User Input for NJOY 99, updated through version 259. 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 program njoy c c ****************************************************************** c * * c * njoy nuclear data processing system * c * version 99.259 * c * 16 Oct 2007 * c * * c ****************************************************************** c * * c * njoy is a system of processing modules intended to convert * c * evaluated nuclear data in the endf format into forms useful * c * for practical applications. * c * * c * reconr...reconstruct pointwise cross sections from endf/b * c * resonance parameters and interpolation schemes. * c * * c * broadr...doppler broaden and thin pointwise cross sections. * c * * c * unresr...compute effective pointwise self-shielded cross * c * sections in the unresolved energy range. * c * * c * heatr...compute heat production cross sections (kerma) * c * and damage energy production. * c * * c * thermr...generate neutron scattering cross sections and * c * point-to-point scattering kernels in the thermal range * c * for free or bound atoms. * c * * c * groupr...generate self-shielded multigroup cross sections and * c * group-to-group scattering and photon production matrices. * c * * c * gaminr...compute multigroup photon interaction cross sections, * c * scattering matrices, and heat production. * c * * c * errorr...construct multigroup covariance matrices. * c * * c * covr...process covariance data from errorr * c * * c * moder...convert between endf/b standard coded mode and the * c * njoy blocked binary mode. * c * * c * dtfr...output and plot multigroup data for discrete ordinates * c * transport codes. * c * * c * ccccr...format multigroup data into the cccc standard * c * interface files isotxs, brkoxs, and dlayxs. * c * * c * matxsr...convert multigroup data into the comprehensive matxs * c * cross section interface format. * c * * c * resxsr...prepare a cccc-like file of pointwise resonance * c * cross sections for thermal flux calculations * c * * c * acer...prepare library for the los alamos continuous energy * c * monte-carlo code mcnp. * c * * c * powr...convert multigroup data into libraries for the thermal * c * powr reactor codes epri-cell and epri-cpm. * c * * c * wimsr...convert multigroup data into libraries for the * c * reactor assembly codes wims-d or wims-e. * c * * c * plotr...plot endf, pendf, gendf, or exp. cross sections, * c * distributions, or matrices. * c * * c * viewr...view plots from plotr, dtfr, covr, etc. in postscript * c * * c * mixr...mix file 3 cross sections (for example, to make * c * elemental cross sections) for plotting, etc. * c * * c * purr...generate unresolved-resonance probability tables * c * for the mcnp monte carlo code * c * * c * leapr...generate s(alpha,beta) for thermal moderators * c * * c * gaspr...add gas production (mt203-207) to pendf * c * * c * each module is an essentially independent code segment. the * c * main program controls the order in which modules are used * c * and contains the utility subroutines used by all modules. * c * * c *---input specifications (free format)---------------------------* c * * c * card 1 module option * c * * c * module six character module name, e.g., reconr. * c * it is not necessary to use quotes. * c * * c * repeat card 1 for each module desired, and * c * use the name "stop" to terminate program. * c * * c * see the comments at the start of each module for * c * its specific input instructions. * c * * c *--- code conversion --------------------------------------------* c * * c * code conversion is handled using the "*if" constructs of * c * the upd code (which is a code for maintaining fortran codes * c * similar to update). the logical variables that can be * c * set are the following: * c * * c * sw -- set for short-word machines (32 bit). leave * c * unset for 64 bit machines. * c * * c ****************************************************************** c RECONR c c ****************************************************************** c * * c * reconstruct pointwise cross sections * c * * c * resonance cross sections are calculated using the methods of * c * resend, with modifications to the method of generating the * c * energy grid and the method of combining resonance and * c * background cross sections. * c * * c * this program generates an energy grid which is the union of * c * an input grid (if any), the resonance energies (if any), and * c * the energies of cross sections in mf3 and mf13 (or mf23). * c * the pointwise cross sections are then computed on this grid * c * and points are added so that the resonance cross sections and * c * any cross sections represented by non-linear interpolation * c * are reproduced within a specified tolerance by linear inter- * c * polation. psi-chi reconstruction can be used if desired. * c * sections which are not cross sections (mu,nu) and photon * c * multiplicities (mf12) are not processed. redundant reactions * c * are reconstructed to be the sum of their parts. the pendf * c * tape contains point cross sections in mf3 and mf13 (or mf23) * c * and a description of the processing in mf1. the mf1 diction- * c * ary is updated. the c1 and c2 fields of the second card in * c * mf1 contain the temperature and reconstruction tolerance * c * respectively. an mf2 appropriate to no resonance parameters * c * is constructed with the potential scattering length added. * c * * c * if unresolved parameters are present, the infinitely dilute * c * cross sections are computed on a special energy grid chosen * c * to preserve the required interpolation properties. this * c * table is added to the pendf tape using a special format in * c * mf2/mt152, and the table is also used to compute the * c * uresolved contributions in mf3. this allows resolved * c * resonance cross sections which overlap the resolved range * c * to be recovered by subtraction. * c * * c *---input specifications (free format)---------------------------* c * * c * card 1 * c * nendf unit for endf/b tape * c * npend unit for pendf tape * c * card 2 * c * tlabel 66 character label for new pendf tape * c * delimited with quotes, ended with /. * c * card 3 * c * mat material to be reconstructed * c * ncards number of cards of descriptive data for new mf1 * c * (default=0) * c * ngrid number of user energy grid points to be added. * c * (default=0) * c * card 4 * c * err fractional reconstruction tolerance used when * c * resonance-integral error criterion (see errint) * c * is not satisfied. * c * tempr reconstruction temperature (deg kelvin) * c * (default=0) * c * errmax fractional reconstruction tolerance used when * c * resonance-integral error criterion is satisfied * c * (errmax.ge.err, default=10*err) * c * errint maximum resonance-integral error (in barns) * c * per grid point (default=err/20000) * c * (note: the max cross section difference for * c * linearization, errlim, and for reconstruction, * c * errmin, are also tied to errint. to get maximum * c * accuracy, set errint to a very small number. * c * for economical production, use the defaults.) * c * card 5 * c * cards ncards of