamma production cross sections and dtfr dtfr.59 : ! matrices. The neutron tables can have reduced table length. dtfr dtfr.60 : ! Up-scatter is allowed. The absorption reaction is computed dtfr dtfr.61 : ! from the total cross section and total scattering. Any edits dtfr dtfr.62 : ! can be produced which are either given in the ENDF file dtfr dtfr.63 : ! or are linear combinations of ENDF cross sections. The dtfr dtfr.64 : ! fission nu*sigf and chi are computed from the fission matrices dtfr dtfr.65 : ! for all partial fission reactions. Chi includes source dtfr dtfr.66 : ! weighting. The Pl tables for l.gt.0 contain the Pl weighted dtfr dtfr.67 : ! total in the total position and the pl transport cross section dtfr dtfr.68 : ! in the absorption position. The gamma tables have gamma group dtfr dtfr.69 : ! 1 in position 1, 2 in position 2, etc, with a table length dtfr dtfr.70 : ! equal to the number of gamma groups. dtfr dtfr.71 : ! dtfr dtfr.72 : ! Plots can be prepared in viewr format. dtfr dtfr.73 : ! dtfr dtfr.74 : !---input specifications (free format)--------------------------- dtfr dtfr.75 : ! dtfr dtfr.76 : ! card 1 units dtfr dtfr.77 : ! nin input unit with data from groupr (binary). dtfr dtfr.78 : ! nout output unit containing dtf tables (coded). dtfr dtfr.79 : ! (default=0=none) dtfr dtfr.80 : ! npend input unit with pendf tape for point plots. dtfr dtfr.81 : ! (default=0=none) dtfr dtfr.82 : ! nplot output plot info for plotr module dtfr dtfr.83 : ! (default=0=none) dtfr dtfr.84 : ! card 2 options dtfr dtfr.85 : ! iprint print control (0 minimum, 1 maximum) dtfr dtfr.86 : ! ifilm film control (0/1/2=no/yes with 1 plot per frame/ dtfr dtfr.87 : ! yes with 4 plots per frame (default=0) dtfr dtfr.88 : ! iedit edit control (0/1=in table/separate) (default=0) dtfr dtfr.89 : ! dtfr dtfr.90 : ! cards 3 through 5 only for iedit=0 dtfr dtfr.91 : ! dtfr dtfr.92 : ! card 3 neutron tables dtfr dtfr.93 : ! nlmax number of neutron tables desired. dtfr dtfr.94 : ! ng number of neutron groups dtfr dtfr.95 : ! iptotl position of total cross section dtfr dtfr.96 : ! ipingp position of in-group scattering cross section. dtfr dtfr.97 : ! itabl neutron table length desired. dtfr dtfr.98 : ! ned number of entries in edit table (default=0). dtfr dtfr.99 : ! ntherm number of thermal groups (default=0). dtfr dtfr.100 : ! card 3a only for ntherm ne 0 dtfr dtfr.101 : ! card 3a thermal incoherent and coherent mts dtfr dtfr.102 : ! mti mt for thermal incoherent data dtfr dtfr.103 : ! mtc mt for thermal coherent data (default=0) dtfr dtfr.104 : ! nlc no. coherent legendre orders (default=0) dtfr dtfr.105 : ! card 4 edit names dtfr dtfr.106 : ! six character hollerith names for edits for as many dtfr dtfr.107 : ! cards as needed. there will be iptotl-3 names read. dtfr dtfr.108 : ! each name is delimited with *. dtfr dtfr.109 : ! card 5 edit specifications dtfr dtfr.110 : ! ned triplets of numbers on as many cards as needed. dtfr dtfr.111 : ! positions can appear more than once. dtfr dtfr.112 : ! reaction types can appear more than once. dtfr dtfr.113 : ! jpos position of edit quantity. dtfr dtfr.114 : ! mt endf reaction number. dtfr dtfr.115 : ! mult multiplicity to be used when adding this mt. dtfr dtfr.116 : ! dtfr dtfr.117 : ! card 6 for iedit=1 dtfr dtfr.118 : ! dtfr dtfr.119 : ! card 6 claw-format tables dtfr dtfr.120 : ! nlmax number of neutron tables (def=5) dtfr dtfr.121 : ! ng number of neutron groups (def=30) dtfr dtfr.122 : ! (number of thermal groups is zero) dtfr dtfr.123 : ! dtfr dtfr.124 : ! card 7 gamma ray tables dtfr dtfr.125 : ! nptabl number of gamma tables desired (default=0) dtfr dtfr.126 : ! ngp number of gamma groups (default=0) dtfr dtfr.127 : ! card 8 material description dtfr dtfr.128 : ! one card for each table set desired. dtfr dtfr.129 : ! empty card (/) terminates execution of dtfr. dtfr dtfr.130 : ! hisnam 6-character isotope name dtfr dtfr.131 : ! mat material number as in endf (default=0) dtfr dtfr.132 : ! jsigz index number of sigma-zero desired (default=1) dtfr dtfr.133 : ! dtemp temperature desired (default=300) dtfr dtfr.134 : ! dtfr dtfr.135 : !------------------------------------------------------------------- dtfr CCCCR ccccr.76 : subroutine ccccr ccccr ccccr.77 : !-------------------------------------------------------------------- ccccr ccccr.78 : ! ccccr ccccr.79 : ! Produce CCCC-IV files from njoy intermediate cross section ccccr ccccr.80 : ! library. ccccr ccccr.81 : ! ccccr ccccr.82 : ! Working from a groupr output tape, this module produces ccccr ccccr.83 : ! the following three standard interface files, ccccr ccccr.84 : ! ccccr ccccr.85 : ! ISOTXS BRKOXS DLAYXS, ccccr ccccr.86 : ! ccccr ccccr.87 : ! as specified by the committee for computer code coordination ccccr ccccr.88 : ! (CCCC), to facilitate the exchange of nuclear data for reactor ccccr ccccr.89 : ! calculations (Reference 1). ccccr ccccr.90 : ! In a given run, all three files can be produced using the ccccr ccccr.91 : ! same user-specified list of isotopes. The code will ignore ccccr ccccr.92 : ! isotopes which are not present on the groupr tape (and in the ccccr ccccr.93 : ! case of DLAYXS, isotopes without delayed neutron data). ccccr ccccr.94 : ! The ISOTXS coding allows for NSBLK equal to one or ngroup. ccccr ccccr.95 : ! In addition, files with higher order matrices can be produced ccccr ccccr.96 : ! with a separate block for each l-order (ifopt=2) or with all ccccr ccccr.97 : ! orders in one block (ifopt=1). This flexibility accommodates ccccr ccccr.98 : ! large group structures. Fission vectors or fission ccccr ccccr.99 : ! matrices can be produced. ccccr ccccr.100 : ! In BRKOXS, the potential scattering cross section for all ccccr ccccr.101 : ! energy groups is equal to the user-input value (xspo). ccccr ccccr.102 : ! The elastic removal f-factor is supplied as the sixth reaction. ccccr ccccr.103 : ! ccccr ccccr.104 : ! 1. R.D.Odell. Standard Interface Files and Procedures ccccr ccccr.105 : ! for Reactor Physics Codes, Version IV, ccccr ccccr.106 : ! LANL report LA-6941-MS (Sept.77) ccccr ccccr.107 : ! ccccr ccccr.108 : ! ccccr ccccr.109 : !---input specifications (free format)--------------------------- ccccr ccccr.110 : ! ccccr ccccr.111 : !-ccccr- ccccr ccccr.112 : ! card 1 units ccccr ccccr.113 : ! nin input unit for data from groupr ccccr ccccr.114 : ! nisot output unit for isotxs (0 if isotxs not wanted) ccccr ccccr.115 : ! nbrks output unit for brkoxs (0 if brkoxs not wanted) ccccr ccccr.116 : ! ndlay output unit for dlayxs (0 if dlayxs not wanted) ccccr ccccr.117 : ! card 2 identification ccccr ccccr.118 : ! lprint print flag (0/1=not print/printed) ccccr ccccr.119 : ! ivers file version number (default=0) ccccr ccccr.120 : ! huse user identification (12 characters) ccccr ccccr.121 : ! delimited by *, ended by /. ccccr ccccr.122 : ! (default=blank) ccccr ccccr.123 : ! card 3 ccccr ccccr.124 : ! hsetid hollerith identification of set (12 characters) ccccr ccccr.125 : ! delimited by *, ended by /. ccccr ccccr.126 : ! (default=blank) ccccr ccccr.127 : ! card 4 file control ccccr ccccr.128 : ! ngroup number of neutron energy groups ccccr ccccr.129 : ! nggrup number of gamma energy groups ccccr ccccr.130 : ! niso number of isotopes desire ccccr ccccr.131 : ! maxord maximum legendre order ccccr ccccr.132 : ! ifopt matrix blocking option (1/2=blocking by ccccr ccccr.133 : ! reaction/legendre order) ccccr ccccr.134 : ! card 5 isotope parameters (one card per isotope) ccccr ccccr.135 : ! (first four words are hollerith, up to six characters ccccr ccccr.136 : ! each, delimited by *) ccccr ccccr.137 : ! hisnm hollerith isotope label ccccr ccccr.138 : ! habsid hollerith absolute isotope label ccccr ccccr.139 : ! hident identifier of data source library (endf) ccccr ccccr.140 : ! hmat isotope identification ccccr ccccr.141 : ! imat numerical isotope identifier (endf mat number) ccccr ccccr.142 : ! xspo average potential scattering cross sect. (brkoxs) ccccr ccccr.143 : ! ccccr ccccr.144 : !-cisotx- (only if nisot.gt.0) ccccr ccccr.145 : ! card 1 file control ccccr ccccr.146 : ! nsblok subblocking option for scattering matrix ccccr ccccr.147 : ! (1 or ngrup sub-blocks allowed) ccccr ccccr.148 : ! maxup maximum number of upscatter groups (always zero) ccccr ccccr.149 : ! maxdn maximum number of downscatter groups ccccr ccccr.150 : ! ichix fission chi representation ccccr ccccr.151 : ! -1 vector (using groupr flux) ccccr ccccr.152 : ! 0 none ccccr ccccr.153 : ! +1 vector (using input flux) ccccr ccccr.154 : ! .gt.1 matrix ccccr ccccr.155 : ! card 2 chi vector control (ichix=1 only) ccccr ccccr.156 : ! spec ngroup flux values used to collapse the groupr ccccr ccccr.157 : ! fission matrix into a chi vector ccccr ccccr.158 : ! card 3 chi matrix control (ichix.gt.1 only) ccccr ccccr.159 : ! spec ngroup values of spec(i)=k define the range of ccccr ccccr.160 : ! groups i to be averaged to obtain spectrum k. ccccr ccccr.161 : ! index k ranges from 1 to ichi. ccccr ccccr.162 : ! the model flux is used to weight each group i. ccccr ccccr.163 : ! card 4 isotope control (one card per isotope) ccccr ccccr.164 : ! kbr isotope classification ccccr ccccr.165 : ! amass gram atomic weight ccccr ccccr.166 : ! efiss total thermal energy/fission ccccr ccccr.167 : ! ecapt total thermal energy/capture ccccr ccccr.168 : ! temp isotope temperature ccccr ccccr.169 : ! sigpot average effective potential scattering ccccr ccccr.170 : ! adens density of isotope in mixture ccccr ccccr.171 : ! ccccr ccccr.172 : !-cbrkxs- (only if nbrks.gt.0) ccccr ccccr.173 : ! card 1 (2i6) file data ccccr ccccr.174 : ! nti number of temperatures desired ccccr ccccr.175 : ! (-n means accept first n temperatures) ccccr ccccr.176 : ! nzi number of sigpo values desire ccccr ccccr.177 : ! (-n means accept first n dilution factors) ccccr ccccr.178 : ! card 2 (not needed if nti.lt.0) ccccr ccccr.179 : ! atem(nti) values of desired temperatures ccccr ccccr.180 : ! card 3 (not needed if nzi.lt.0) ccccr ccccr.181 : ! asig(nzi) values of desired sigpo ccccr ccccr.182 : ! ccccr ccccr.183 : !-cdlayx-- no input required ccccr ccccr.184 : ! ccccr ccccr.185 : !-------------------------------------------------------------------- ccccr MATXSR matxsr.56 : subroutine matxsr matxsr matxsr.57 : !------------------------------------------------------------------- matxsr matxsr.58 : ! matxsr matxsr.59 : ! Produce MATXS interface file from NJOY intermediate cross matxsr matxsr.60 : ! section data from group or gaminr. matxsr matxsr.61 : ! matxsr matxsr.62 : ! The matxs file uses a generalized, flexible format based on matxsr matxsr.63 : ! the CCCC interface conventions. Working from groupr and/or matxsr matxsr.64 : ! gaminr output tapes, this module can process neutron, matxsr matxsr.65 : ! thermal, photon, and charged-particle data into a matxsr matxsr.66 : ! single output file. This file can then be used by the matxsr matxsr.67 : ! TRANSX code to prepare data libraries for transport codes. matxsr matxsr.68 : ! matxsr matxsr.69 : ! A MATXS file specification may be found following the matxsr matxsr.70 : ! input instructions. matxsr matxsr.71 : ! matxsr matxsr.72 : !---input specifications (free format)--------------------------- matxsr matxsr.73 : ! matxsr matxsr.74 : ! card 1 units matxsr matxsr.75 : ! ngen1 input unit for data from groupr matxsr matxsr.76 : ! ngen2 input unit for data from gaminr matxsr matxsr.77 : ! nmatx output unit for matxs matxsr matxsr.78 : ! ngen3 incident proton data from groupr (default=0) matxsr matxsr.79 : ! ngen4 incident deuteron data from groupr (default=0) matxsr matxsr.80 : ! ngen5 incident triton data from groupr (default=0) matxsr matxsr.81 : ! ngen6 incident he3 data from groupr (default=0) matxsr matxsr.82 : ! ngen7 incident alpha data from groupr (default=0) matxsr matxsr.83 : ! ngen8 photonuclear data from groupr (default=0) matxsr matxsr.84 : ! card 2 user identification matxsr matxsr.85 : ! ivers file version number (default=0) matxsr matxsr.86 : ! huse user id (up to 16 characters, delimited by *, matxsr matxsr.87 : ! ended by /) (default=blank) matxsr matxsr.88 : ! card 3 file control matxsr matxsr.89 : ! npart number of particles for which group matxsr matxsr.90 : ! structures are given matxsr matxsr.91 : ! ntype number of data types in set matxsr matxsr.92 : ! nholl number of cards to be read for hollerith matxsr matxsr.93 : ! identification record. matxsr matxsr.94 : ! nmat number of materials desired matxsr matxsr.95 : ! card 4 set hollerith identification matxsr matxsr.96 : ! hsetid hollerith identification of set matxsr matxsr.97 : ! (each line can be up to 72 characters, matxsr matxsr.98 : ! delimited with *, ended by /) matxsr matxsr.99 : ! card 5 particle identifiers matxsr matxsr.100 : ! hpart hollerith identifiers for particles matxsr matxsr.101 : ! (up to 8 characters each) matxsr matxsr.102 : ! card 6 energy groups matxsr matxsr.103 : ! ngrp number of groups for each particle matxsr matxsr.104 : ! card 7 data type identifiers matxsr matxsr.105 : ! htype hollerith identifiers for data types matxsr matxsr.106 : ! (up to 8 characters each) matxsr matxsr.107 : ! card 8 input particle ids matxsr matxsr.108 : ! jinp input particle id for each data type matxsr matxsr.109 : ! card 9 output particle ids matxsr matxsr.110 : ! joutp output particle id for each data type matxsr matxsr.111 : ! card 10 material data (one card per material) matxsr matxsr.112 : ! hmat hollerith material identifier matxsr matxsr.113 : ! (up to 8 characters each) matxsr matxsr.114 : ! matno integer material identifier matxsr matxsr.115 : ! (endf mat number) matxsr matxsr.116 : ! matgg mat number for photoatomic data matxsr matxsr.117 : ! (default=100*(matno/100) as in endf-6) matxsr matxsr.118 : ! matxsr matxsr.119 : !