descriptive comments for mt451 * c * each card delimited with quotes, ended with /. * c * card 6 * c * enode users energy grid points * c * * c * cards 3, 4, 5, 6 must be input for each material desired * c * mat=0/ terminates execution of reconr. * c * * c ****************************************************************** c BROADR c c ****************************************************************** c * * c * doppler broaden and thin neutron point cross sections * c * * c * a modified version of the kernel broadening method developed * c * for sigma1 (d.e.cullen, llnl) is used. cross sections * c * for low threshold reactions are unionized on the grid of the * c * total cross section, then broadened and thinned in parallel. * c * high threshold reactions are not broadened. the total and * c * and nonelastic are reconstructed to equal the sum of parts. * c * * c * the output energy grid for broadened cross sections is * c * constructed adaptively (as in reconr) so that the results * c * represent the true function within the given tolerance. * c * energy values are either removed from the original grid, or * c * new values are added between the original points. thus, a * c * given energy range can have more or fewer points than the * c * original energy grid. * c * * c * for high temperatures and low energies where the original * c * sigma1 breaks down, a new direct expansion of the doppler * c * integral is used. * c * * c * if the temperature is close to 293.6 K (.0253 ev), broadr * c * computes and displays thermal cross sections, maxwellian * c * integrals (one-group thermal cross sections), g-factors, * c * integral ratios (eta, alpha), the k1 integral and the * c * corresponding 1/v-equivalent, and resonance integrals. * c * * c * the results are written out in pendf format with each * c * temperature represented as a different mat. dictionaries * c * are corrected to reflect the effects of thinning. * c * * c *---input specifications (free format)---------------------------* c * * c * card 1 * c * nendf input endf tape (for thermal nubar only) * c * nin input pendf tape * c * nout output pendf tape * c * card 2 * c * mat1 material to be processed * c * ntemp2 number of final temperatures (maximum=10) * c * istart restart (0 no, 1 yes, default 0) * c * istrap bootstrap (0 no, 1 yes, default 0) * c * temp1 starting temperature from nin (default=0.k) * c * card 3 * c * errthn fractional tolerance for thinning * c * thnmax max. energy for broadening and thinning * c * (default=1 mev) * c * errmax fractional tolerance used when integral criterion * c * is satisfied (same usage as in reconr) * c * (errmax.ge.errthn, default=10*errthn) * c * errint parameter to control integral thinning * c * (usage as in reconr) (default=errthn/20000) * c * set very small to turn off integral thinning. * c * (a good choice for the convergence parameters * c * errthn, errmax, and errint is the same set of * c * values used in reconr) * c * card 4 * c * temp2 final temperatures (deg kelvin) * c * card 5 * c * mat1 next mat number to be processed with these * c * parameters. terminate with mat1=0. * c * * c *---input options------------------------------------------------* c * * c * the output tape will contain the ntemp2 final temperatures * c * specified. it is necessary to have temp1.le.temp2(1). * c * if temp2.eq.temp1, the data will be thinned only. * c * * c * restart continue broadening an existing pendf tape. all * c * temperatures are copied through temp1. additional * c * final temperatures are added by starting with the * c * data at temp1. * c * * c * bootstrap if bootstrap is not requested, each final tempera- * c * ture is generated by broadening directly from * c * temp1 to temp2. if bootstrap is requested, each * c * final temperature is broadened from the preceding * c * temperature. this option is faster due to the * c * thinning in the previous step. however, errors * c * accumulate. * c * * c * thnmax the upper limit for broadening and thinning is the * c * lowest of the input value of thnmax, the lowest * c * reaction threshold, or the start of the unresolved * c * range. if there is resolved-unresolved overlap, * c * the overlap region is included in the broadening. * c * a negative value of thnmax will override the * c * resolved and threshold limits. This allows the * c * first few threshold reactions to be broadened if * c * desired. the magnitude of thnmax must be chosen * c * to keep the number of broadenable reactions less * c * than or equal to the maximum of ntt (10). * c * * c ****************************************************************** c UNRESR c c ****************************************************************** c * * c * compute unresolved resonance cross-sections * c * * c * the method of etox is used to compute self-shielded * c * unresolved resonance cross-sections on the energy grid of * c * the unresolved parameters. subsequent interpolation is * c * to be on the cross-sections and not on the parameters. * c * additional energy grid points are added at quarter lethargy * c * intervals if only three or fewer grid points are found. * c * the accurate hwang quadrature set is used for the integrals. * c * * c *---input specifications (free format)---------------------------* c * * c * card 1 * c * nendf unit for endf/b tape * c * nin unit for input pendf tape * c * nout unit for output pendf tape * c * card 2 * c * matd material to be processed * c * ntemp no. of temperatures (10 max) * c * nsigz no. of sigma zeroes (10 max) * c * iprint print option (0=min, 1=max) (default=0) * c * card 3 * c * temp temperatures in kelvin (including zero) * c * card 4 * c * sigz sigma zero values (including infinity) * c * cards 2, 3, 4 must be input for each material desired * c * matd=0/ terminates execution of unresr. * c * * c ****************************************************************** c HEATR c c ****************************************************************** c * * c * compute heating kerma (kinetic energy release in material) * c * and radiation damage energy production * c * * c * the prompt kerma is computed pointwise on the grid of the * c * total cross section from the input pendf tape and written * c * onto the output pendf tape at infinite dilution using the * c * 300 series of mt numbers. all temperatures on the input pendf * c * tape for the desired material are processed. the dictionary * c * is revised. reaction q values are obtained from the endf/b * c * tape unless the user enters his own value. partial kermas * c * can be requested for self-shielding calculations or other * c * purposes. the code uses the energy balance method where * c * photon files are available and deposits all photon energy * c * locally when files are not available. this assures * c * consistency between neutron heating and energy deposition by * c * subsequent photon interactions. an exception is made for * c * capture where recoil is computed by momentum conservation. * c * photon files are used to estimate the average photon momentum * c * when available. a diagnostic message is printed if the * c * momentum calculation