------------------------------------------------------------------- matxsr matxsr.120 : matxsr matxsr.121 : ! Standardized CCCC format listing for MATXS file matxsr matxsr.122 : !c matxsr matxsr.123 : !c********************************************************************** matxsr matxsr.124 : !c proposed 09/09/77 matxsr matxsr.125 : !c (modified 09/80) matxsr matxsr.126 : !c (nomenclature changed 06/88) matxsr matxsr.127 : !c (modified for const sub-blocks 06/90) matxsr matxsr.128 : !c (ordering changed 10/90) matxsr matxsr.129 : !c c (bcd format changed 12/21/91) matxsr matxsr.130 : !c matxsr matxsr.131 : !cf matxs matxsr matxsr.132 : !ce material cross section file matxsr matxsr.133 : !c matxsr matxsr.134 : !cn this file contains cross section matxsr matxsr.135 : !cn vectors and matrices for all matxsr matxsr.136 : !cn particles, materials, and reactions; matxsr matxsr.137 : !cn delayed neutron spectra by time group; matxsr matxsr.138 : !cn and decay heat and photon spectra. matxsr matxsr.139 : !c matxsr matxsr.140 : !cn formats given are for file exchange only matxsr matxsr.141 : !c matxsr matxsr.142 : !c********************************************************************** matxsr matxsr.143 : !c matxsr matxsr.144 : !c matxsr matxsr.145 : !c---------------------------------------------------------------------- matxsr matxsr.146 : !cs file structure matxsr matxsr.147 : !cs matxsr matxsr.148 : !cs record type present if matxsr matxsr.149 : !cs ============================== =============== matxsr matxsr.150 : !cs file identification always matxsr matxsr.151 : !cs file control always matxsr matxsr.152 : !cs set hollerith identification always matxsr matxsr.153 : !cs file data always matxsr matxsr.154 : !cs matxsr matxsr.155 : !cs *************(repeat for all particles) matxsr matxsr.156 : !cs * group structures always matxsr matxsr.157 : !cs ************* matxsr matxsr.158 : !cs matxsr matxsr.159 : !cs *************(repeat for all materials) matxsr matxsr.160 : !cs * material control always matxsr matxsr.161 : !cs * matxsr matxsr.162 : !cs * ***********(repeat for all submaterials) matxsr matxsr.163 : !cs * * vector control n1db.gt.0 matxsr matxsr.164 : !cs * * matxsr matxsr.165 : !cs * * *********(repeat for all vector blocks) matxsr matxsr.166 : !cs * * * vector block n1db.gt.0 matxsr matxsr.167 : !cs * * ********* matxsr matxsr.168 : !cs * * matxsr matxsr.169 : !cs * * *********(repeat for all matrix blocks) matxsr matxsr.170 : !cs * * * matrix control n2d.gt.0 matxsr matxsr.171 : !cs * * * matxsr matxsr.172 : !cs * * * *******(repeat for all sub-blocks) matxsr matxsr.173 : !cs * * * * matrix sub-block n2d.gt.0 matxsr matxsr.174 : !cs * * * ******* matxsr matxsr.175 : !cs * * * matxsr matxsr.176 : !cs * * * constant sub-block jconst.gt.0 matxsr matxsr.177 : !cs * * * matxsr matxsr.178 : !cs ************* matxsr matxsr.179 : !c matxsr matxsr.180 : !c---------------------------------------------------------------------- matxsr matxsr.181 : !c matxsr matxsr.182 : !c matxsr matxsr.183 : !c---------------------------------------------------------------------- matxsr matxsr.184 : !cr file identification matxsr matxsr.185 : !c matxsr matxsr.186 : !cl hname,(huse(i),i=1,2),ivers matxsr matxsr.187 : !c matxsr matxsr.188 : !cw 1+3*mult matxsr matxsr.189 : !c matxsr matxsr.190 : !cb format(4h 0v ,a8,1h*,2a8,1h*,i6) matxsr matxsr.191 : !c matxsr matxsr.192 : !cd hname hollerith file name - matxs - (a8) matxsr matxsr.193 : !cd huse hollerith user identifiation (a8) matxsr matxsr.194 : !cd ivers file version number matxsr matxsr.195 : !cd mult double precision parameter matxsr matxsr.196 : !cd 1- a8 word is single word matxsr matxsr.197 : !cd 2- a8 word is double precision word matxsr matxsr.198 : !c matxsr matxsr.199 : !c---------------------------------------------------------------------- matxsr matxsr.200 : !c matxsr matxsr.201 : !c matxsr matxsr.202 : !c---------------------------------------------------------------------- matxsr matxsr.203 : !cr file control matxsr matxsr.204 : !c matxsr matxsr.205 : !cl npart,ntype,nholl,nmat,maxw,length matxsr matxsr.206 : !c matxsr matxsr.207 : !cw 6 matxsr matxsr.208 : !c matxsr matxsr.209 : !cb format(6h 1d ,6i6) matxsr matxsr.210 : !c matxsr matxsr.211 : !cd npart number of particles for which group matxsr matxsr.212 : !cd structures are given matxsr matxsr.213 : !cd ntype number of data types present in set matxsr matxsr.214 : !cd nholl number of words in set hollerith matxsr matxsr.215 : !cd identification record matxsr matxsr.216 : !cd nmat number of materials on file matxsr matxsr.217 : !cd maxw maximum record size for sub-blocking matxsr matxsr.218 : !cd length length of file matxsr matxsr.219 : !c matxsr matxsr.220 : !c---------------------------------------------------------------------- matxsr matxsr.221 : !c matxsr matxsr.222 : !c matxsr matxsr.223 : !c---------------------------------------------------------------------- matxsr matxsr.224 : !cr set hollerith identification matxsr matxsr.225 : !c matxsr matxsr.226 : !cl (hsetid(i),i=1,nholl) matxsr matxsr.227 : !c matxsr matxsr.228 : !cw nholl*mult matxsr matxsr.229 : !c matxsr matxsr.230 : !cb format(4h 2d /(9a8)) matxsr matxsr.231 : !c matxsr matxsr.232 : !cd hsetid hollerith identification of set (a8) matxsr matxsr.233 : !cd (to be edited out 72 characters per line) matxsr matxsr.234 : !c matxsr matxsr.235 : !c---------------------------------------------------------------------- matxsr matxsr.236 : !c matxsr matxsr.237 : !c matxsr matxsr.238 : !c---------------------------------------------------------------------- matxsr matxsr.239 : !cr file data matxsr matxsr.240 : !c matxsr matxsr.241 : !cl (hprt(j),j=1,npart),(htype(k),k=1,ntype),(hmatn(i),i=1,nmat), matxsr matxsr.242 : !cl 1(ngrp(j),j=1,npart),(jinp(k),k=1,ntype,(joutp(k),k=1,ntype), matxsr matxsr.243 : !cl 2(nsubm(i)i=1,nmat),(locm(i),i=1,nmat) matxsr matxsr.244 : !c matxsr matxsr.245 : !cw (npart+ntype+nmat)*mult+2*ntype+npart+2*nmat matxsr matxsr.246 : !c matxsr matxsr.247 : !cb format(4h 3d ,4x,8a8/(9a8)) hprt,htype,hmatn matxsr matxsr.248 : !cb format(12i6) ngrp,jinp,joutp,nsubm,locm matxsr matxsr.249 : !c matxsr matxsr.250 : !cd hprt(j) hollerith identification for particle j matxsr matxsr.251 : !cd n neutron matxsr matxsr.252 : !cd g gamma matxsr matxsr.253 : !cd p proton matxsr matxsr.254 : !cd d deuteron matxsr matxsr.255 : !cd t triton matxsr matxsr.256 : !cd h he-3 nucleus matxsr matxsr.257 : !cd a alpha (he-4 nucleus) matxsr matxsr.258 : !cd b beta matxsr matxsr.259 : !cd r residual or recoil matxsr matxsr.260 : !cd (heavier than alpha) matxsr matxsr.261 : !cd htype(k) hollerith identification for data type k matxsr matxsr.262 : !cd nscat neutron scattering matxsr matxsr.263 : !cd ng neutron induced gamma production matxsr matxsr.264 : !cd gscat gamma scattering (atomic) matxsr matxsr.265 : !cd gg gamma scattering (photonuclear) matxsr matxsr.266 : !cd pn proton induced neutron production matxsr matxsr.267 : !cd . . matxsr matxsr.268 : !cd . . matxsr matxsr.269 : !cd . . matxsr matxsr.270 : !cd dkn delayed neutron data matxsr matxsr.271 : !cd dkhg decay heat and gamma data matxsr matxsr.272 : !cd dkb decay beta data matxsr matxsr.273 : !cd hmatn(i) hollerith identification for material i matxsr matxsr.274 : !cd ngrp(j) number of energy groups for particle j matxsr matxsr.275 : !cd jinp(k) type of incident particle associated with matxsr matxsr.276 : !cd data type k. for dk data types, jinp is 0. matxsr matxsr.277 : !cd joutp(k) type of outgoing particle associated with matxsr matxsr.278 : !cd data type k matxsr matxsr.279 : !cd nsubm(i) number of submaterials for material i matxsr matxsr.280 : !cd locm(i) location of material i matxsr matxsr.281 : !c matxsr matxsr.282 : !c---------------------------------------------------------------------- matxsr matxsr.283 : !c matxsr matxsr.284 : !c matxsr matxsr.285 : !c---------------------------------------------------------------------- matxsr matxsr.286 : !cr group structure matxsr matxsr.287 : !c matxsr matxsr.288 : !cl (gpb(i),i=1,ngr),emin matxsr matxsr.289 : !c matxsr matxsr.290 : !cc ngr=ngrp(j) matxsr matxsr.291 : !c matxsr matxsr.292 : !cw ngrp(j)+1 matxsr matxsr.293 : !c matxsr matxsr.294 : !cb format(4h 4d ,8x,1p,5e12.5/(6e12.5)) matxsr matxsr.295 : !c matxsr matxsr.296 : !cd gpb(i) maximum energy bound for group i for particle j matxsr matxsr.297 : !cd emin minimum energy bound for particle j matxsr matxsr.298 : !c matxsr matxsr.299 : !c---------------------------------------------------------------------- matxsr matxsr.300 : !c matxsr matxsr.301 : !c matxsr matxsr.302 : !c---------------------------------------------------------------------- matxsr matxsr.303 : !cr material control matxsr matxsr.304 : !c matxsr matxsr.305 : !cl hmat,amass,(temp(i),sigz(i),itype(i),n1d(i),n2d(i), matxsr matxsr.306 : !cl 1locs(i),i=1,nsubm) matxsr matxsr.307 : !c matxsr matxsr.308 : !cw mult+1+6*nsubm matxsr matxsr.309 : !c matxsr matxsr.310 : !cb format(4h 5d ,a8,1p,2e12.5/(2e12.5,5i6)) matxsr matxsr.311 : !c matxsr matxsr.312 : !cd hmat hollerith material identifier matxsr matxsr.313 : !cd amass atomic weight ratio matxsr matxsr.314 : !cd temp ambient temperature or other parameters for matxsr matxsr.315 : !cd submaterial i matxsr matxsr.316 : !cd sigz dilution factor or other parameters for matxsr matxsr.317 : !cd submaterial i matxsr matxsr.318 : !cd itype data type for submaterial i matxsr matxsr.319 : !cd n1d number of vectors for submaterial i matxsr matxsr.320 : !cd n2d number of matrix blocks for submaterial i matxsr matxsr.321 : !cd locs location of submaterial i matxsr matxsr.322 : !c matxsr matxsr.323 : !c---------------------------------------------------------------------- matxsr matxsr.324 : !c matxsr matxsr.325 : !c matxsr matxsr.326 : !c---------------------------------------------------------------------- matxsr matxsr.327 : !cr vector control matxsr matxsr.328 : !c matxsr matxsr.329 : !cl (hvps(i),i=1,n1d),(nfg(i),i=1,n1d),(nlg(i),i=1,n1d) matxsr matxsr.330 : !c matxsr matxsr.331 : !cw (mult+2)*n1d matxsr matxsr.332 : !c matxsr matxsr.333 : !cb format(4h 6d ,4x,8a8/(9a8)) hvps matxsr matxsr.334 : !cb format(12i6) iblk,nfg,nlg matxsr matxsr.335 : !c matxsr matxsr.336 : !cd hvps(i) hollerith identifier of vector matxsr matxsr.337 : !cd nelas neutron elastic scattering matxsr matxsr.338 : !cd n2n (n,2n) matxsr matxsr.339 : !cd nnf second chance fission matxsr matxsr.340 : !cd gabs gamma absorption matxsr matxsr.341 : !cd p2n protons in, 2 neutrons out matxsr matxsr.342 : !cd . . matxsr matxsr.343 : !cd . . matxsr matxsr.344 : !cd . . matxsr matxsr.345 : !cd nfg(i) number of first group in band for vector i matxsr matxsr.346 : !cd nlg(i) number of last group in band for vector i matxsr matxsr.347 : !c matxsr matxsr.348 : !c---------------------------------------------------------------------- matxsr matxsr.349 : !c matxsr matxsr.350 : !c matxsr matxsr.351 : !c---------------------------------------------------------------------- matxsr matxsr.352 : !cr vector block matxsr matxsr.353 : !c matxsr matxsr.354 : !cl (vps(i),i=1,kmax) matxsr matxsr.355 : !c matxsr matxsr.356 : !cc kmax=sum over group band for each vector in block j matxsr matxsr.357 : !c matxsr matxsr.358 : !cw kmax matxsr matxsr.359 : !c matxsr matxsr.360 : !cb format(4h 7d ,8x,1p,5e12.5/(6e12.5)) matxsr matxsr.361 : !c matxsr matxsr.362 : !cd vps(i) data for group bands for vectors in block j. matxsr matxsr.363 : !cd block size is determined by taking all the group matxsr matxsr.364 : !cd bands that have a total length less than or equal matxsr matxsr.365 : !cd to maxw. matxsr matxsr.366 : !c matxsr matxsr.367 : !c---------------------------------------------------------------------- matxsr matxsr.368 : !c matxsr matxsr.369 : !c matxsr matxsr.370 : !c---------------------------------------------------------------------- matxsr matxsr.371 : !cr scattering matrix control matxsr matxsr.372 : !c matxsr matxsr.373 : !cl hmtx,lord,jconst, matxsr matxsr.374 : !cl 1(jband(l),l=1,noutg(k)),(ijj(l),l=1,noutg(k)) matxsr matxsr.375 : !c matxsr matxsr.376 : !cw mult+2+2*noutg(k) matxsr matxsr.377 : !c matxsr matxsr.378 : !cb format(4h 8d ,4x,a8/(12i6)) hmtx,lord,jconst, matxsr matxsr.379 : !cb jband,ijj matxsr matxsr.380 : !c matxsr matxsr.381 : !cd hmtx hollerith identification of block matxsr matxsr.382 : !cd lord number of orders present matxsr matxsr.383 : !cd jconst number of groups with constant spectrum matxsr matxsr.384 : !cd jband(l) bandwidth for group l matxsr matxsr.385 : !cd ijj(l) lowest group in band for group l matxsr matxsr.386 : !c matxsr matxsr.387 : !c---------------------------------------------------------------------- matxsr matxsr.388 : !c matxsr matxsr.389 : !c matxsr matxsr.390 : !c---------------------------------------------------------------------- matxsr matxsr.391 : !cr scattering sub-block matxsr matxsr.392 : !c matxsr matxsr.393 : !cl (scat(k),k=1,kmax) matxsr matxsr.394 : !c matxsr matxsr.395 : !cc kmax=lord times the sum over all jband in the group range of matxsr matxsr.396 : !cc this sub-block matxsr matxsr.397 : !c matxsr matxsr.398 : !cb format(4h 9d ,8x,1p,5e12.5/(6e12.5)) matxsr matxsr.399 : !c matxsr matxsr.400 : !cw kmax matxsr matxsr.401 : !c matxsr matxsr.402 : !cd scat(k) matrix data given as bands of elements for initial matxsr matxsr.403 : !cd groups that lead to each final group. the order matxsr matxsr.404 : !cd of the elements is as follows: band for p0 of matxsr matxsr.405 : !cd group i, band for p1 of group i, ... , band for p0 matxsr matxsr.406 : !cd of group i+1, band for p1 of group i+1, etc. the matxsr matxsr.407 : !cd groups in each band are given in descending order. matxsr matxsr.408 : !cd the size of each sub-block is determined by the matxsr matxsr.409 : !cd total length of a group of bands that is less than matxsr matxsr.410 : !cd or equal to maxw. matxsr matxsr.411 : !cd matxsr matxsr.412 : !cd if jconst.gt.0, the contributions from the jconst matxsr matxsr.413 : !cd low-energy groups are given separately. matxsr matxsr.414 : !c matxsr matxsr.415 : !c---------------------------------------------------------------------- matxsr matxsr.416 : !c matxsr matxsr.417 : !c matxsr matxsr.418 : !c---------------------------------------------------------------------- matxsr matxsr.419 : !cr constant sub-block matxsr matxsr.420 : !c matxsr matxsr.421 : !cl (spec(l),l=1,noutg(k)),(prod(l),l=l1,ning(k)) matxsr matxsr.422 : !c matxsr matxsr.423 : !cc l1=ning(k)-jconst+1 matxsr matxsr.424 : !c matxsr matxsr.425 : !cw noutg(k)+jconst matxsr matxsr.426 : !c matxsr matxsr.427 : !cb format(4h10d ,8x,1p,5e12.5/(6e12.5)) matxsr matxsr.428 : !c matxsr matxsr.429 : !cd spec normalized spectrum of final particles for initial matxsr matxsr.430 : !cd particles in groups l1 to ning(k) matxsr matxsr.431 : !cd prod production cross section (e.g., nu*sigf) for matxsr matxsr.432 : !cd initial groups l1 through ning(k) matxsr matxsr.433 : !cd matxsr matxsr.434 : !cd this option is normally used for the energy-independent matxsr matxsr.435 : !cd neutron and photon spectra from fission and radiative matxsr matxsr.436 : !cd capture usually seen at low energies. matxsr matxsr.437 : !c matxsr matxsr.438 : !c---------------------------------------------------------------------- matxsr matxsr.439 : !c matxsr matxsr.440 : matxsr matxsr.441 : !------------------------------------------------------------------- matxsr RESXSR resxsr.11 : subroutine resxsr resxsr resxsr.12 : !------------------------------------------------------------------- resxsr resxsr.13 : ! resxsr resxsr.14 : ! Construct a RESXS resonance cross section resxsr resxsr.15 : ! file from NJOY pendf cross sections. resxsr resxsr.16 : ! resxsr resxsr.17 : ! User input: resxsr resxsr.18 : ! resxsr resxsr.19 : ! card 1 units resxsr resxsr.20 : ! nout output unit resxsr resxsr.21 : ! resxsr resxsr.22 : ! card 2 control resxsr resxsr.23 : ! nmat number of materials resxsr resxsr.24 : ! maxt max. number of temperatures resxsr resxsr.25 : ! nholl number of lines of descriptive comments resxsr resxsr.26 : ! efirst lower energy limit (ev) resxsr resxsr.27 : ! elast upper energy limit resxsr resxsr.28 : ! eps thinning tolerance resxsr resxsr.29 : ! resxsr resxsr.30 : ! card 3 user id resxsr resxsr.31 : ! huse hollerith user identification (up to 16 chars) resxsr resxsr.32 : ! ivers file version number resxsr resxsr.33 : ! resxsr resxsr.34 : ! card 4 descriptive data (repeat nholl times) resxsr resxsr.35 : ! holl line of hollerith data (72 chars max) resxsr resxsr.36 : ! resxsr resxsr.37 : ! card 5 material specifications (repeat nmat times) resxsr resxsr.38 : ! hmat hollerith name for material (up to 8 chars) resxsr resxsr.39 : ! mat endf mat number for material resxsr resxsr.40 : ! unit njoy unit number for pendf data resxsr resxsr.41 : ! resxsr resxsr.42 : ! The RESXS format specification follows: resxsr resxsr.43 : ! resxsr resxsr.44 : !*********************************************************************** resxsr resxsr.45 : ! proposed 09/24/90 - resxsr resxsr.46 : ! - resxsr resxsr.47 : !f resxs - resxsr resxsr.48 : !e resonance cross section file - resxsr resxsr.49 : ! - resxsr resxsr.50 : !n this file contains pointwise cross - resxsr resxsr.51 : !n sections for the epithermal resonance - resxsr resxsr.52 : !n range to be used for hyper-fine flux - resxsr resxsr.53 : !n calculations. elastic, fission, and - resxsr resxsr.54 : !n capture cross sections are given vs - resxsr resxsr.55 : !n temperature. linear interpolation is - resxsr resxsr.56 : !n assumed. - resxsr resxsr.57 : ! - resxsr resxsr.58 : !n formats given are for file exchange only - resxsr resxsr.59 : ! - resxsr resxsr.60 : !*********************************************************************** resxsr resxsr.61 : ! resxsr resxsr.62 : ! resxsr resxsr.63 : !----------------------------------------------------------------------- resxsr resxsr.64 : !s file structure - resxsr resxsr.65 : !s - resxsr resxsr.66 : !s record type present if - resxsr resxsr.67 : !s ============================== =============== - resxsr resxsr.68 : !s file identification always - resxsr resxsr.69 : !s file control always - resxsr resxsr.70 : !s set hollerith identification always - resxsr resxsr.71 : !s file data always - resxsr resxsr.72 : !s - resxsr resxsr.73 : !s *************(repeat for all materials) - resxsr resxsr.74 : !s * material control always - resxsr resxsr.75 : !s * - resxsr resxsr.76 : !s * ***********(repeat for all cross section blocks) - resxsr resxsr.77 : !s * * cross section block always - resxsr resxsr.78 : !s * *********** - resxsr resxsr.79 : !s ************* - resxsr resxsr.80 : ! - resxsr resxsr.81 : !----------------------------------------------------------------------- resxsr resxsr.82 : ! resxsr resxsr.83 : ! resxsr resxsr.84 : !----------------------------------------------------------------------- resxsr resxsr.85 : !r file identification - resxsr resxsr.86 : ! - resxsr resxsr.87 : !l hname,(huse(i),i=1,2),ivers - resxsr resxsr.88 : ! - resxsr resxsr.89 : !w 1+3*mult - resxsr resxsr.90 : ! - resxsr resxsr.91 : !b format(4h ov ,a8,1h*,2a8,1h*,i6) - resxsr resxsr.92 : ! - resxsr resxsr.93 : !d hname hollerith file name - resxs - (a8) - resxsr resxsr.94 : !d huse hollerith user identifiation (a8) - resxsr resxsr.95 : !d ivers file version number - resxsr resxsr.96 : !d mult double precision parameter - resxsr resxsr.97 : !d 1- a8 word is single word - resxsr resxsr.98 : !d 2- a8 word is double precision word - resxsr resxsr.99 : ! - resxsr resxsr.100 : !----------------------------------------------------------------------- resxsr resxsr.101 : ! resxsr resxsr.102 : ! resxsr resxsr.103 : !----------------------------------------------------------------------- resxsr resxsr.104 : !r file control - resxsr resxsr.105 : ! - resxsr resxsr.106 : !l efirst,elast,nholl,nmat,nblok resxsr resxsr.107 : ! - resxsr resxsr.108 : !w 5 - resxsr resxsr.109 : ! - resxsr resxsr.110 : !b format(4h 1d ,2i6) - resxsr resxsr.111 : ! - resxsr resxsr.112 : !d efirst lowest energy on file (ev) - resxsr resxsr.113 : !d elast highest enery on file (ev) - resxsr resxsr.114 : !d nholl number of words in set hollerith - resxsr resxsr.115 : !d identification record - resxsr resxsr.116 : !d nmat number of materials on file - resxsr resxsr.117 : !d nblok energy blocking factor - resxsr resxsr.118 : ! - resxsr resxsr.119 : !----------------------------------------------------------------------- resxsr resxsr.120 : ! resxsr resxsr.121 : ! resxsr resxsr.122 : !----------------------------------------------------------------------- resxsr resxsr.123 : !r set hollerith identification - resxsr resxsr.124 : ! - resxsr resxsr.125 : !l (hsetid(i),i=1,nholl) - resxsr resxsr.126 : ! - resxsr resxsr.127 : !w nholl*mult - resxsr resxsr.128 : ! - resxsr resxsr.129 : !b format(4h 2d ,8a8/(9a8)) - resxsr resxsr.130 : ! - resxsr resxsr.131 : !d hsetid hollerith identification of set (a8) - resxsr resxsr.132 : !d (to be edited out 72 characters per line) - resxsr resxsr.133 : ! - resxsr resxsr.134 : !----------------------------------------------------------------------- resxsr resxsr.135 : ! resxsr resxsr.136 : ! resxsr resxsr.137 : !----------------------------------------------------------------------- resxsr resxsr.138 : !r file data - resxsr resxsr.139 : ! - resxsr resxsr.140 : !l (hmatn(i),i=1,nmat),(ntemp(i),i=1,nmat),(locm(i),i=1,nmat) - resxsr resxsr.141 : ! - resxsr resxsr.142 : !w (mult+2)*nmat - resxsr resxsr.143 : ! - resxsr resxsr.144 : !b format(4h 3d ,8a8/(9a8)) hmatn - resxsr resxsr.145 : !b format(12i6) ntemp,locm - resxsr resxsr.146 : ! - resxsr resxsr.147 : !d hmatn(i) hollerith identification for material i - resxsr resxsr.148 : !d ntemp(i) number of temperatures for material i - resxsr resxsr.149 : !d locm(i) location of material i - resxsr resxsr.150 : ! - resxsr resxsr.151 : !----------------------------------------------------------------------- resxsr resxsr.152 : ! resxsr resxsr.153 : ! resxsr resxsr.154 : !----------------------------------------------------------------------- resxsr resxsr.155 : !r material control - resxsr resxsr.156 : ! - resxsr resxsr.157 : !l hmat,amass,(temp(i),i=1,ntemp),nreac,nener - resxsr resxsr.158 : ! - resxsr resxsr.159 : !w mult+3+ntemp - resxsr resxsr.160 : ! - resxsr resxsr.161 : !b format(4h 6d ,a8,1h*,1p1e12.5/(6e12.5)) hmat,temp - resxsr resxsr.162 : !b format(2i6) nener,blok - resxsr resxsr.163 : ! - resxsr resxsr.164 : !d hmat hollerith material identifier - resxsr resxsr.165 : !d amass atomic weight ratio - resxsr resxsr.166 : !d temp temperature values for this material - resxsr resxsr.167 : !d nreac number of reactions for this material - resxsr resxsr.168 : !d (3 for fissionable, 2 for nonfissionable) - resxsr resxsr.169 : !d nener number of energies for this material - resxsr resxsr.170 : ! - resxsr resxsr.171 : !----------------------------------------------------------------------- resxsr resxsr.172 : ! resxsr resxsr.173 : ! resxsr resxsr.174 : !----------------------------------------------------------------------- resxsr resxsr.175 : !r cross section block - resxsr resxsr.176 : ! - resxsr resxsr.177 : !l (xsb(i),i=1,imax) - resxsr resxsr.178 : ! - resxsr resxsr.179 : !c imax=3*ntemp*(number of energies in the block) - resxsr resxsr.180 : ! - resxsr resxsr.181 : !w imax - resxsr resxsr.182 : ! - resxsr resxsr.183 : !b format(4h 8d ,1p5e12.5/(6e12.5)) - resxsr resxsr.184 : ! - resxsr resxsr.185 : !d xsb(i) data for a block of nblok or fewer point energy - resxsr resxsr.186 : !d values. the data values given for each energy - resxsr resxsr.187 : !d are nelas, nfis, and ng at temp(1), followed by - resxsr resxsr.188 : !d nelas, nfis, and ng at temp(2), and so on. - resxsr resxsr.189 : ! - resxsr resxsr.190 : !----------------------------------------------------------------------- resxsr ACER acer.9 : subroutine acer acer acer.10 : !