leads to a significant error in * c * energy conservation. * c * * c * if desired, the energy-balance kerma factors can be compared * c * with conservative kinematic limits (set iprint=2). * c * a plot file for viewr can be automatically prepared. * c * * c * damage energy is computed using the lindhard electronic * c * screening damage function with a displacement threshold * c * from a table of default values for important elements * c * or a value provided by the user. * c * * c *---input specifications (free format)---------------------------* c * * c * card 1 * c * nendf unit for endf/b tape * c * nin unit for input pendf tape * c * nout unit for output pendf tape * c * nplot unit for graphical check output * c * card 2 * c * matd material to be processed * c * npk number of partial kermas desired (default=0) * c * nqa number of user q values (default=0) * c * ntemp number of temperatures to process * c * (default=0, meaning all on pendf) * c * local 0/1=gamma rays transported/deposited locally * c * (default=0) * c * iprint print (0 min, 1 max, 2 check) (default=0) * c * ed displacement energy for damage * c * (default from built-in table) * c * card 3 for npk gt 0 only * c * mtk mt numbers for partial kermas desired * c * total (mt301) will be provided automatically. * c * partial kerma for reaction mt is mt+300 * c * and may not be properly defined unless * c * a gamma file for mt is on endf tape. * c * special values allowed-- * c * 303 non-elastic (all but mt2) * c * 304 inelastic (mt51 thru 91) * c * 318 fission (mt18 or mt19, 20, 21, 38) * c * 401 disappearance (mt102 thru 120) * c * 442 total photon ev-barns * c * 443 total kinematic kerma (high limit) * c * damage energy production values-- * c * 444 total * c * 445 elastic (mt2) * c * 446 inelastic (mt51 thru 91) * c * 447 disappearance (mt102 thru 120) * c * cards 4 and 5 for nqa gt 0 only * c * card 4 * c * mta mt numbers for users q values * c * card 5 * c * qa user specified q values (ev) * c * (if qa.ge.99.e6, read in variable qbar * c * for this reaction) * c * card 5a variable qbar (for reactions with qa flag only) * c * qbar tab1 record giving qbar versus e (1000 words max) * c * * c ****************************************************************** c THERMR c c ****************************************************************** c * * c * generate neutron scattering cross sections and point-to-point * c * scattering kernels in the thermal range * c * * c * add pointwise scattering cross sections and scattering * c * matrices to an existing pendf tape. cross sections are * c * added to mf3 and matrices are written in mf6 (using a * c * modified format). both using mtref for inelastic and * c * mtref+1 for elastic (if any). * c * * c * multiple scattering types (ie, h free and h in h2o) can be * c * written on one pendf tape by using different values of mtref * c * for each thermr run. if data for one mtref is already on * c * the tape, it will be replaced with the new cross sections. * c * the energy grid for coherent scattering is determined * c * adaptively so as to represent the sharp bragg edges to * c * a specified tolerance using linear interpolation. the * c * secondary energy grid for inelastic scattering is also deter- * c * mined adaptively. angular dependence is represented as * c * equally probable cosines. the initial energy grid is wired in* c * (see egrid in calcem). a special projection interpolation * c * scheme is used in groupr to integrate this relatively * c * coarse grid. * c * * c * current capabilities... * c * 1.) compute free-gas scattering matrices and normalize * c * to the elastic cross section on the old pendf tape. * c * 2.) compute incoherent matrices from read-in * c * s(alpha,beta) data. * c * 3.) compute coherent scattering from hexagonal lattices. * c * 4.) compute incoherent elastic scattering. * c * * c * for endf 3 to 5 formats, the constants used for coherent * c * elastic, incoherent elastic, and short-collision-time calcu- * c * lations are obtained from internal data statements based on * c * the original general atomic report on the evaluations * c * (ga-8774 revised, endf-269, july 1978). * c * * c * for endf6 format libraries, these constants are included * c * in the format. * c * * c *---input specifications (free format)---------------------------* c * * c * card 1 * c * nendf endf/b tape for mf7 data * c * nin old pendf tape * c * nout new pendf tape * c * card 2 * c * matde material desired on endf tape * c * matdp material desired on pendf tape * c * nbin number of equi-probable angles * c * ntemp number of temperatures * c * iinc inelastic options * c * 0 none * c * 1 compute as free gas * c * 2 reserved * c * 3 reserved * c * 4 read s(a,b) and compute matrix * c * icoh elastic options * c * 0 none * c * 1 graphite * c * 2 beryllium * c * 3 beryllium oxide * c * 11 polyethylene * c * 12 h(zrh) * c * 13 zr(zrh) * c * natom number of principal atoms * c * mtref mt for inelastic reaction (201-250 only) * c * iprint print option (0=minimum, 1=maximum, * c * 2=max. normal + intermediate results) * c * (default=0) * c * card 3 * c * tempr temperatures (kelvin) * c * card 4 * c * tol tolerance * c * emax maximum energy for thermal treatment * c * (for temperatures greater than 3000, * c * emax and the energy grid are scaled by * c * temp/300. free gas only.) * c * * c * nendf can be endf-6 format (e.g., from leapr) while * c * nin and nout are endf-4 or 5 format, if desired. * c * * c ****************************************************************** c GROUPR c c ****************************************************************** c * * c * compute self-shielded group-averaged cross sections * c * * c * produces self-shielded cross sections, neutron scattering * c * matrices, and photon production matrices. scattering and * c * photon matrices may be self-shielded if desired (see init). * c * bondarenko weighting is normally used. optionally, the flux * c * can be computed for an infinite mixture of heavy absorber * c * and light moderator. delayed neutron data and thermal * c * scattering matrices are handled specially. * c * * c * the integration over initial energy is handled in the same * c * way for all reaction types by using the integrand * c * feed*xsec*flux . * c * feed is the source into final energy group gprime and * c * legendre order l from initial energy e (see getff). for * c * vectors, the feed is 1. or a yield (nubar, mubar). for two * c * body scattering, a center-of-mass gaussian integration is used * c * to obtain accurate results even for small legendre components * c * of the group-to-group scattering. additional initial energy * c * quadrature points are added to integrate the known polynomial * c * order of this feed function. feed for tabulated continuum * c * reactions is computed exactly on the endf/b grid points and * c * then interpolated at e. a special projection interpolation * c * scheme is used for thermal matrices (see getaed). the feed * c * for analytic continuum reactions is exact. * c * * c *---input specifications (free format)---------------------------* c * * c * card1 * c * nendf unit for endf/b tape * c * npend unit for pendf tape * c * ngout1 unit for input gout tape (default=0) * c * ngout2 unit for output gout tape (default=0) * c * card2 * c * matb material to be processed * c * if ngout=0, matb<0 is an option to automatically * c * process all the mats on the endf input tape. * c * otherwise, matb<0 is a flag to add mts to and/or * c * replace individual mts on gout1. * c * ign neutron group structure option * c * igg gamma group structure option * c * iwt weight function option * c * lord legendre order * c * ntemp number of temperatures * c * nsigz number of sigma zeroes * c * iprint long print option (0/1=minimum/maximum) * c * (default=1) * c * card3 * c * title run label (up to 80 characters delimited by *, * c * ended with /) (default=blank) * c * card4 * c * temp temperatures in kelvin * c * card5 * c * sigz sigma zero values (including infinity) * c * * c * if ign=1, read neutron group structure (6a and 6b) * c * card6a * c * ngn number of groups * c * card6b * c * egn ngn+1 group breaks (ev) * c * * c * if igg=1, read gamma group structure (7a and 7b) * c * card7a * c * ngg number of groups * c * card7b * c * egg ngg+1 group breaks (ev) * c * * c * weight function options (8a,8b,8c,8d) * c * card8a flux calculator parameters (iwt.lt.0 only) * c * ehi break between computed flux and bondarenko flux * c * (must be in resolved range) * c * sigpot estimate of potential scattering cross section * c * nflmax maximum number of computed flux points * c * ninwt tape unit for new flux parameters (default=0) * c * note: weighting flux file is always written binary * c * jsigz index of reference sigma zero in sigz array * c * (default=0) * c * alpha2 alpha for admixed moderator (def=o=none) * c * sam admixed moderator xsec in barns per absorber * c * atom (def=0=none) * c * beta heterogeniety parameter (def=0=none) * c * alpha3 alpha for external moderator (def=0=none) * c * gamma fraction of admixed moderator cross section in * c * external moderator cross section (def=0) * c * card8b tabulated (iwt=1 or -1 only) * c * wght read weight function as tab1 record. * c * end with a /. * c * card8c analytic flux parameters (iwt=4 or -4 only) * c * eb thermal break (ev) * c * tb thermal temperature (ev) * c * ec fission break (ev) * c * tc fission temperature (ev) * c * card8d input resonance flux (iwt=0 only) * c * ninwt tape unit for flux parameters (binary) * c * * c * card9 * c * mfd file to be processed * c * mtd section to be processed * c * mtname description of section to be processed * c * repeat for all reactions desired * c * mfd=0/ terminates this temperature/material. * c * card10 * c * matd next mat number to be processed * c * matd=0/ terminates groupr run. * c * * c *---options for input variables----------------------------------* c * * c * ign meaning * c * --- ------- * c * 1 arbitrary structure (read in) * c * 2 csewg 239-group structure * c * 3 lanl 30-group structure * c * 4 anl 27-group structure * c * 5 rrd 50-group structure * c * 6 gam-i 68-group structure * c * 7 gam-ii 100-group structure * c * 8 laser-thermos 35-group structure * c * 9 epri-cpm 69-group structure * c * 10 lanl 187-group structure * c * 11 lanl 70-group structure * c * 12 sand-ii 620-group structure * c * 13 lanl 80-group structure * c * 14 eurlib 100-group structure * c * 15 sand-iia 640-group structure * c * 16 vitamin-e 174-group structure * c * 17 vitamin-j 175-group structure * c * 18 xmas nea-lanl c * all new additional group structure with 7 significant c * decimal digits compatible with calendf c * 19 ecco 33-group structure c * 20 ecco 1968-group structure c * 21 tripoli 315-group structure c * 22 xmas lwpc 172-group structure c * 23 vit-j lwpc 175-group structure c * * c * igg meaning * c * --- ------- * c * 0 none * c * 1 arbitrary structure (read in) * c * 2 csewg 94-group structure * c * 3 lanl 12-group structure * c * 4 steiner 21-group gamma-ray structure * c * 5 straker 22-group structure * c * 6 lanl 48-group structure * c * 7 lanl 24-group structure * c * 8 vitamin-c 36-group structure * c * 9 vitamin-e 38-group structure * c * 10 vitamin-j 42-group structure * c * * c * iwt meaning * c * --- ------- * c * 1 read in smooth weight function * c * 2 constant * c * 3 1/e * c * 4 1/e + fission spectrum + thermal maxwellian * c * 5 epri-cell lwr * c * 6 (thermal) -- (1/e) -- (fission + fusion) * c * 7 same with t-dep thermal part * c * 8 thermal--1/e--fast reactor--fission + fusion * c * 9 claw weight function * c * 10 claw with t-dependent thermal part * c * 11 vitamin-e weight function (ornl-5505) * c * 12 vit-e with t-dep thermal part * c * -n compute flux with weight n * c * 0 read in resonance flux from ninwt * c * * c * mfd meaning * c * --- ------- * c * 3 cross section or yield vector * c * 5 fission chi by short-cut method * c * 6 neutron-neutron matrix (mf4/5) * c * 8 neutron-neutron matrix (mf6) * c * 12 photon prod. xsec (photon yields given, mf12) * c * 13 photon prod. xsec (photon xsecs given, mf13) * c * 16 neutron-gamma matrix (photon yields given) * c * 17 neutron-gamma matrix (photon xsecs given) * c * 18 neutron-gamma matrix (mf6) * c * note: if necessary, mfd=13 will automatically change * c * to 12 and mfd=16 will automatically change to 17 or 18.* c * 21 proton production matrix (mf6) * c * 22 deuteron production (mf6) * c * 23 triton production (mf6) * c * 24 he-3 production (mf6) * c * 25 alpha production (mf6) * c * 26 residual nucleus (a>4) production (mf6) * c * 31 proton production matrix (mf4) * c * 32 deuteron production (mf4) * c * 33 triton production (mf4) * c * 34 he-3 production (mf4) * c * 35 alpha production (mf4) * c * 36 residual nucleus (a>4) production (mf4) * c * note: if necessary, mfd=21-26 will * c * automatically change to 31-36. * c * 1zzzaaam nuclide production for zzzaaam * c * subsection from file 3 * c * 2zzzaaam nuclide production for zzzaaam * c * subsection from file 6 * c * 3zzzaaam nuclide production for zzzaaam * c * subsection from file 9 * c * 4zzzaaam nuclide production for zzzaaam * c * subsection from file 10 * c * * c * mtd meaning * c * --- ------- * c * -n process all mt numbers from the previous * c * entry to n inclusive * c * 221-250 reserved for thermal scattering * c * 258 average lethargy * c * 259 average inverse velocity (m/sec) * c * * c * automatic reaction processing options * c * ------------------------------------- * c * 3/ do all reactions in file3 on input pendf * c * 6/ do all matrix reactions in endf dictionary * c * 10/ do all isotope productions using mf8 * c * 13/ do all photon production cross sections * c * 16/ do all photon production matrices * c * 21/ do all proton production matrices * c * 22/ do all deuteron production matrices * c * 23/ do all triton production matrices * c * 24/ do all he-3 production matrices * c * 25/ do all alpha production matrices * c * 26/ do all a>4 production matrices * c * * c ****************************************************************** c GAMINR c c ****************************************************************** c * * c * compute multigroup photon cross sections * c * * c * produce multigroup photon interaction cross sections * c * and heating kerma factors using endf/b cross sections * c * and coherent and incoherent form factors. initial energy * c * quadrature techiques are identical to those used in groupr. * c * secondary energy-angle quadrature is performed using gaussian * c * integration. * c * * c *---input specifications (free format)---------------------------* c * * c * card1 * c * nendf unit for endf/b tape * c * npend unit for pendf tape * c * ngam1 unit for input ngam tape (default=0) * c * ngam2 unit for output ngam tape (default=0) * c * card2 * c * matb material to be processed * c * input materials in ascending order * c * igg gamma group structure option * c * iwt weight function option * c * lord legendre order * c * iprint print option (0/1=minimum/maximum) (default=1) * c * card3 * c * title run label up to 80 characters (delimited by *, * c * ended with /) * c * card4 (igg=1 only) * c * ngg number of groups * c * egg ngg+1 group bounds (ev) * c * card5 (iwt=1 only) * c * wght weight function as tab1 record * c * card6 * c * mfd file to be processed * c * mtd section to be processed * c * mtname description of section to be processed * c * repeat for all reactions desired * c * mfd=0/ terminates this material * c * mfd=-1/ is a flag to process all sections present * c * for this material (termination is automatic) * c * card7 * c * matd next mat number to be processed * c * terminate gaminr run with matd=0. * c * * c *---options for input variables----------------------------------* c * * c * igg meaning * c * --- ------- * c * 0 none * c * 1 arbitrary structure (read in) * c * 2 csewg 94-group structure * c * 3 lanl 12-group structure * c * 4 steiner 21-group gamma-ray structure * c * 5 straker 22-group structure * c * 6 lanl 48-group structure * c * 7 lanl 24-group structure * c * 8 vitamin-c 36-group structure * c * 9 vitamin-e 38-group structure * c * 10 vitamin-j 42-group structure * c * * c * iwt meaning * c * --- ------- * c * 1 read in * c * 2 constant * c * 3 1/e + rolloffs * c * * c ****************************************************************** c ERRORJ c c ****************************************************************** c * * c * modifed errorr module based on the errorj code * c * * c * From errorr: egtflx, egtsig, grist, lumpmt, lumpxs, merge, * c * rdsig, stand * c * From errorr with modifications: * c * errorr, covcal, covout, egngpn, epanel, grpav, * c * rdgout, sigc, uniong, colaps, gridd, resprp, * c * rescon, egnwtf, wgtwtf * c * From reconr with modifications: * c * ggrmat, ggmlbw, ssmlbw, ssslbw, ggunr1 * c * From errorj: resprx, Resprx_XXX, grpav4, alsigc, egtlgc, * c * musigc, matrixin, rdlgnd, fssigc, rdchi * c * * c ****************************************************************** c * * c * Further adapted for njoy99 by Skip Kahler (9/25+/2007) * c * - include ggrmat changes specified by Go Chiba in his "Bug- * c * fix for ERRORJ-2.3" memo, dated October 3, 2007 (his ggmlbw * c * correction has already been made and noted below). * c * - change "implicit double precision" to "implicit real*8" to * c * match historical njoy coding practice. * c * - change (or add) real number exponents from "e" to "d". * c * - make sure routines duplicated from other modules contain * c * the latest updates (through njoy99.257 currently). * c * - for consistency and future maintenance, replace assignments * c * for pi and physical constants with values defined or * c * calculated from main program common blocks. * c * - eliminate the "H" edit descriptor in format statements. * c * - changed "write(6,..." to "write(*,...". * c * - fix typo, "cwave" -> "cwaven" in ggmlbw. * c * - move "mprint=0" out of the if block in errorj so that this * c * variable is always properly initialized. * c * - add "mxlru2" to ggunr1 call list for proper amu dimension * c * declaration (g95 compiler). * c * - change b(1),alp(1) to b(*),alp(*) in rdlgnd dimension * c * declaration (g95 compiler). * c * - restructure a number of multiple condition "if" tests to * c * avoid run-time (undefined variables or array bounds under/ * c * overflow) errors from code compiled without optimization. * c * - change b(10) to b(*) in musigc and fssigc. * c * - delete "return" that cannot be reached in ggunr1 (absoft * c * compiler). * c * - miscellaneous text formatting changes to make the source * c * code flow more readable. * c * * c ****************************************************************** c * * c * produce cross section covariances from error files in endf/b * c * format * c * * c * first, the union energy grid of the users group structure * c * and the endf covariance energies is determined. the array * c * of coefficients for derived cross sections is also constructed.* c * then multigroup cross sections are computed on the union * c * grid (see grpav), or they are read from a multigroup cross * c * section library and then collapsed to the union grid. the * c * methods of groupr are used for cross section averaging. endf * c * covariances and the group cross sections are then combined * c * to get the basic covariance matrices (see covcal). finally, * c * the basic matrices are combined to get covariances for * c * derived reactions, the matrices are collapsed to the user-s * c * group structure, and the results are printed and/or written * c * onto an output gendf tape for later use (see covout). * c * * c *---input specifications (free format)---------------------------* c * * c * card 1 * c * nendf unit for endf/b tape * c * npend unit for pendf tape * c * ngout unit for input group xsec (gendf) tape * c * (if zero, group xsecs will be calculated) * c * (if iread eq 2 or if mfcov eq 31 (see card 7), * c * ngout cannot be zero) * c * (if mfcov eq 35 (see card 7), * c * ngout cannot be zero) * c * (default=0) * c * nout unit for output covariance tape (default=0) * c * nin unit for input covariance tape (default=0) * c * (nin and nout must be both coded or both binary) * c * nstan unit for ratio-to-standard tape (default=0) * c * card 2 * c * matd material to be processed * c * ign neutron group option * c * (ign definition same as groupr, except ign=19, * c * which means read in an energy grid, as in ign=1, * c * and supplement this with the endf covariance grid * c * within the range of the user-specified energies) * c * (default=1) * c * iwt weight function option (default=6) * c * iprint print option (0/1=minimum/maximum) (default=1) * c * irelco covariance form (0/1=absolute/relative) (default=1) * c * (if mfcov=34, irelco must be 1) * c * card 3 (omit if ngout.ne.0) * c * mprint print option for group averaging (0=min., 1=max.) * c * tempin temperature (default=300) * c * * c *---for endf/b version 4 (iverf=4) only--------------------------* c * * c * card 4 * c * nek number of derived xsec energy ranges * c * (if zero, all xsecs are independent) * c * card 5 (omit if nek=0) * c * ek nek+1 derived xsec energy bounds * c * card 6 (omit if nek=0) * c * akxy derived cross section coefficients, one row/line * c * * c *---for endf/b version 5 or 6 (iverf=5 or 6) only----------------* c * * c * card 7 * c * iread 0/1/2=program calculated mts/input mts and eks/ * c * calculated mts plus extra mat1-mt1 pairs from input * c * (default=0) * c * mfcov endf covariance file (31, 33, 34 or 35) to be * c * processed (default=33). * c * note--contribution to group cross section * c * covariances from resonance-parameter uncertainties * c * (mf=32) is included when mfcov=33 is specified. * c * (mf=-33) high speed Calc. for test case * c * (mf=333) high speed Calc. for test case(faster) * c * irespr processing option of resonance parameter covariance * c * (mf=32) (default=1) * c * 0 = area sensitivity method * c * 1 = 1% sensitivity method * c * legord legendre order calculating covariance (default=1) * c * (if mfcov is not 34, legord is ignored) * c * ifissp processing energy range number of fission energy * c * spectrum (default=-1) * c * (if mfcov is not 35, ifissp is ignored) * c * n>0 = energy range number * c * -1 = fast neutron reactor (average energy = 2 MeV) * c * * c * following cards only if iread eq 1 * c * card 8 * c * nmt no. mts to be processed * c * nek no. derived cross section energy ranges * c * (if zero, all xsecs are independent) * c * card 8a * c * mts nmt mts * c * card 8b (omit if nek=0) * c * ek nek+1 derived cross section energy bounds * c * card 9 (omit if nek=0) * c * akxy derived cross section coefficients, one row/line * c * * c * following card only if iread eq 2 * c * card 10 * c * mat1 cross-material reaction to be added to * c * mt1 covariance reaction list. * c * repeat for all mat1-mt1 pairs desired * c * terminate with mat1=0. * c * * c * following card only if nstan ne 0 * c * card 11 * c * matb standards reaction referenced * c * mtb in matd. * c * matc standards reaction to be * c * mtc used instead. * c * repeat for all standard reactions to be redefined. * c * terminate with matb=0. * c * note. if matb(1) and mtb(1) are negative, then matc(1) and * c * mtc(1) identify a third reaction, correlated with matd thru * c * the use of the same standard. covariances of all reactions * c * in matd (which reference the standard) with the reaction * c * matc(1)-mtc(1) will be produced. the standard reaction * c * must be identified on card 10 and repeated as the negative * c * entries on card 11. the group xsec tape ngout must include * c * all covariance reactions in matd, plus matc(1)-mtc(1). * c *----------------------------------------------------------------* c * * c * card 12a (for ign eq 1 or ign eq 19) * c * ngn number of groups * c * (if negative, group bounds is decending order) * c * card 12b * c * egn ngn+1 group bounds (ev) * c * card 13a tabulated (iwt=1 only) * c * wght weight function as a tab1 record * c * card 13b analytic flux parameters (iwt=4 only) * c * eb thermal break (ev) * c * tb thermal temperature (ev) * c * ec fission break (ev) * c * tc fission temperature (ev) * c * * c *---options for input variables----------------------------------* c * * c * ign meaning * c * --- ------- * c * 1 arbitrary structure (read in) * c * 2 csewg 239-group structure * c * 3 lanl 30-group structure * c * 4 anl 27-group structure * c * 5 rrd 50-group structure * c * 6 gam-i 68-group structure * c * 7 gam-ii 100-group structure * c * 8 laser-thermos 35-group structure * c * 9 epri-cpm 69-group structure * c * 10 lanl 187-group structure * c * 11 lanl 70-group structure * c * 12 sand-ii 620-group structure * c * 13 lanl 80-group structure * c * 14 eurlib 100-group structure * c * 15 sand-iia 640-group structure * c * 16 vitamin-e 174-group structure * c * 17 vitamin-j 175-group structure * c * 18 xmas 172-group structure * c * 19 read in, supplemented with endf covariance grid* c * * c * iwt meaning * c * --- ------- * c * 1 read in smooth weight function * c * 2 constant * c * 3 1/e * c * 4 1/e + fission spectrum + thermal maxwellian * c * 5 epri-cell lwr * c * 6 (thermal) -- (1/e) -- (fission + fusion) * c * 7 same with t-dep thermal part * c * 8 thermal--1/e--fast reactor--fission + fusion * c * 9 claw weight function * c * 10 claw with t-dependent thermal part * c * 11 vitamin-e weight function (ornl-5505) * c * 12 vit-e with t-dep thermal part * c * * c ****************************************************************** c COVR c c ****************************************************************** c * * c * plot covariance data from errorr or make a condensed library. * c * * c * in the plot option, covr plots a matrix of correlation * c * coefficients and an associated pair of standard deviation * c * vectors,i.e.,a covariance matrix. the correlation * c * matrix is plotted as a shaded contour plot and the vectors * c * are plotted as semi-log plots,one rotated by 90 degrees. * c * the log energy grids for the vector plots are identical * c * to the grids for the matrix plot. this version plots * c * through viewr. * c * * c * in the library option, covr produces a condensed bcd * c * covariance library in the boxer format. this format is * c * efficient for matrices of simple blocks. * c * * c *---input specifications (free format)---------------------------* c * * c * card 1 * c * nin input tape unit * c * nout output tape unit * c * (default=0=none) * c * nplot viewr output unit * c * (default=0=none) * c * * c * ---cards 2, 2a, and 3a for nout.ne.0 only (plot option) * c * * c * card 2 * c * icolor select color or monochrome style * c * 0=monochrome (uses cross hatching) * c * 1=color background and contours * c * (default=0) * c * card 2a * c * epmin lowest energy of interest (default=0.) * c * card 3a * c * irelco type of covariances present on nin * c * 0/1=absolute/relative covariances * c * (default=1) * c * ncase no. cases to be run (maximum=60) * c * (default=1) * c * noleg plot legend option * c * -1/0/1=legend for first subcase only/ * c * legend for all plots/no legends * c * (default=0) * c * nstart sequential figure number * c * 0/n=not needed/first figure is figure n. * c * (default=1) * c * ndiv no. of subdivisions of each of the * c * gray shades (default=1) * c * * c * ---cards 2b, 3b, and 3c for nout gt 0 (library option) only--* c * * c * card 2b * c * matype output library matrix option * c * 3/4=covariances/correlations * c * (default=3) * c * ncase no. cases to be run (maximum=60) * c * (default=1) * c * card 3b * c * hlibid up to 6 characters for identification * c * card 3c * c * hdescr up to 21 characters of descriptive * c * information * c * * c * ---cards 4 for both options--- * c * * c * card 4 * c * mat desired mat number * c * mt desired mt number * c * mat1 desired mat1 number * c * mt1 desired mt1 number * c * (default for mt, mat1 and mt1 are 0,0,0 * c * meaning process all mts for this mat * c * with mat1=mat) * c * (neg. values for mt, mat1, and mt1 mean * c * process all mts for this mat, except for * c * the mt-numbers -mt, -mat1, and -mt1. in * c * general, -n will strip both mt=1 and mt=n. * c * -4 will strip mt=1, mt=3, and mt=4, and * c * -62, for example, will strip mt=1, mt=62, * c * mt=63, ... up to and incl. mt=90.) * c * repeat card 4 ncase times * c * * c * note---if more than one material appears on the input tape, * c * the mat