-------------------------------------------------------------------- acer acer.11 : ! acer acer.12 : ! Prepare a data library for MCNP, acer acer.13 : ! the Los Alamos continuous energy Monte Carlo code. acer acer.14 : ! acer acer.15 : ! --- continuous (fast) data --- acer acer.16 : ! acer acer.17 : ! Reaction cross sections are reconstructed on the grid of the acer acer.18 : ! total cross section from the input pendf tape (assumed to be acer acer.19 : ! linearized and unionized). Redundant reactions (except for acer acer.20 : ! MT1, MT452, and reactions needed for photon yields) are acer acer.21 : ! removed. MT18 is considered redundant if MT19 is present. acer acer.22 : ! Angular distributions are converted into either 32 equally acer acer.23 : ! probable bins, or into cummulative probability distributions. acer acer.24 : ! Tabulated energy distributions are converted into "law 4" acer acer.25 : ! probability distributions. Analytic secondary-energy acer acer.26 : ! distributions are converted into their ACE formats. acer acer.27 : ! Coupled energy-angle distributions (File 6) are converted acer acer.28 : ! into ACE laws. The old format supports law44 for tabulated acer acer.29 : ! data with Kalbach systematics, law67 for angle-energy data, acer acer.30 : ! and law66 for phase space. The newer format adds law61 with acer acer.31 : ! with cummulative angle distributions for Legendre or tabulated acer acer.32 : ! distributions (see newfor). All photon production cross acer acer.33 : ! sections are combined on the cross section energy grid. acer acer.34 : ! If provided, multigroup photon production data is summed acer acer.35 : ! and converted into a set of equally probable emission acer acer.36 : ! energies for each input group. Detailed photon production acer acer.37 : ! data can be generated directly from Files 12, 13, 14, 15, acer acer.38 : ! and 16 from the input ENDF tapes and written out using the acer acer.39 : ! "law 4" cummulative energy distribution format. acer acer.40 : ! acer acer.41 : ! --- thermal data --- acer acer.42 : ! acer acer.43 : ! The data from the pendf tape as prepared by the thermr acer acer.44 : ! module is read in. Inelastic and incoherent elastic cross acer acer.45 : ! sections are stored directly. Coherent elastic cross acer acer.46 : ! sections are converted to a cummulative "stair step" form acer acer.47 : ! and stored. The angular representation for incoherent acer acer.48 : ! elastic is stored directly. None is needed for coherent acer acer.49 : ! elastic. The incoherent inelastic energy distributions acer acer.50 : ! are converted into probability bins with the equally acer acer.51 : ! probable angles left unchanged. The bins can have equal acer acer.52 : ! probabilities or variable probabilities. In the latter acer acer.53 : ! case, outlying bins with smaller probabilities are provided acer acer.54 : ! to extend the sampling to rare events. A new tabulated option acer acer.55 : ! uses a continuous tabulated probability distribution (pdf/cdf) acer acer.56 : ! (requires a MCNP5.1.50 or later) and provides extended acer acer.57 : ! plotting. acer acer.58 : ! acer acer.59 : ! --- dosimetry data --- acer acer.60 : ! acer acer.61 : ! ENDF cross sections for dosimetry reactions are simply acer acer.62 : ! stored in ACE format without changing the energy grid. acer acer.63 : ! The endf interpolation law is also provided. acer acer.64 : ! acer acer.65 : ! --- photoatomic data --- acer acer.66 : ! acer acer.67 : ! Photon interaction cross sections are stored on the grid of acer acer.68 : ! the total cross section. The coherent form factor is acer acer.69 : ! stored together with an integral over the form factor that acer acer.70 : ! is used in sampling for coherent scattering. The acer acer.71 : ! incoherent scattering function is simply stored. Photon acer acer.72 : ! heating is calculated from the incoherent scattering data, acer acer.73 : ! the pair production data, and the photoelectric absorption acer acer.74 : ! data. The input photoatomic data file is mounted on nendf. acer acer.75 : ! Fluorescence data can be generated from an atomic relaxation acer acer.76 : ! data file in ENDF format mounted on npend. acer acer.77 : ! acer acer.78 : ! --- photonuclear data --- acer acer.79 : ! acer acer.80 : ! Photonuclear data are processed from new evaluations now acer acer.81 : ! available in ENDF format using a new ACE format developed acer acer.82 : ! for MCNP and MCNPX. acer acer.83 : ! acer acer.84 : ! --- particle production --- acer acer.85 : ! acer acer.86 : ! With the new format (see newfor), for charged particles, and acer acer.87 : ! for photonuclear data, new sections are written describing the acer acer.88 : ! distributions of light particles produced that are different acer acer.89 : ! from the incident particle. acer acer.90 : ! acer acer.91 : ! --- incident charged particles --- acer acer.92 : ! acer acer.93 : ! Incident charged particles are automatically recognized from acer acer.94 : ! the input tape. acer acer.95 : ! acer acer.96 : ! --- mcnpx format --- acer acer.97 : ! acer acer.98 : ! MCNPX format is given to support a proposed extension of acer acer.99 : ! the zaid indentifier that uses three digits and two letters acer acer.100 : ! to the right of the decimal. This will increase flexibility acer acer.101 : ! for handling exotic particles and provide more space for acer acer.102 : ! different data versions. To request MCNPX format, set the acer acer.103 : ! value of iopt negative. acer acer.104 : ! acer acer.105 : ! --- output --- acer acer.106 : ! acer acer.107 : ! The ACE output file can be Type 1 (formatted) or Type 2 acer acer.108 : ! (f77 binary). Type 3 is no longer used. A line of file acer acer.109 : ! directory information is also written. It must normally acer acer.110 : ! be edited to tell the system the path to the file. ACER acer acer.111 : ! can also be used to print, edit, or convert the mode of acer acer.112 : ! existing ACE-format files. acer acer.113 : ! acer acer.114 : !---input specifications (free format)--------------------------- acer acer.115 : ! acer acer.116 : ! card 1 acer acer.117 : ! nendf unit for input endf tape acer acer.118 : ! npend unit for input pendf tape acer acer.119 : ! ngend unit for input multigroup photon data acer acer.120 : ! nace unit for output ace tape acer acer.121 : ! ndir unit for output mcnp directory acer acer.122 : ! card 2 acer acer.123 : ! iopt type of acer run option acer acer.124 : ! 1 fast data acer acer.125 : ! 2 thermal data acer acer.126 : ! 3 dosimetry data acer acer.127 : ! 4 photo-atomic data acer acer.128 : ! 5 photo-nuclear data acer acer.129 : ! 7 read type 1 ace files to print or edit acer acer.130 : ! 8 read type 2 ace files to print or edit acer acer.131 : ! set iopt negative for mcnpx format acer acer.132 : ! iprint print control (0 min, 1 max, default=1) acer acer.133 : ! itype ace output type (1, 2, or 3, default=1) acer acer.134 : ! suff id suffix for zaid (default=.00) acer acer.135 : ! nxtra number of iz,aw pairs to read in (default=0) acer acer.136 : ! card 3 acer acer.137 : ! hk descriptive character string (70 char max) acer acer.138 : ! delimited by quotes acer acer.139 : ! card 4 (nxtra.gt.0 only) acer acer.140 : ! iz,aw nxtra pairs of iz and aw acer acer.141 : ! acer acer.142 : ! --- fast data (iopt=1 only) --- acer acer.143 : ! acer acer.144 : ! card 5 acer acer.145 : ! matd material to be processed acer acer.146 : ! tempd temperature desired (kelvin) (default=300) acer acer.147 : ! card 6 acer acer.148 : ! newfor use new cummulative angle distributions, acer acer.149 : ! law 61, and outgoing particle distributions. acer acer.150 : ! (0=no, 1=yes, default=1) acer acer.151 : ! iopp detailed photons (0=no, 1=yes, default=1) acer acer.152 : ! card 7 acer acer.153 : ! type of thinning is determined by sign of thin(1) acer acer.154 : ! (pos. or zero/neg.=energy skip/integral fraction) acer acer.155 : ! (all entries defaulted=no thinning) acer acer.156 : ! thin(1) e1 energy below which to use all energies (ev) acer acer.157 : ! or iwtt weighting option (1=flat,2=1/e) acer acer.158 : ! (1/e actually has weight=10 when e lt .1) acer acer.159 : ! thin(2) e2 energy above which to use all energies acer acer.160 : ! or target number of points acer acer.161 : ! thin(3) iskf skip factor--use every iskf-th energy acer acer.162 : ! between e1 and e2, or rsigz reference sigma zero acer acer.163 : ! acer acer.164 : ! --- thermal data (iopt=2 only) --- acer acer.165 : ! acer acer.166 : ! card 8 acer acer.167 : ! matd material to be processed acer acer.168 : ! tempd temperature desired (kelvin) (default=300) acer acer.169 : ! tname thermal zaid name ( 6 char max, def=za) acer acer.170 : ! card 8a acer acer.171 : ! iza01 moderator component za value acer acer.172 : ! iza02 moderator component za value (def=0) acer acer.173 : ! iza03 moderator component za value (def=0) acer acer.174 : ! card 9 acer acer.175 : ! mti mt for thermal incoherent data acer acer.176 : ! nbint number of bins for incoherent scattering acer acer.177 : ! mte mt for thermal elastic data acer acer.178 : ! ielas 0/1=coherent/incoherent elastic acer acer.179 : ! nmix number of atom types in mixed moderator acer acer.180 : ! (default=1, not mixed) acer acer.181 : ! (example, 2 for beo or c6h6) acer acer.182 : ! emax maximum energy for thermal treatment (ev) acer acer.183 : ! (default=1000.=determined from mf3, mti) acer acer.184 : ! iwt weighting option acer acer.185 : ! 0/1/2=variable/constant/tabulated (default=variable) acer acer.186 : ! acer acer.187 : ! --- dosimetry data (iopt=3 only) --- acer acer.188 : ! acer acer.189 : ! card 10 acer acer.190 : ! matd material to be processed acer acer.191 : ! tempd temperature desired (kelvin) (default=300) acer acer.192 : ! acer acer.193 : ! --- photo-atomic data (iopt=4 only) --- acer acer.194 : ! acer acer.195 : ! card 11 acer acer.196 : ! matd material to be processed acer acer.197 : ! photoatomic data on nendf acer acer.198 : ! atomic relaxation data on npend acer acer.199 : ! acer acer.200 : ! --- photo-nuclear data (iopt=5 only) --- acer acer.201 : ! acer acer.202 : ! card 11 acer acer.203 : ! matd material to be processed acer acer.204 : ! acer acer.205 : ! --- print or edit existing files (iopt=7-9) --- acer acer.206 : ! acer acer.207 : ! No additional input cards are required. Mount the old acer acer.208 : ! ace tape on "npend". The code can modify zaid, hk, acer acer.209 : ! the (iz,aw) list, and the type of the file. Use suff<0 acer acer.210 : ! to leave the old zaid unchanged. Use just "/" on acer acer.211 : ! card 3 to leave the comment field hk unchanged. Use acer acer.212 : ! nxtra=0 to leave the old iz,aw list unchanged. The acer acer.213 : ! code can modify zaid, hk, and type of file. acer acer.214 : ! acer acer.215 : ! Exhaustive consistency checks are automatically made on acer acer.216 : ! the input file. If ngend.ne.0, a set of standard ACE plots acer acer.217 : ! are prepared on unit ngend as plotr input instructions. acer acer.218 : ! acer acer.219 : !-------------------------------------------------------------------- acer POWR powr.64 : subroutine powr powr powr.65 : !-------------------------------------------------------------------- powr powr.66 : ! powr powr.67 : ! Produce input for the EPRI-CELL codes GAMTAP (fast) and powr powr.68 : ! LIBRAR (thermal), and the EPRI-CPM code CLIB. powr powr.69 : ! powr powr.70 : !---input specifications (free format)--------------------------- powr powr.71 : ! powr powr.72 : ! card 1 powr powr.73 : ! ngendf unit for input gout tape powr powr.74 : ! nout unit for output tape powr powr.75 : ! card 2 powr powr.76 : ! lib library option (1=fast, 2=thermal, 3=cpm) powr powr.77 : ! iprint print option (0=minimum, 1=maximum) powr powr.78 : ! (default=0) powr powr.79 : ! iclaps group collapsing option (0=collapse from 185 group powr powr.80 : ! to desired group structure, 1=no collapse) powr powr.81 : ! (default=0) powr powr.82 : ! powr powr.83 : !---for lib=1---------------------------------------------------- powr powr.84 : ! powr powr.85 : ! card 3 powr powr.86 : ! matd material to be processed powr powr.87 : ! if matd lt 0, read-in absorption data only for powr powr.88 : ! this material with mat=abs(matd) directly from powr powr.89 : ! input deck (see card 6) powr powr.90 : ! following three parameters irrelevant for matd lt 0 powr powr.91 : ! rtemp reference temperature (degrees kelvin) powr powr.92 : ! (default=300 k) powr powr.93 : ! iff f-factor option powr powr.94 : ! (0/1=do not calculate f-factors/calculate if found) powr powr.95 : ! (default=1) powr powr.96 : ! nsgz no. of sigma zeroes to process for this material powr powr.97 : ! (default=0=all found on input tape) powr powr.98 : ! izref ref. sigzero for elastic matrix (default=1) powr powr.99 : ! cards 4 and 5 for normal run only (matd gt 0) powr powr.100 : ! card 4 powr powr.101 : ! word description of nuclide (up to 16 characters, powr powr.102 : ! delimited with *, ended with /) (default=blank) powr powr.103 : ! card 5 powr powr.104 : ! fsn title of fission spectrum (up to 40 characters, powr powr.105 : ! delimited with *, ended with /0 (default=blank) powr powr.106 : ! delimited with *, ended with /) (default=blank) powr powr.107 : ! card 6 for reading in absorption data only powr powr.108 : ! abs ngnd absorption values (default values=0) powr powr.109 : ! repeat cards 3 through 6 for each material desired. powr powr.110 : ! terminate with matd=0/ (i.e., a 0/ card). powr powr.111 : ! powr powr.112 : !---for lib=2---------------------------------------------------- powr powr.113 : ! powr powr.114 : ! card 3 powr powr.115 : ! matd material to be processed powr powr.116 : ! idtemp temperature id (default=300 k) powr powr.117 : ! name hollerith name of isotope (up to 10 characters, powr powr.118 : ! delimited with *, ended with /) (default=blank) powr powr.119 : ! card 4 default for all values=0. powr powr.120 : ! itrc transport correction option (0 no, 1 yes) powr powr.121 : ! mti thermal inelastic mt powr powr.122 : ! mtc thermal elastic mt powr powr.123 : ! card 5 default for all values=0. powr powr.124 : ! xi powr powr.125 : ! alpha powr powr.126 : ! mubar powr powr.127 : ! nu powr powr.128 : ! kappa fission powr powr.129 : ! kappa capture powr powr.130 : ! lambda powr powr.131 : ! sigma s if 0, set to scattering cross section at group 35 powr powr.132 : ! repeat cards 3 thru 5 for each material and temperature desired powr powr.133 : ! (maximum number of temperatures allowed is 7.) powr powr.134 : ! terminate with matd=0/ (i.e., a 0/ card). powr powr.135 : ! powr powr.136 : !---for lib=3---------------------------------------------------- powr powr.137 : ! powr powr.138 : ! card 3 powr powr.139 : ! nlib number of library. powr powr.140 : ! idat date library is written (i format). powr powr.141 : ! newmat number of materials to be added. powr powr.142 : ! iopt add option (0=mats will be read in, powr powr.143 : ! 1=use all mats found on ngendf). powr powr.144 : ! mode 0/1/2=replace isotope(2) in cpmlib/ powr powr.145 : ! add/create a new library (default=0) powr powr.146 : ! if5 file5 (burnup data) option powr powr.147 : ! 0/1/2=do not process file5 burnup data/ powr powr.148 : ! process burnup data along with rest of data/ powr powr.149 : ! process burnup data only (default=0) powr powr.150 : ! (default=0) powr powr.151 : ! if4 file4 (cross section data) option powr powr.152 : ! 0/1=do not process/process powr powr.153 : ! (default=1) powr powr.154 : ! card 4 for iopt=0 only powr powr.155 : ! mat endf mat number of all desired materials. powr powr.156 : ! for materials not on gendf tape, use ident for mat. powr powr.157 : ! if mat lt 0, add 100 to output ident powr powr.158 : ! (for second isomer of an isotope) powr powr.159 : ! card 5 powr powr.160 : ! nina nina indicator. powr powr.161 : ! 0/1/2/3=normal/ powr powr.162 : ! no file2 data, calculate absorption in file4/ powr powr.163 : ! no file2 data, read in absorption in file4/ powr powr.164 : ! read in all file2 and file4 data. powr powr.165 : ! ntemp no. of temperatures to process for this material powr powr.166 : ! (default=0=all found on input tape) powr powr.167 : ! nsigz no. of sigma zeroes to process for this material powr powr.168 : ! (default=0=all found on input tape) powr powr.169 : ! sgref reference sigma zero powr powr.170 : ! following 2 parameters are for nina=0 or nina=3. powr powr.171 : ! ires resonance absorber indicator (0/1=no/yes) powr powr.172 : ! sigp potential cross section from endf. powr powr.173 : ! following 5 parameters are for ntapea=0 only powr powr.174 : ! mti thermal inelastic mt powr powr.175 : ! mtc thermal elastic mt powr powr.176 : ! ip1opt 0/1=calculate p1 matrices/ powr powr.177 : ! correct p0 scattering matrix ingroups. powr powr.178 : ! ******if a p1 matrix is calculated for one of the isotopes powr powr.179 : ! having a p1 matrix on the old library, file 6 on the powr powr.180 : ! new library will be completely replaced.****** powr powr.181 : ! inorf 0/1=include resonance fission if found/ powr powr.182 : ! do not include powr powr.183 : ! following two parameters for mode=0 only powr powr.184 : ! pos position of this isotope in cpmlib powr powr.185 : ! posr (for ires=1) position of this isotope in resonance powr powr.186 : ! tabulation in cpmlib powr powr.187 : ! repeat card 5 for each nuclide. powr powr.188 : ! following three cards are for if5 gt 0 only powr powr.189 : ! card 6 powr powr.190 : ! ntis no. time-dependent isotopes powr powr.191 : ! nfis no. fissionable burnup isotopes powr powr.192 : ! card 7 powr powr.193 : ! identb ident of each of the nfis isotopes powr powr.194 : ! card 8 powr powr.195 : ! identa ident of time-dependent isotope powr powr.196 : ! decay decay constant (default=0.) powr powr.197 : ! yield nfis yields (default=0.) powr powr.198 : ! repeat card 8 for each of the ntis isotopes. powr powr.199 : ! card 9 for if5=2 only powr powr.200 : ! aw atomic weight powr powr.201 : ! indfis fission indicator powr powr.202 : ! ntemp no. temperatures on old library powr powr.203 : ! repeat card 9 for each of the ntis isotopes. powr powr.204 : ! card 10 powr powr.205 : ! lambda resonance group goldstein lambdas powr powr.206 : ! ******remember that the 69-group structure has 13 resonance powr powr.207 : ! groups while the collapsed 185-group structure has 15. powr powr.208 : ! use a slash at end of each line of card 10 input.****** powr powr.209 : ! repeat card 10 for each nuclide having nina=0, nina=3, or powr powr.210 : ! ires=1. powr powr.211 : ! cards 11 and 11a for nuclides having nina=3 only. powr powr.212 : ! card 11 powr powr.213 : ! resnu nrg nus values to go with the lambda values powr powr.214 : ! card 11a powr powr.215 : ! tot nrg total xsec values to go with the lambda values powr powr.216 : ! read cards 11 and 11a for each nuclide having nina=3. powr powr.217 : ! cards 12 for nina gt 2 only powr powr.218 : ! aw atomic weight powr powr.219 : ! temp temperature powr powr.220 : ! fpa ngnd absorption values (default=0.) powr powr.221 : ! cards 12a, 12b, 12c for nuclides having nina=3 only. powr powr.222 : ! card 12a powr powr.223 : ! nus ngnd nus values powr powr.224 : ! fis ngnd fission values powr powr.225 : ! xtr ngnd transport values powr powr.226 : ! card 12b powr powr.227 : ! ia group. 0 means no scattering from this group powr powr.228 : ! l1 lowest group to which scattering occurs powr powr.229 : ! l2 highest group to which scattering occurs powr powr.230 : ! card 12c for ia gt 0 only powr powr.231 : ! scat l2-l1+1 scattering values powr powr.232 : ! repeat card 12b and 12c for each group powr powr.233 : ! repeat cards 12 for each of the nina gt 2 nuclides powr powr.234 : ! powr powr.235 : !-------------------------------------------------------------------- powr WIMSR wimsr.49 : subroutine wimsr wimsr wimsr.50 : !-------------------------------------------------------------------- wimsr wimsr.51 : ! wimsr wimsr.52 : ! Format multigroup cross sections from groupr for WIMS. wimsr wimsr.53 : ! wimsr wimsr.54 : !---input specifications (free format)---- wimsr wimsr.55 : ! wimsr wimsr.56 : ! card 1 wimsr wimsr.57 : ! ngendf unit for input gendf tape wimsr wimsr.58 : ! nout unit for output wims tape wimsr wimsr.59 : ! wimsr wimsr.60 : ! card 2 wimsr wimsr.61 : ! iprint print option wimsr wimsr.62 : ! 0=minimum (default) wimsr wimsr.63 : ! 1=regular wimsr wimsr.64 : ! 2=1+intermediate results wimsr wimsr.65 : ! iverw wims version wimsr wimsr.66 : ! 4=wims-d (default) wimsr wimsr.67 : ! 5=wims-e wimsr wimsr.68 : ! igroup group option wimsr wimsr.69 : ! 0=69 groups (default) wimsr wimsr.70 : ! 9=user's choice wimsr wimsr.71 : ! wimsr wimsr.72 : ! card 2a (igroup.eq.9 only) wimsr wimsr.73 : ! ngnd number of groups wimsr wimsr.74 : ! nfg number of fast groups wimsr wimsr.75 : ! nrg number of resonance groups wimsr wimsr.76 : ! igref reference group (default is last fast group) wimsr wimsr.77 : ! wimsr wimsr.78 : ! card 3 wimsr wimsr.79 : ! mat endf mat number of the material to be processed wimsr wimsr.80 : ! nfid not used wimsr wimsr.81 : ! rdfid identification of material for the wims library wimsr wimsr.82 : ! iburn burnup data option wimsr wimsr.83 : ! -1=suppress printout of burnup data wimsr wimsr.84 : ! 0=no burnup data is provided (default) wimsr wimsr.85 : ! 1=burnup data is provided in cards 5 and 6 wimsr wimsr.86 : ! wimsr wimsr.87 : ! card 4 wimsr wimsr.88 : ! ntemp no. of temperatures to process for this material wimsr wimsr.89 : ! in the thermal energy range wimsr wimsr.90 : ! (0=all found on input tape) wimsr wimsr.91 : ! nsigz no. of sigma zeroes to process for this material wimsr wimsr.92 : ! (0=all found on input tape) wimsr wimsr.93 : ! sgref reference sigma zero wimsr wimsr.94 : ! (.ge. 1.e10 to select all cross sect. at inf.dil.* wimsr wimsr.95 : ! but fully shielded elastic x-sect, wimsr wimsr.96 : ! .lt. 1.e10 to select all x-sect at inf.dil. wimsr wimsr.97 : ! =sig0 from the list on groupr input to wimsr wimsr.98 : ! select all x-sect. at that sig0) wimsr wimsr.99 : ! ires resonance absorber indicator wimsr wimsr.100 : ! 0=no resonance tables wimsr wimsr.101 : ! >0=ires temperatures processed wimsr wimsr.102 : ! sigp potential cross section from endf. wimsr wimsr.103 : ! (if zero, replace by the elastic cross section) wimsr wimsr.104 : ! mti thermal inelastic mt (default=0=none) wimsr wimsr.105 : ! mtc thermal elastic mt (default=0=none) wimsr wimsr.106 : ! ip1opt include p1 matrices wimsr wimsr.107 : ! 0=yes wimsr wimsr.108 : ! 1=no, correct p0 ingroups (default) wimsr wimsr.109 : ! inorf resonance fission (if found) wimsr wimsr.110 : ! 0=include resonance fission (default) wimsr wimsr.111 : ! 1=do not include wimsr wimsr.112 : ! isof fission spectrum wimsr wimsr.113 : ! 0=do not include fission spectrum (default) wimsr wimsr.114 : ! 1=include fission spectrum wimsr wimsr.115 : ! ifprod fission product flag wimsr wimsr.116 : ! 0=not a fission product (default) wimsr wimsr.117 : ! 1=fission product, no resonance tables wimsr wimsr.118 : ! 2=fission product, resonance tables wimsr wimsr.119 : ! jp1 transport correction neutron current spectrum flag wimsr wimsr.120 : ! 0=use p1-flux for transport correction (default) wimsr wimsr.121 : ! >0=read in jp1 values of the neutron current wimsr wimsr.122 : ! spectrum from input wimsr wimsr.123 : ! wimsr wimsr.124 : ! the following cards 5 and 6 are for iburn gt 0 only wimsr wimsr.125 : ! card 5 wimsr wimsr.126 : ! ntis no. of time-dependent isotopes wimsr wimsr.127 : ! for burnable materials ntis=2 wimsr wimsr.128 : ! for fissile materials ntis>2 when fission product wimsr wimsr.129 : ! yields are given. wimsr wimsr.130 : ! efiss energy released per fission wimsr wimsr.131 : ! wimsr wimsr.132 : ! card 6a wimsr wimsr.133 : ! identa ident of capture product isotope wimsr wimsr.134 : ! yield yield of product identa from capture wimsr wimsr.135 : ! wimsr wimsr.136 : ! card 6b wimsr wimsr.137 : ! identa ident of decay product isotope (zero if stable) wimsr wimsr.138 : ! lambda decay constant (s-1) wimsr wimsr.139 : ! wimsr wimsr.140 : ! card 6c (repeated ntis-2 times, if necessary) wimsr wimsr.141 : ! identa ident of fission product isotope wimsr wimsr.142 : ! yield fission yield of identa from burnup of mat wimsr wimsr.143 : ! wimsr wimsr.144 : ! card 7 wimsr wimsr.145 : ! lambda resonance-group goldstein lambdas (13 for wimsr wimsr.146 : ! default 69-group structure, nrg otherwise). wimsr wimsr.147 : ! wimsr wimsr.148 : ! card 8 (only when jp1>0) wimsr wimsr.149 : ! p1flx current spectrum (jp1 entries read, the rest are wimsr wimsr.150 : ! set with the default p1-flux calculated by njoy). wimsr wimsr.151 : !-------------------------------------------------------------------- wimsr PLOTR plotr.11 : subroutine plotr plotr plotr.12 : !-------------------------------------------------------------------- plotr plotr.13 : ! plotr plotr.14 : ! plot cross sections plotr plotr.15 : ! plotr plotr.16 : ! Handles ENDF data, PENDF or GENDF data at specified temper- plotr plotr.17 : ! atures, or experimental input data. Several plots can be plotr plotr.18 : ! given on each set of axes, with both left and right scales. plotr plotr.19 : ! Also, several graphs can be given on each page or display. plotr plotr.20 : ! Error bars may be included for input data. Flexible titles plotr plotr.21 : ! and legend blocks are allowed. All standard combinations of plotr plotr.22 : ! log and linear axes are supported, either grids or tick marks plotr plotr.23 : ! can be requested, and scales can be chosen automatically plotr plotr.24 : ! or set by the user. In some cases, the x axis is thinned. plotr plotr.25 : ! In other cases, extra points are added so that, for example, plotr plotr.26 : ! linear-linear data plots correctly on a log-log graph. plotr plotr.27 : ! A limited capability for 3-d plots of angle and energy plotr plotr.28 : ! is included, and the ENDF-6 File 6 format is supported. plotr plotr.29 : ! Percent difference and ratio plots can be requested. plotr plotr.30 : ! plotr plotr.31 : ! Plotr writes plot commands on an output file for later use plotr plotr.32 : ! by the viewr module or an external graphics program. plotr plotr.33 : ! plotr plotr.34 : !---input-------------------------------------------------------- plotr plotr.35 : ! plotr plotr.36 : ! card 0 plotr plotr.37 : ! nplt unit for output plot commands plotr plotr.38 : ! nplt0 unit for input plot commands plotr plotr.39 : ! default=0=none plotr plotr.40 : ! output plot commands are appended plotr plotr.41 : ! to the input plot commands, if any. plotr plotr.42 : ! card 1 plotr plotr.43 : ! lori page orientation (def=1) plotr plotr.44 : ! 0 portrait (7.5x10in) plotr plotr.45 : ! 1 landscape (10x7.5in) plotr plotr.46 : ! istyle character style (def=2) plotr plotr.47 : ! 1 = roman plotr plotr.48 : ! 2 = swiss plotr plotr.49 : ! size character size option plotr plotr.50 : ! pos = height in page units plotr plotr.51 : ! neg = height as fraction of subplot size plotr plotr.52 : ! (default=0.30) plotr plotr.53 : ! ipcol page color (def=white) plotr plotr.54 : ! 0=white plotr plotr.55 : ! 1=navajo white plotr plotr.56 : ! 2=blanched almond plotr plotr.57 : ! 3=antique white plotr plotr.58 : ! 4=very pale yellow plotr plotr.59 : ! 5=very pale rose plotr plotr.60 : ! 6=very pale green plotr plotr.61 : ! 7=very pale blue plotr plotr.62 : ! plotr plotr.63 : ! -----repeat cards 2 through 13 for each curve----- plotr plotr.64 : ! plotr plotr.65 : ! card 2 plotr plotr.66 : ! iplot plot index plotr plotr.67 : ! 99 = terminate plotting job plotr plotr.68 : ! 1 = new axes, new page plotr plotr.69 : ! -1 = new axes, existing page plotr plotr.70 : ! n = nth additional plot on existing axes plotr plotr.71 : ! -n = start a new set of curves using plotr plotr.72 : ! the alternate y axis plotr plotr.73 : ! default = 1 plotr plotr.74 : ! iwcol window color (def=white) plotr plotr.75 : ! color list same as for ipcol above plotr plotr.76 : ! factx factor for energies (default=1.) plotr plotr.77 : ! facty factor for cross-sections (default=1.) plotr plotr.78 : ! xll,yll lower-left corner of plot area plotr plotr.79 : ! ww,wh,wr window width, height, and rotation angle plotr plotr.80 : ! (plot area defaults to one plot per page) plotr plotr.81 : ! plotr plotr.82 : ! -----cards 3 thru 7 for iplot = 1 or -1 only----- plotr plotr.83 : ! plotr plotr.84 : ! card 3 plotr plotr.85 : ! t1 first line of title plotr plotr.86 : ! 