numbers must be in ascending order. * c * * c ****************************************************************** c MODER c c ****************************************************************** c * * c * change the mode of an endf/b tape. * c * * c * also works for pendf, gendf and covariance tapes. * c * moder can also be used to select materials from an endf-type * c * tape, or to merge several materials into a new tape. * c * * c *---input specifications (free format)---------------------------* c * * c * card 1 unit numbers * c * nin input unit * c * nout output unit * c * * c * a positive unit is coded (mode 3). * c * a negative unit is blocked binary (njoy mode). * c * * c * note: abs(nin) ge 1 and le 19 is a flag to select various * c * materials from one or more input tapes, with or * c * without mode conversion. the kind of data to be * c * processed is keyed to nin as follows: * c * nin=1, for endf or pendf input and output, * c * 2, for gendf input and output, * c * 3, for errorr-format input and output. * c * * c * cards 2 and 3 for abs (nin) ge 1 and le 19 only. * c * * c * card 2 * c * tpid tapeid for nout. 66 characters allowed * c * (delimited with *, ended with /) * c * card 3 * c * nin input unit * c * terminate moder by setting nin=0 * c * matd material on this tape to add to nout * c ****************************************************************** c DTFR c c ****************************************************************** c * * c * convert output of groupr to dtf format. * c * * c * processes neutron and gamma production cross sections and * c * matrices. the neutron tables can have reduced table length. * c * up-scatter is allowed. the absorption reaction is computed * c * from the total cross section and total scattering. any edits * c * can be produced which are either given in the endf/b file * c * or are linear combinations of endf/b cross sections. the * c * fission nu*sigf and chi are computed from the fission matrices * c * for all partial fission reactions. chi includes source * c * weighting. the pl tables for l.gt.0 contain the pl weighted * c * total in the total position and the pl transport cross section * c * in the absorption position. the gamma tables have gamma group * c * 1 in position 1, 2 in position 2, etc, with a table length * c * equal to the number of gamma groups. * c * * c * plots can be prepared in viewr format. * c * * c *---input specifications (free format)---------------------------* c * * c * card 1 units * c * nin input unit with data from groupr (binary). * c * nout output unit containing dtf tables (coded). * c * (default=0=none) * c * npend input unit with pendf tape for point plots. * c * (default=0=none) * c * nplot output plot info for plotr module * c * (default=0=none) * c * card 2 options * c * iprint print control (0 minimum, 1 maximum) * c * ifilm film control (0/1/2=no/yes with 1 plot per frame/ * c * yes with 4 plots per frame (default=0) * c * iedit edit control (0/1=in table/separate) (default=0) * c * * c * cards 3 through 5 only for iedit=0 * c * * c * card 3 neutron tables * c * nlmax number of neutron tables desired. * c * ng number of neutron groups * c * iptotl position of total cross section * c * ipingp position of in-group scattering cross section. * c * itabl neutron table length desired. * c * ned number of entries in edit table (default=0). * c * ntherm number of thermal groups (default=0). * c * card 3a only for ntherm ne 0 * c * card 3a thermal incoherent and coherent mts * c * mti mt for thermal incoherent data * c * mtc mt for thermal coherent data (default=0) * c * nlc no. coherent legendre orders (default=0) * c * card 4 edit names * c * six character hollerith names for edits for as many * c * cards as needed. there will be iptotl-3 names read. * c * each name is delimited with *. * c * card 5 edit specifications * c * ned triplets of numbers on as many cards as needed. * c * positions can appear more than once. * c * reaction types can appear more than once. * c * jpos position of edit quantity. * c * mt endf/b reaction number. * c * mult multiplicity to be used when adding this mt. * c * * c * card 6 for iedit=1 * c * * c * card 6 claw-format tables * c * nlmax number of neutron tables (def=5) * c * ng number of neutron groups (def=30) * c * (number of thermal groups is zero) * c * * c * card 7 gamma ray tables * c * nptabl number of gamma tables desired (default=0) * c * ngp number of gamma groups (default=0) * c * card 8 material description * c * one card for each table set desired. * c * empty card (/) terminates execution of dtfr. * c * hisnam 6-character isotope name * c * mat material number as in endf/b (default=0) * c * jsigz index number of sigma-zero desired (default=1) * c * dtemp temperature desired (default=300) * c * * c ****************************************************************** c CCCCR c c ****************************************************************** c * * c * produce cccc-iv files from njoy intermediate cross section * c * library * c * * c * working from a groupr output tape, this module produces * c * the following three standard interface files, * c * * c * isotxs brkoxs dlayxs, * c * * c * as specified by the committee for computer code coordination * c * (cccc), to facilitate the exchange of nuclear data for reactor* c * calculations (reference 1). * c * in a given run, all three files can be produced using the * c * same user-specified list of isotopes. the code will ignore * c * isotopes which are not present on the groupr tape (and in the * c * case of dlayxs, isotopes without delayed neutron data). * c * the isotxs coding allows for nsblk equal to one or ngroup.* c * in addition, files with higher order matrices can be produced * c * with a separate block for each l-order (ifopt=2) or with all * c * orders in one block (ifopt=1). this flexibility accommodates * c * large group structures. fission vectors or fission * c * matrices can be produced. * c * in brkoxs, the potential scattering cross section for all * c * energy groups is equal to the user-input value (xspo). * c * the elastic removal f-factor is supplied as the sixth reaction.