60 characters allowed. plotr plotr.87 : ! default=none plotr plotr.88 : ! plotr plotr.89 : ! card 3a plotr plotr.90 : ! t2 second line of title plotr plotr.91 : ! 60 characters allowed. plotr plotr.92 : ! default=none plotr plotr.93 : ! plotr plotr.94 : ! card 4 plotr plotr.95 : ! itype type for primary axes plotr plotr.96 : ! 1 = linear x - linear y plotr plotr.97 : ! 2 = linear x - log y plotr plotr.98 : ! 3 = log x - linear y plotr plotr.99 : ! 4 = log x - log y plotr plotr.100 : ! set negative for 3d axes plotr plotr.101 : ! default=4 plotr plotr.102 : ! jtype type for alternate y axis or z axis plotr plotr.103 : ! 0 = none plotr plotr.104 : ! 1 = linear plotr plotr.105 : ! 2 = log plotr plotr.106 : ! default=0 plotr plotr.107 : ! igrid grid and tic mark control plotr plotr.108 : ! 0 = no grid lines or tic marks plotr plotr.109 : ! 1 = grid lines plotr plotr.110 : ! 2 = tic marks on outside plotr plotr.111 : ! 3 = tic marks on inside plotr plotr.112 : ! default=2 plotr plotr.113 : ! ileg option to write a legend. plotr plotr.114 : ! 0 = none plotr plotr.115 : ! 1 = write a legend block with upper left plotr plotr.116 : ! corner at xtag,ytag (see below) plotr plotr.117 : ! 2 = use tag labels on each curve with plotr plotr.118 : ! a vector from the tag to the curve plotr plotr.119 : ! default=0 plotr plotr.120 : ! xtag x coordinate of upper left corner plotr plotr.121 : ! of legend block plotr plotr.122 : ! ytag y coord of upper left corner plotr plotr.123 : ! default=upper left corner of plot plotr plotr.124 : ! plotr plotr.125 : ! card 5 plotr plotr.126 : ! el lowest energy to be plotted plotr plotr.127 : ! eh highest energy to be plotted plotr plotr.128 : ! xstep x axis step plotr plotr.129 : ! default = automatic scales plotr plotr.130 : ! (default all 3, or none) plotr plotr.131 : ! (the actual value of xstep is plotr plotr.132 : ! ignored for log scales) plotr plotr.133 : ! plotr plotr.134 : ! card 5a plotr plotr.135 : ! xlabl label for x axis plotr plotr.136 : ! 60 characters allowed. plotr plotr.137 : ! default="energy (ev)" plotr plotr.138 : ! plotr plotr.139 : ! card 6 plotr plotr.140 : ! yl lowest value of y axis. plotr plotr.141 : ! yh highest value of y axis. plotr plotr.142 : ! ystep step for y ayis (linear scales only) plotr plotr.143 : ! default = automatic scales plotr plotr.144 : ! (default all 3, or none) plotr plotr.145 : ! (the actual value of ystep is plotr plotr.146 : ! ignored for log scales) plotr plotr.147 : ! plotr plotr.148 : ! card 6a plotr plotr.149 : ! ylabl label for y axis plotr plotr.150 : ! 60 characters allowed. plotr plotr.151 : ! default="cross section (barns)" plotr plotr.152 : ! plotr plotr.153 : ! card 7 (jtype.gt.0 only) plotr plotr.154 : ! rbot lowest value of secondary y axis or z axis plotr plotr.155 : ! rtop highest value of secondary y axis or z axis plotr plotr.156 : ! rstep step for secondary y axis or z axis plotr plotr.157 : ! default for last three = automatic plotr plotr.158 : ! plotr plotr.159 : ! card 7a (jtype.gt.0 only) plotr plotr.160 : ! rl label for alternate y axis or z axis plotr plotr.161 : ! 60 characters allowed. plotr plotr.162 : ! default=blank plotr plotr.163 : ! plotr plotr.164 : ! -----cards 8 thru 9 are always given----- plotr plotr.165 : ! plotr plotr.166 : ! card 8 plotr plotr.167 : ! iverf version of endf tape plotr plotr.168 : ! set to zero for data on input file plotr plotr.169 : ! and ignore rest of parameters on card plotr plotr.170 : ! set to 1 for gendf data plotr plotr.171 : ! nin input tape plotr plotr.172 : ! can change for every curve if desired. plotr plotr.173 : ! matd desired material plotr plotr.174 : ! mfd desired file plotr plotr.175 : ! mtd desired section plotr plotr.176 : ! mtd=0 means loop over all reactions in mfd plotr plotr.177 : ! (usually one page per mt, but for mf=3, plotr plotr.178 : ! resonance reactions may have several pages) plotr plotr.179 : ! temper temperature for endf data (degK, default=0.) plotr plotr.180 : ! nth,ntp,nkh see below (defaults=1) plotr plotr.181 : ! plotr plotr.182 : ! special meanings for nth,ntp,nkh for file 3 or 5 data plotr plotr.183 : ! nth number of subsection to plot plotr plotr.184 : ! (works for isomer prod, delayed n, etc.) plotr plotr.185 : ! ntp special features plotr plotr.186 : ! 1 for regular plots (default) plotr plotr.187 : ! 2 for percent difference plots plotr plotr.188 : ! read a second "card 8" for percent diff plotr plotr.189 : ! of second curve with respect to first plotr plotr.190 : ! 3 for ratio plots plotr plotr.191 : ! read a second "card 8" for ratio plotr plotr.192 : ! of second curve to first plotr plotr.193 : ! nkh not used plotr plotr.194 : ! plotr plotr.195 : ! special meanings for nth for file 4 Legendre data plotr plotr.196 : ! nth index for Legendre coefficient (p1, p2, ...) plotr plotr.197 : ! plotr plotr.198 : ! special meanings for nth,ntp,nkh for file 6 data plotr plotr.199 : ! nth index for incident energy plotr plotr.200 : ! ntp number of dep. variable in cyle to plot plotr plotr.201 : ! (or angle number for law 7) plotr plotr.202 : ! nkh number of outgoing particle to plot plotr plotr.203 : ! plotr plotr.204 : ! special meanings for nth,ntp,nkh for gendf mf=3 data plotr plotr.205 : ! nth=0 for flux per unit lethargy plotr plotr.206 : ! nth=1 for cross section (default) plotr plotr.207 : ! ntp=1 for infinite dilution (default) plotr plotr.208 : ! ntp=2 for next lowest sigma-zero values, etc. plotr plotr.209 : ! set ntp negative for self-shielding factor plotr plotr.210 : ! ntp=21,22,... plotr plotr.211 : ! like 1,2,... except read another source plotr plotr.212 : ! and compute percent difference plotr plotr.213 : ! ntp=41,42,... plotr plotr.214 : ! like 1,2,... except read another source plotr plotr.215 : ! and compute ratio plotr plotr.216 : ! ntp=-21,-22,... plotr plotr.217 : ! like -1,-2,... except read another source plotr plotr.218 : ! and compute percent difference plotr plotr.219 : ! ntp=-41,-42,... plotr plotr.220 : ! like -1,-2,... except read another source plotr plotr.221 : ! and compute ratio plotr plotr.222 : ! nkh=1 for p0 weighting (default) plotr plotr.223 : ! nkh=2 for p1 weighting (total only) plotr plotr.224 : ! plotr plotr.225 : ! special meaning for nth for gendf mf=6 data plotr plotr.226 : ! nth=1 plot 2-d spectrum for group 1 plotr plotr.227 : ! nth=2 plot 2-d spectrum for group 2 plotr plotr.228 : ! etc. plotr plotr.229 : ! no special flags are needed for mf=6 3d plots plotr plotr.230 : ! plotr plotr.231 : ! special meanings for nth and ntp for mf7 plots plotr plotr.232 : ! nth is index for indep. variable (alpha or beta) plotr plotr.233 : ! ntp=1 selects alpha as indep. variable (default) plotr plotr.234 : ! ntp=2 selects beta as indep. variable plotr plotr.235 : ! nkh=1 selects normal s(alpha,beta) plotr plotr.236 : ! nkh=2 selects script s(alpha,-beta) plotr plotr.237 : ! nkh=3 selects script s(alpha,beta) plotr plotr.238 : ! plotr plotr.239 : ! additional guidance for ratio (ntp=3 on card 8) plotting of plotr plotr.240 : ! mf=3 endf or pendf data: plotr plotr.241 : ! - if both cross sections are zero, the ratio is defined to be plotr plotr.242 : ! unity. plotr plotr.243 : ! - if ntp=3 and mtd=0, then mtd2 is set to zero regardless of plotr plotr.244 : ! its value on card 8a. plotr plotr.245 : ! - if mtd=0 and y-axis limits (card 6) were specified, then plotr plotr.246 : ! those limits will apply to all plots. For selected mt's plotr plotr.247 : ! both linear-linear and log-linear plots will be produced. plotr plotr.248 : ! - if mtd=0 and y-axis limits (card 6) are not given, then plotr plotr.249 : ! y-axis limits are determined internally. For selected mt's plotr plotr.250 : ! both linear-linear and log-log plots will be produced. plotr plotr.251 : ! plotr plotr.252 : ! -----cards 9 and 10 for 2d plots only----- plotr plotr.253 : ! plotr plotr.254 : ! card 9 plotr plotr.255 : ! icon symbol and connection option plotr plotr.256 : ! 0 = points connected, no symbols plotr plotr.257 : ! -i = points not connected, symbol at every plotr plotr.258 : ! ith point plotr plotr.259 : ! i = points connected, symbol at every ith plotr plotr.260 : ! points plotr plotr.261 : ! default=0 plotr plotr.262 : ! isym no. of symbol to be used plotr plotr.263 : ! 0 = square plotr plotr.264 : ! 1 = octagon plotr plotr.265 : ! 2 = triangle plotr plotr.266 : ! 3 = cross plotr plotr.267 : ! 4 = ex plotr plotr.268 : ! 5 = diamond plotr plotr.269 : ! 6 = inverted triangle plotr plotr.270 : ! 7 = exed square plotr plotr.271 : ! 8 = crossed ex plotr plotr.272 : ! 9 = crossed diamond plotr plotr.273 : ! 10 = crossed octagon plotr plotr.274 : ! 11 = double triangle plotr plotr.275 : ! 12 = crossed square plotr plotr.276 : ! 13 = exed octagon plotr plotr.277 : ! 14 = triangle and square plotr plotr.278 : ! 15 = filled circle plotr plotr.279 : ! 16 = open circle plotr plotr.280 : ! 17 = open square plotr plotr.281 : ! 18 = filled square plotr plotr.282 : ! default=0 plotr plotr.283 : ! idash type of line to plot plotr plotr.284 : ! 0 = solid plotr plotr.285 : ! 1 = dashed plotr plotr.286 : ! 2 = chain dash plotr plotr.287 : ! 3 = chain dot plotr plotr.288 : ! 4 = dot plotr plotr.289 : ! default=0 plotr plotr.290 : ! iccol curve color (def=black) plotr plotr.291 : ! 0=black plotr plotr.292 : ! 1=red plotr plotr.293 : ! 2=green plotr plotr.294 : ! 3=blue plotr plotr.295 : ! 4=magenta plotr plotr.296 : ! 5=cyan plotr plotr.297 : ! 6=brown plotr plotr.298 : ! 7=purple plotr plotr.299 : ! ithick thickness of curve (def=1) plotr plotr.300 : ! 0 = invisible (for shaded areas) plotr plotr.301 : ! ishade shade pattern plotr plotr.302 : ! 0 = none plotr plotr.303 : ! 1 to 10 = 10% to 100% gray plotr plotr.304 : ! 11 to 20 = 45 deg right hatching plotr plotr.305 : ! 21 to 30 = 45 deg left hatching plotr plotr.306 : ! 31 to 40 = 45 deg cross hatching plotr plotr.307 : ! 41 to 50 = shades of green plotr plotr.308 : ! 51 to 60 = shades of red plotr plotr.309 : ! 61 to 70 = shades of brown plotr plotr.310 : ! 71 to 80 = shades of blue plotr plotr.311 : ! default=0 plotr plotr.312 : ! plotr plotr.313 : ! card 10 ---ileg.ne.0 only--- plotr plotr.314 : ! aleg title for curve tag or legend block plotr plotr.315 : ! 60 characters allowed. plotr plotr.316 : ! default=blank plotr plotr.317 : ! plotr plotr.318 : ! card 10a ---ileg.eq.2 only--- plotr plotr.319 : ! xtag x position of tag title plotr plotr.320 : ! ytag y position of tag title plotr plotr.321 : ! xpoint x coordinate of vector point plotr plotr.322 : ! (.le.0 to omit vector) plotr plotr.323 : ! plotr plotr.324 : ! -----card 11 for 3d plots only----- plotr plotr.325 : ! plotr plotr.326 : ! card 11 plotr plotr.327 : ! xv,yv,zv abs. coords of view point plotr plotr.328 : ! defaults=15.,-15.,15. plotr plotr.329 : ! x3,y3,z3 abs. sides of work box volume plotr plotr.330 : ! defaults=2.5,6.5,2.5 plotr plotr.331 : ! plotr plotr.332 : ! set x3 or y3 negative to flip the order of the plotr plotr.333 : ! axis on that side of the work box. plotr plotr.334 : ! plotr plotr.335 : ! -----cards 12 thru 13 for iverf = 0 only----- plotr plotr.336 : ! plotr plotr.337 : ! card 12 plotr plotr.338 : ! nform format code for input data plotr plotr.339 : ! 0 = free format input with plotr plotr.340 : ! optional x and y error bars plotr plotr.341 : ! plotr plotr.342 : ! card 13 ---nform = 0 only--- plotr plotr.343 : ! xdata dependent value plotr plotr.344 : ! terminate with empty card (/) plotr plotr.345 : ! ydata independent value plotr plotr.346 : ! yerr1 lower y error limit plotr plotr.347 : ! no y error bar if zero plotr plotr.348 : ! yerr2 upper y error limit plotr plotr.349 : ! if zero, equals yerr1 plotr plotr.350 : ! xerr1 x left error limit plotr plotr.351 : ! no x error bar if zero plotr plotr.352 : ! xerr2 x right error limit plotr plotr.353 : ! if zero, equals xerr1 plotr plotr.354 : ! plotr plotr.355 : ! plotr plotr.356 : ! all curves contain at least 10 points per decade (see delta). plotr plotr.357 : ! code can plot curves containing fewer than 10000 points (see plotr plotr.358 : ! max) without thinning. curves with more points are thinned plotr plotr.359 : ! based on a minimum spacing determined from max and the plotr plotr.360 : ! length of the x axis. plotr plotr.361 : ! plotr plotr.362 : !-------------------------------------------------------------------- plotr VIEWR viewr.43 : subroutine viewr viewr viewr.44 : !-------------------------------------------------------------------- viewr viewr.45 : ! viewr viewr.46 : ! View plots generated by plotr, covr, or dtfr. viewr viewr.47 : ! Postscript version. viewr viewr.48 : ! viewr viewr.49 : ! Character specifications are similar to DISSPLA, except that viewr viewr.50 : ! the default case is lower instead of upper. This allows viewr viewr.51 : ! mixed-case strings to be used in Postscript mode. The viewr viewr.52 : ! following shift characters are used: viewr viewr.53 : ! < = upper-case standard viewr viewr.54 : ! > = lower-case or mixed-case standard viewr viewr.55 : ! [ = upper-case greek viewr viewr.56 : ! ] = lower-case or mixed-case greek viewr viewr.57 : ! # = instructions viewr viewr.58 : ! Give one of the shift characters twice to get it instead of viewr viewr.59 : ! its action. The following instructions are supported: viewr viewr.60 : ! Ev = elevate by v as a fraction of the height viewr viewr.61 : ! if v is missing or D is given, use .5 viewr viewr.62 : ! Lv = lower by v as a fraction of the height viewr viewr.63 : ! if v is missing or D is given, use .5 viewr viewr.64 : ! Hv = change height by v as a fraction of the height viewr viewr.65 : ! if v is missing or D is given, use .5 viewr viewr.66 : ! Fi = change to font number i viewr viewr.67 : ! Mi = change mode number, where mode 0 is the lower 128 viewr viewr.68 : ! postscript characters and mode 1 is the upper 128 viewr viewr.69 : ! X = reset E, L, or H. Font and Mode must be viewr viewr.70 : ! reset explicitly. viewr viewr.71 : ! c is a real number, i is an integer. viewr viewr.72 : ! viewr viewr.73 : !---input-------------------------------------------------------- viewr viewr.74 : ! viewr viewr.75 : ! card 1 viewr viewr.76 : ! infile input file viewr viewr.77 : ! nps postscript output file viewr viewr.78 : ! viewr viewr.79 : !---data file format--------------------------------------------- viewr viewr.80 : ! viewr viewr.81 : ! card 1 viewr viewr.82 : ! lori page orientation (def=1) viewr viewr.83 : ! 0 portrait (7.5x10in) viewr viewr.84 : ! 1 landscape (10x7.5in) viewr viewr.85 : ! istyle character style (def=2) viewr viewr.86 : ! 1 roman viewr viewr.87 : ! 2 swiss viewr viewr.88 : ! size character size option viewr viewr.89 : ! pos = height in page units viewr viewr.90 : ! neg = height as fraction of subplot size viewr viewr.91 : ! (default=.30) viewr viewr.92 : ! ipcol page color (def=white) viewr viewr.93 : ! 0=white viewr viewr.94 : ! 1=navajo white viewr viewr.95 : ! 2=blanched almond viewr viewr.96 : ! 3=antique white viewr viewr.97 : ! 4=very pale yellow viewr viewr.98 : ! 5=very pale rose viewr viewr.99 : ! 6=very pale green viewr viewr.100 : ! 7=very pale blue viewr viewr.101 : ! viewr viewr.102 : ! -----repeat cards 2 through 13 for each curve----- viewr viewr.103 : ! viewr viewr.104 : ! card 2 viewr viewr.105 : ! iplot plot index viewr viewr.106 : ! 99 = terminate plotting job viewr viewr.107 : ! 1 = new axes, new page viewr viewr.108 : ! -1 = new axes, existing page viewr viewr.109 : ! n = nth additional plot on existing axes viewr viewr.110 : ! -n = start a new set of curves using viewr viewr.111 : ! the alternate y axis viewr viewr.112 : ! default = 1 viewr viewr.113 : ! iwcol window color (def=white) viewr viewr.114 : ! color list same as for ipcol above viewr viewr.115 : ! factx factor for energies (default=1.) viewr viewr.116 : ! facty factor for cross-sections (default=1.) viewr viewr.117 : ! xll,yll lower-left corner of plot area viewr viewr.118 : ! ww,wh,wr window width, height, and rotation angle viewr viewr.119 : ! (plot area defaults to one plot per page) viewr viewr.120 : ! viewr viewr.121 : ! -----cards 3 thru 7 for iplot = 1 or -1 only----- viewr viewr.122 : ! viewr viewr.123 : ! card 3 viewr viewr.124 : ! t1 first line of title viewr viewr.125 : ! 80 characters allowed. viewr viewr.126 : ! default=none viewr viewr.127 : ! viewr viewr.128 : ! card 3a viewr viewr.129 : ! t2 second line of title viewr viewr.130 : ! 80 characters allowed. viewr viewr.131 : ! default=none viewr viewr.132 : ! viewr viewr.133 : ! card 4 viewr viewr.134 : ! itype type for primary axes viewr viewr.135 : ! 1 = linear x - linear y viewr viewr.136 : ! 2 = linear x - log y viewr viewr.137 : ! 3 = log x - linear y viewr viewr.138 : ! 4 = log x - log y viewr viewr.139 : ! set negative for 3d axes viewr viewr.140 : ! 0 = no plot, titles only viewr viewr.141 : ! default=4 viewr viewr.142 : ! jtype type for alternate y axis or z axis viewr viewr.143 : ! 0 = none viewr viewr.144 : ! 1 = linear viewr viewr.145 : ! 2 = log viewr viewr.146 : ! default=0 viewr viewr.147 : ! igrid grid and tic mark control viewr viewr.148 : ! 0 = no grid lines or tic marks viewr viewr.149 : ! 1 = grid lines viewr viewr.150 : ! 2 = tic marks on outside viewr viewr.151 : ! 3 = tic marks on inside viewr viewr.152 : ! default=2 viewr viewr.153 : ! ileg option to write a legend. viewr viewr.154 : ! 0 = none viewr viewr.155 : ! 1 = write a legend block with upper left viewr viewr.156 : ! corner at xtag,ytag (see below) viewr viewr.157 : ! 2 = use tag labels on each curve with viewr viewr.158 : ! a vector from the tag to the curve viewr viewr.159 : ! default=0 viewr viewr.160 : ! xtag x coordinate of upper left corner viewr viewr.161 : ! of legend block viewr viewr.162 : ! ytag y coord of upper left corner viewr viewr.163 : ! default=upper left corner of plot viewr viewr.164 : ! viewr viewr.165 : ! card 5 viewr viewr.166 : ! xmin lowest energy to be plotted viewr viewr.167 : ! xmax highest energy to be plotted viewr viewr.168 : ! xstep x axis step viewr viewr.169 : ! default = automatic scales viewr viewr.170 : ! (for linear, give all 3, or none) viewr viewr.171 : ! (for log, give first 2, or none) viewr viewr.172 : ! viewr viewr.173 : ! card 5a viewr viewr.174 : ! xlabl label for x axis viewr viewr.175 : ! 80 characters allowed. viewr viewr.176 : ! (default = no label, no numbering) viewr viewr.177 : ! viewr viewr.178 : ! card 6 viewr viewr.179 : ! ymin lowest value of y axis. viewr viewr.180 : ! ymax highest value of y axis. viewr viewr.181 : ! ystep step for y ayis (linear scales only) viewr viewr.182 : ! default = automatic scales viewr viewr.183 : ! (for linear, give all 3, or none) viewr viewr.184 : ! (for log, give first 2, or none) viewr viewr.185 : ! viewr viewr.186 : ! card 6a viewr viewr.187 : ! ylabl label for y axis viewr viewr.188 : ! 80 characters allowed. viewr viewr.189 : ! (default = no label, no numbering) viewr viewr.190 : ! viewr viewr.191 : ! card 7 (jtype.gt.0 only) viewr viewr.192 : ! rmin lowest value of secondary y axis or z axis viewr viewr.193 : ! rmax highest value of secondary y axis or z axis viewr viewr.194 : ! rstep step for secondary y axis or z axis viewr viewr.195 : ! (default = automatic scale) viewr viewr.196 : ! (for linear, give all 3, or none) viewr viewr.197 : ! (for log, give first 2, or none) viewr viewr.198 : ! viewr viewr.199 : ! card 7a (jtype.gt.0 only) viewr viewr.200 : ! rl label for alternate y axis or z axis viewr viewr.201 : ! 80 characters allowed. viewr viewr.202 : ! (default = no label, no numbering) viewr viewr.203 : ! viewr viewr.204 : ! card 8 -- dummy input card for consistency with plotr viewr viewr.205 : ! it always should be 0/ viewr viewr.206 : ! viewr viewr.207 : ! -----cards 9 and 10 for 2d plots only----- viewr viewr.208 : ! viewr viewr.209 : ! card 9 viewr viewr.210 : ! icon symbol and connection option viewr viewr.211 : ! 0 = points connected, no symbols viewr viewr.212 : ! -i = points not connected, symbol at every viewr viewr.213 : ! ith point viewr viewr.214 : ! i = points connected, symbol at every ith viewr viewr.215 : ! points viewr viewr.216 : ! default=0 viewr viewr.217 : ! isym no. of symbol to be used viewr viewr.218 : ! 0 = square viewr viewr.219 : ! 1 = octagon viewr viewr.220 : ! 2 = triangle viewr viewr.221 : ! 3 = cross viewr viewr.222 : ! 4 = ex viewr viewr.223 : ! 5 = diamond viewr viewr.224 : ! 6 = inverted triangle viewr viewr.225 : ! 7 = exed square viewr viewr.226 : ! 8 = crossed ex viewr viewr.227 : ! 9 = crossed diamond viewr viewr.228 : ! 10 = crossed octagon viewr viewr.229 : ! 11 = double triangle viewr viewr.230 : ! 12 = crossed square viewr viewr.231 : ! 13 = exed octagon viewr viewr.232 : ! 14 = triangle and square viewr viewr.233 : ! 15 = filled circle viewr viewr.234 : ! 16 = open circle viewr viewr.235 : ! 17 = open square viewr viewr.236 : ! 18 = filled square viewr viewr.237 : ! 19 = filled diamond viewr viewr.238 : ! 20 = filled triangle viewr viewr.239 : ! 21 = filled inverted triangle viewr viewr.240 : ! 22 = crossed circle viewr viewr.241 : ! 23 = exed circle viewr viewr.242 : ! 24 = exed diamond viewr viewr.243 : ! default=0 viewr viewr.244 : ! idash type of line to plot viewr viewr.245 : ! 0 = solid viewr viewr.246 : ! 1 = dashed viewr viewr.247 : ! 2 = chain dash viewr viewr.248 : ! 3 = chain dot viewr viewr.249 : ! 4 = dot viewr viewr.250 : ! 5 = invisible viewr viewr.251 : ! default=0 viewr viewr.252 : ! iccol curve color (def=black) viewr viewr.253 : ! 0=black viewr viewr.254 : ! 1=red viewr viewr.255 : ! 2=green viewr viewr.256 : ! 3=blue viewr viewr.257 : ! 4=magenta viewr viewr.258 : ! 5=cyan viewr viewr.259 : ! 6=brown viewr viewr.260 : ! 7=purple viewr viewr.261 : ! 8=orange viewr viewr.262 : ! ithick controls thickness of curve viewr viewr.263 : ! 0 = invisible (for shaded areas) viewr viewr.264 : ! (default=1) viewr viewr.265 : ! ishade shade pattern viewr viewr.266 : ! 0 = none viewr viewr.267 : ! 1 to 10 = 10% to 100% gray viewr viewr.268 : ! 11 to 20 = 45 deg right hatching viewr viewr.269 : ! 21 to 30 = 45 deg left hatching viewr viewr.270 : ! 31 to 40 = 45 deg cross hatching viewr viewr.271 : ! 41 to 50 = shades of green viewr viewr.272 : ! 51 to 60 = shades of red viewr viewr.273 : ! 61 to 70 = shades of brown viewr viewr.274 : ! 71 to 80 = shades of blue viewr viewr.275 : ! default=0 viewr viewr.276 : ! viewr viewr.277 : ! card 10 ---ileg.ne.0 only--- viewr viewr.278 : ! aleg title for curve tag or legend block viewr viewr.279 : ! 80 characters allowed. viewr viewr.280 : ! default=blank viewr viewr.281 : ! viewr viewr.282 : ! card 10a ---ileg.eq.2 only--- viewr viewr.283 : ! xtag x position of tag title viewr viewr.284 : ! ytag y position of tag title viewr viewr.285 : ! xpoint x coordinate of vector point viewr viewr.286 : ! (.le.0 to omit vector) viewr viewr.287 : ! viewr viewr.288 : ! -----card 11 for 3d plots only----- viewr viewr.289 : ! viewr viewr.290 : ! card 11 viewr viewr.291 : ! xv,yv,zv abs. coords of view point viewr viewr.292 : ! defaults= 15.,-15.,15. viewr viewr.293 : ! x3,y3,z3 abs. sides of work box volume viewr viewr.294 : ! defaults=2.5,6.5,2.5 viewr viewr.295 : ! viewr viewr.296 : ! set x3 negative to flip the order of the axis on viewr viewr.297 : ! that side of the box (secondary energy, cosine). viewr viewr.298 : ! viewr viewr.299 : ! card 12 viewr viewr.300 : ! nform format code for input data viewr viewr.301 : ! 0 = free format input with viewr viewr.302 : ! optional x and y error bars viewr viewr.303 : ! 1 = free format input for a viewr viewr.304 : ! 3d family of curves z(x) vs y viewr viewr.305 : ! viewr viewr.306 : ! card 13 ---nform = 0 only--- 2-d data viewr viewr.307 : ! xdata independent value viewr viewr.308 : ! terminate with empty card (/) viewr viewr.309 : ! ydata dependent value viewr viewr.310 : ! yerr1 lower y error limit viewr viewr.311 : ! no y error bar if zero viewr viewr.312 : ! yerr2 upper y error limit viewr viewr.313 : ! if zero, equals yerr1 viewr viewr.314 : ! xerr1 x left error limit viewr viewr.315 : ! no x error bar if zero viewr viewr.316 : ! xerr2 x right error limit viewr viewr.317 : ! if zero, equals xerr1 viewr viewr.318 : ! viewr viewr.319 : ! card 14 ---nform = 1 only--- 3-d data viewr viewr.320 : ! y y value for curve viewr viewr.321 : ! repeat cards 13 and 13a for each curve viewr viewr.322 : ! terminate with empty card (/) viewr viewr.323 : ! viewr viewr.324 : ! card14a ---nform = 1 only--- viewr viewr.325 : ! x x value viewr viewr.326 : ! z z value viewr viewr.327 : ! repeat card 13a for each point in curve viewr viewr.328 : ! terminate with empty card (/) viewr viewr.329 : ! disspla version requires same x grid viewr viewr.330 : ! for each value of y. viewr viewr.331 : ! viewr viewr.332 : !-------------------------------------------------------------------- viewr MIXR mixr.11 : subroutine mixr mixr mixr.12 : !------------------------------------------------------------------- mixr mixr.13 : ! mixr mixr.14 : ! mixr mixr mixr.15 : ! mixr mixr.16 : ! Construct a new pendf tape with a specified set of mixr mixr.17 : ! reactions that are specified linear combinations of the mixr mixr.18 : ! cross sections from the input tapes. Mixr can also be mixr mixr.19 : ! used for endf tapes, but the input interpolation laws mixr mixr.20 : ! are ignored. This module can be used to construct mixed mixr mixr.21 : ! reactions for plotting (for example, elemental cross mixr mixr.22 : ! sections). The output file contains files 1 and 3 only. mixr mixr.23 : ! Linear-linear interpolation is assumed. mixr mixr.24 : ! mixr mixr.25 : ! user input -- mixr mixr.26 : ! mixr mixr.27 : ! card 1 -- units mixr mixr.28 : ! nout output unit for mixed cross sections mixr mixr.29 : ! nin1 first input unit (endf or pendf) mixr mixr.30 : ! nin2 second input unit mixr up3.20 : ! ... continue for nnin<=nninmx (=10) input units mixr mixr.32 : ! mixr mixr.33 : ! card 2 -- reaction list mixr up3.22 : ! mtn list of nmt<=nmtmx (=20) mt numbers for mixr up3.23 : ! the output reactions mixr mixr.36 : ! mixr mixr.37 : ! card 3 -- material list mixr up3.25 : ! matn, list of nmat<=nmatmx (=nninmx=10) pairs (matn,wtn) mixr up3.26 : ! wtn of material numbers and associated weighting factors mixr mixr.40 : ! mixr mixr.41 : ! card 4 -- temperature mixr mixr.42 : ! temp temperature (use zero except for pendf tapes) mixr mixr.43 : ! mixr mixr.44 : ! card 5 -- output material mixr mixr.45 : ! matd material number mixr mixr.46 : ! za za value mixr mixr.47 : ! awr awr value mixr mixr.48 : ! mixr mixr.49 : ! card 6 -- file 1 comment card mixr up3.28 : ! des description (66 char max) mixr mixr.51 : ! mixr mixr.52 : !------------------------------------------------------------------- mixr PURR purr.58 : subroutine purr purr purr.59 : !------------------------------------------------------------------- purr purr.60 : ! purr purr.61 : ! Probabalistic unresolved calculation of purr purr.62 : ! Bondarenko moments and probability tables purr purr.63 : ! purr purr.64 : !------------------------------------------------------------------- purr purr.65 : ! purr purr.66 : ! Purr constructs a series of resonance ladders that obey the purr purr.67 : ! distributions given in MT151 of the ENDF tape. Each ladder purr purr.68 : ! is sampled randomly to produce contributions to a probability purr purr.69 : ! table and a set of bondarenko moments. When the table is purr purr.70 : ! complete, Bondarenko moments are computed from the table to purr purr.71 : ! provide a convergence check. All temperatures are computed purr purr.72 : ! simultaneously to preserve temperature correlations. The purr purr.73 : ! Bondarenko tables are written on the pendf tape using MT152, purr purr.74 : ! and the probability tables are written using MT153. purr purr.75 : ! A conditional probability for heating is added to the table. purr purr.76 : ! If partial heating cross sections for elastic (302), fission purr purr.77 : ! (318), and capture (402) are available from heatr, full purr purr.78 : ! fluctuations will be provided for the total heating. purr purr.79 : ! Otherwise, the same value will be provided for each bin. purr purr.80 : ! purr purr.81 : !---input data cards--------------------------------------------- purr purr.82 : ! purr purr.83 : ! card 1 purr purr.84 : ! nendf unit for endf tape purr purr.85 : ! nin unit for input pendf tape purr purr.86 : ! nout unit for output pendf tape purr purr.87 : ! card 2 purr purr.88 : ! matd material to be processed purr purr.89 : ! matd=0 terminates purr purr purr.90 : ! ntemp no. of temperatures (default=1) purr purr.91 : ! nsigz no of sigma zeros (default=1) purr purr.92 : ! nbin no. of probability bins (15 or more) purr purr.93 : ! nladr no. of resonance ladders purr purr.94 : ! iprint print option (0=min, 1=max, def=1) purr purr.95 : ! nunx no. of energy points desired (def=0=all) purr purr.96 : ! card 3 purr purr.97 : ! temp temperatures in kelvin (including zero) purr purr.98 : ! card 4 purr purr.99 : ! sigz sigma zero values (including infinity) purr purr.100 : ! purr purr.101 : !------------------------------------------------------------------- purr LEAPR leapr.50 : subroutine leapr leapr leapr.51 : !-------------------------------------------------------------------- leapr leapr.52 : ! leapr leapr.53 : ! Calculate S(alpha,beta) leapr leapr.54 : ! leapr leapr.55 : ! Calculates the thermal scattering law, S(alpha,beta), in the leapr leapr.56 : ! incoherent and gaussian approximations. The scattering law leapr leapr.57 : ! for solid-type frequency distributions is calculated using leapr leapr.58 : ! the phonon expansion method without recourse to the usual leapr leapr.59 : ! edgewood and sct approximations. If desired, an analytic leapr leapr.60 : ! representation of diffusion or free-gas scattering can be leapr leapr.61 : ! convolved with the solid-type scattering law. In addition, leapr leapr.62 : ! up to 50 discrete oscillators can be convolved with the leapr leapr.63 : ! continuous scattering law. The results of the calculation leapr leapr.64 : ! are written out in ENDF-6 File 7 format, ready to be leapr leapr.65 : ! processed by the thermr module of NJOY. leapr leapr.66 : ! leapr leapr.67 : ! It is possible to generate S(alpha,beta) for composite leapr leapr.68 : ! moderators like BeO, where Be in BeO is combined with O in leapr leapr.69 : ! BeO and normalized to be used with the Be cross section. leapr leapr.70 : ! leapr leapr.71 : ! Incoherent elastic or coherent elastic scattering functions leapr leapr.72 : ! can also be included using the ENDF-6 format. The incoherent leapr leapr.73 : ! result depends on the Debye-Waller factor computed during the leapr leapr.74 : ! S(alpha,beta) calculation. The coherent result is computed leapr leapr.75 : ! using the methods developed for the thermr module of NJOY leapr leapr.76 : ! (which were based on the HEXSCAT code). This scattering leapr leapr.77 : ! law depends on the Debye-Waller factor from the S(alpha,beta) leapr leapr.78 : ! calculation, on lattice parameters that are built in to data leapr leapr.79 : ! statements in the code, and on the coherent scattering cross leapr leapr.80 : ! section (which is also built in). leapr leapr.81 : ! leapr leapr.82 : ! A special option exists for liquid hydrogen and deuterium. leapr leapr.83 : ! A solid-type spectrum and a diffusive spectrum can be given leapr leapr.84 : ! in the normal way. The resulting S(alpha,beta) is then leapr leapr.85 : ! convolved with rotational modes calculated using the method leapr leapr.86 : ! of Young and Koppel. Because of the inclusion of spin leapr leapr.87 : ! correlations, the resulting S(alpha,beta) is not symmetric in leapr leapr.88 : ! beta, and the lasym option is used in MF7. leapr leapr.89 : ! leapr leapr.90 : ! This module is loosly based on the British code 'LEAP+ADDELT', leapr leapr.91 : ! originally written by R.C.F.McLatchie at Harwell (1962, leapr leapr.92 : ! unpublished), then implemented by A.T.D.Butland at Winfrith leapr leapr.93 : ! (AEEW 1200, 1973), and finally modified to work better for leapr leapr.94 : ! cold moderators as part of the thesis of D.J.Picton, now leapr leapr.95 : ! at the University of Birmingham. The first ENDF and NJOY leapr leapr.96 : ! compatible version was prepared by R.E.MacFarlane at leapr leapr.97 : ! Los Alamos in 1987. The main changes to the original code leapr leapr.98 : ! were: 1) the change to NJOY style, 2) the addition of ENDF-6 leapr leapr.99 : ! output, 3) the addition of incoherent elastic output, 4) the leapr leapr.100 : ! addition of a coherent elastic calculation, 5) a major leapr leapr.101 : ! speed up of the diffusion calculation by using interpolation leapr leapr.102 : ! instead of direct recalculation of S-solid(alpha,beta), leapr leapr.103 : ! and 6) the liquid hydrogen and deuterium treatments. leapr leapr.104 : ! A second version was prepared by R.E.MacFarlane in 1989 by leapr leapr.105 : ! removing the Edgewood and SCT approximations in favor of leapr leapr.106 : ! direct use of the phonon expansion for all phonon orders. leapr leapr.107 : ! In addition, free gas scattering was added, the code was leapr leapr.108 : ! simplified and scratch tapes were eliminated. Thus, the leapr leapr.109 : ! code takes advantage of the capabilities of large, fast leapr leapr.110 : ! computers that weren't available to the designers of the leapr leapr.111 : ! original lEAP code. This 1992 version changed to using leapr leapr.112 : ! the asymmetric S(alpha,beta) for better numerics on leapr leapr.113 : ! short-word machines, added the mixed moderator capability, leapr leapr.114 : ! rebuilt the discrete-oscillator calculation for better leapr leapr.115 : ! accuracy, and made many other smaller improvements. leapr leapr.116 : ! leapr leapr.117 : !----- user input (free format) --------------------------------- leapr leapr.118 : ! leapr leapr.119 : ! card 1 - units leapr leapr.120 : ! nout endf output unit for thermal file leapr leapr.121 : ! leapr leapr.122 : ! card 2 - title leapr leapr.123 : ! leapr leapr.124 : ! card 3 - run control leapr leapr.125 : ! ntempr number of temperatures (def=1) leapr leapr.126 : ! iprint print control (0=min, 1=more, 2=most, def=1) leapr leapr.127 : ! nphon phonon-expansion order (def=100) leapr leapr.128 : ! leapr leapr.129 : ! card 4 - endf output control leapr leapr.130 : ! mat endf mat number leapr leapr.131 : ! za 1000*z+a for principal scatterer leapr leapr.132 : ! isabt sab type (0=s, 1=ss, def=0) leapr leapr.133 : ! ilog log flag (0=s, 1=log10(s), def=0) leapr leapr.134 : ! leapr leapr.135 : ! card 5 - principal scatterer control leapr leapr.136 : ! awr weight ratio to neutron for principal scatterer leapr leapr.137 : ! spr free atom cross section for principal scatterer leapr leapr.138 : ! npr number of principal scattering atoms in compound leapr leapr.139 : ! iel coherent elastic option leapr leapr.140 : ! 0 none (default) leapr leapr.141 : ! 1 graphite leapr leapr.142 : ! 2 beryllium leapr leapr.143 : ! 3 beryllium oxide leapr leapr.144 : ! 4 aluminum leapr leapr.145 : ! 5 lead leapr leapr.146 : ! 6 iron leapr leapr.147 : ! ncold cold hydrogen option leapr leapr.148 : ! 0 none (default) leapr leapr.149 : ! 1 ortho hydrogen leapr leapr.150 : ! 2 para hydrogen leapr leapr.151 : ! 3 otho deuterium leapr leapr.152 : ! 4 para deuterium leapr leapr.153 : ! nsk 0 none (default) leapr leapr.154 : ! 1 vineyard leapr leapr.155 : ! 2 skold leapr leapr.156 : ! leapr leapr.157 : ! card 6 - secondary scatterer control leapr leapr.158 : ! nss number of secondary scatterers (0 or 1) leapr leapr.159 : ! b7 secondary scatterer type leapr leapr.160 : ! (0=sct only, 1=free, 2=diffusion) leapr leapr.161 : ! aws weight ratio to neutron for secondary scatterer leapr leapr.162 : ! sps free atoms cross section for secondary scatterer leapr leapr.163 : ! mss number of atoms of this type in the compound leapr leapr.164 : ! leapr leapr.165 : ! card 7 - alpha, beta control leapr leapr.166 : ! nalpha number of alpha values leapr leapr.167 : ! nbeta number of beta values leapr leapr.168 : ! lat if lat.eq.1, alpha and beta values are scaled leapr leapr.169 : ! by .0253/tev, where tev is temp in ev. (def=0) leapr leapr.170 : ! leapr leapr.171 : ! card 8 - alpha values (increasing order) leapr leapr.172 : ! card 9 - beta values (increasing order) leapr leapr.173 : ! leapr leapr.174 : ! scatterer loop, do temperature loop for principal scatterer. leapr leapr.175 : ! repeat for secondary scatterer (if any) if b7=0. leapr leapr.176 : ! leapr leapr.177 : ! temperature loop, repeat cards 10 to 18 for each temperature leapr leapr.178 : ! leapr leapr.179 : ! card 10 - temperature (k) leapr leapr.180 : ! a negative value means skip cards 11 to 18, leapr leapr.181 : ! thereby using previous parameters for this temp. leapr leapr.182 : ! leapr leapr.183 : ! card 11 -- continuous distribution control leapr leapr.184 : ! delta interval in ev leapr leapr.185 : ! ni number of points leapr leapr.186 : ! leapr leapr.187 : ! card 12 -- rho(energy) (order of increasing ev) leapr leapr.188 : ! leapr leapr.189 : ! card 13 - continuous distribution parameters leapr leapr.190 : ! twt translational weight leapr leapr.191 : ! c diffusion constant (zero for free gas) leapr leapr.192 : ! tbeta normalization for continuous part leapr leapr.193 : ! leapr leapr.194 : ! card 14 - discrete oscillator control leapr leapr.195 : ! nd number of discrete oscillators leapr leapr.196 : ! leapr leapr.197 : ! card 15 - oscillator energies (ev) leapr leapr.198 : ! card 16 - oscillator weights (sum to 1.-tbeta-twt) leapr leapr.199 : ! leapr leapr.200 : ! card 17 - pair correlation control (nsk.ne.0 only) leapr leapr.201 : ! nka number of kappa values leapr leapr.202 : ! dka kappa increment (inv. angstroms) leapr leapr.203 : ! leapr leapr.204 : ! card 18 skappa values in increasing order (inv. ang.) leapr leapr.205 : ! leapr leapr.206 : ! card 19 coherent scattering fraction for nsk.eq.2 only leapr leapr.207 : ! cfrac coherent fraction leapr leapr.208 : ! leapr leapr.209 : ! card 20 - file 1 comments, repeat until blank line is read. leapr leapr.210 : ! leapr leapr.211 : !-------------------------------------------------------------------- leapr GASPR gaspr.10 : subroutine gaspr gaspr gaspr.11 : !------------------------------------------------------------------- gaspr gaspr.12 : ! gaspr gaspr.13 : ! Add gas production reactions (mt203-207) to the pendf tape. gaspr gaspr.14 : ! Any old gas sections on the input pendf tape are deleted. gaspr gaspr.15 : ! The directory is updated to show the new reactions. gaspr gaspr.16 : ! This module can be run anywhere in the pendf preparation gaspr gaspr.17 : ! sequence as long as it is somewhere after broadr. gaspr gaspr.18 : ! gaspr gaspr.19 : ! If the input pendf tape omits mt103 to mt107, but it does gaspr gaspr.20 : ! have the corresponding charged-particle cross sections, they gaspr gaspr.21 : ! are processed and will appear in the appropriate mt20x section. gaspr gaspr.22 : ! gaspr gaspr.23 : !---input specifications (free format)-------------------------- gaspr gaspr.24 : ! gaspr gaspr.25 : ! card 1 gaspr gaspr.26 : ! nendf unit for endf tape gaspr gaspr.27 : ! nin unit for input pendf tape gaspr gaspr.28 : ! nout unit for output pendf tape gaspr gaspr.29 : ! gaspr gaspr.30 : !------------------------------------------------------------------- gaspr