* c * * c * 1. r.d.odell. standard interface files and procedures * c * for reactor physics codes, version iv, * c * lanl report la-6941-ms (sept.77) * c * * c * * c *---input specifications (free format)---------------------------* c * * c *-ccccr- * c * card 1 units * c * nin input unit for data from groupr * c * nisot output unit for isotxs (0 if isotxs not wanted) * c * nbrks output unit for brkoxs (0 if brkoxs not wanted) * c * ndlay output unit for dlayxs (0 if dlayxs not wanted) * c * card 2 identification * c * lprint print flag (0/1=not print/printed) * c * ivers file version number (default=0) * c * huse user identification (12 characters) * c * delimited by *, ended by /. * c * (default=blank) * c * card 3 * c * hsetid hollerith identification of set (12 characters) * c * delimited by *, ended by /. * c * (default=blank) * c * card 4 file control * c * ngroup number of neutron energy groups * c * nggrup number of gamma energy groups * c * niso number of isotopes desire * c * maxord maximum legendre order * c * ifopt matrix blocking option (1/2=blocking by * c * reaction/legendre order) * c * card 5 isotope parameters (one card per isotope) * c * (first four words are hollerith, up to six characters * c * each, delimited by *) * c * hisnm hollerith isotope label * c * habsid hollerith absolute isotope label * c * hident identifier of data source library (endf/b) * c * hmat isotope identification * c * imat numerical isotope identifier (endf/b mat number) * c * xspo average potential scattering cross sect. (brkoxs) * c * * c *-cisotx- (only if nisot.gt.0) * c * card 1 file control * c * nsblok subblocking option for scattering matrix * c * (1 or ngrup sub-blocks allowed) * c * maxup maximum number of upscatter groups (always zero) * c * maxdn maximum number of downscatter groups * c * ichix fission chi representation * c * -1 vector (using groupr flux) * c * 0 none * c * +1 vector (using input flux) * c * .gt.1 matrix * c * card 2 chi vector control (ichix=1 only) * c * spec ngroup flux values used to collapse the groupr * c * fission matrix into a chi vector * c * card 3 chi matrix control (ichix.gt.1 only) * c * spec ngroup values of spec(i)=k define the range of * c * groups i to be averaged to obtain spectrum k. * c * index k ranges from 1 to ichi. * c * the model flux is used to weight each group i. * c * card 4 isotope control (one card per isotope) * c * kbr isotope classification * c * amass gram atomic weight * c * efiss total thermal energy/fission * c * ecapt total thermal energy/capture * c * temp isotope temperature * c * sigpot average effective potential scattering * c * adens density of isotope in mixture * c * * c *-cbrkxs- (only if nbrks.gt.0) * c * card 1 (2i6) file data * c * nti number of temperatures desired * c * (-n means accept first n temperatures) * c * nzi number of sigpo values desire * c * (-n means accept first n dilution factors) * c * card 2 (not needed if nti.lt.0) * c * atem(nti) values of desired temperatures * c * card 3 (not needed if nzi.lt.0) * c * asig(nzi) values of desired sigpo * c * * c *-cdlayx-- no input required * c * * c ****************************************************************** c MATXSR c c ****************************************************************** c * * c * produce matxs interface file from njoy intermediate cross * c * section data from group or gaminr * c * * c * the matxs file uses a generalized, flexible format based on * c * the cccc interface conventions. working from groupr and/or * c * gaminr output tapes, this module can process neutron, * c * thermal, photon, and charged-particle data into a * c * single output file. this file can then be used by the * c * transx code to prepare data libraries for transport codes. * c * c * a matxs file specification may be found following the * c * input instructions. * c * * c *---input specifications (free format)---------------------------* c * * c * card 1 units * c * ngen1 input unit for data from groupr * c * ngen2 input unit for data from gaminr * c * nmatx output unit for matxs * c * ngen3 incident proton data from groupr (default=0) * c * ngen4 incident deuteron data from groupr (default=0) * c * ngen5 incident triton data from groupr (default=0) * c * ngen6 incident he3 data from groupr (default=0) * c * ngen7 incident alpha data from groupr (default=0) * c * ngen8 photonuclear data from groupr (default=0) * c * card 2 user identification * c * ivers file version number (default=0) * c * huse user id (up to 16 characters, delimited by *, * c * ended by /) (default=blank) * c * card 3 file control * c * npart number of particles for which group * c * structures are given * c * ntype number of data types in set * c * nholl number of cards to be read for hollerith * c * identification record. * c * nmat number of materials desired * c * card 4 set hollerith identification * c * hsetid hollerith identification of set * c * (each line can be up to 72 characters, * c * delimited with *, ended by /) * c * card 5 particle identifiers * c * hpart hollerith identifiers for particles * c * (up to 8 characters each) * c * card 6 energy groups * c * ngrp number of groups for each particle * c * card 7 data type identifiers * c * htype hollerith identifiers for data types * c * (up to 8 characters each) * c * card 8 input particle ids * c * jinp input particle id for each data type * c * card 9 output particle ids * c * joutp output particle id for each data type * c * card 10 material data (one card per material) * c * hmat hollerith material identifier * c * (up to 8 characters each) * c * matno integer material identifier * c * (endf/b mat number) * c * matgg mat number for photoatomic data * c * (default=100*(matno/100) as in endf-6) * c * * c ****************************************************************** c c c*********************************************************************** c proposed 09/09/77 - c (modified 09/80) - c (nomenclature changed 06/88) - c (modified for const sub-blocks 06/90) - c (ordering changed 10/90) - c c (bcd format changed 12/21/91) c - cf matxs - ce material cross section file - c - cn this file contains cross section - cn vectors and matrices for all - cn particles, materials, and reactions; - cn delayed neutron spectra by time group; - cn and decay heat and photon spectra. - c - cn formats given are for file exchange only - c - c*********************************************************************** c c c----------------------------------------------------------------------- cs file structure - cs - cs record type present if - cs ============================== =============== - cs file identification always - cs file control always - cs set hollerith identification always - cs file data always - cs - cs *************(repeat for all particles) - cs * group structures always - cs ************* - cs - cs *************(repeat for all materials) - cs * material control always - cs * - cs * ***********(repeat for all submaterials) - cs * * vector control n1db.gt.0 - cs * * - cs * * *********(repeat for all vector blocks) - cs * * * vector block n1db.gt.0 - cs * * ********* - cs * * - cs * * *********(repeat for all matrix blocks) - cs * * * matrix control n2d.gt.0 - cs * * * - cs * * * *******(repeat for all sub-blocks) - cs * * * * matrix sub-block n2d.gt.0 - cs * * * ******* - cs * * * - cs * * * constant sub-block jconst.gt.0 - cs * * * - cs ************* - c - c----------------------------------------------------------------------- c c c----------------------------------------------------------------------- cr file identification - c - cl hname,(huse(i),i=1,2),ivers - c - cw 1+3*mult - c - cb format(4h 0v ,a8,1h*,2a8,1h*,i6) c - cd hname hollerith file name - matxs - (a8) - cd huse hollerith user identifiation (a8) - cd ivers file version number - cd mult double precision parameter - cd 1- a8 word is single word - cd 2- a8 word is double precision word - c - c----------------------------------------------------------------------- c c c----------------------------------------------------------------------- cr file control - c - cl npart,ntype,nholl,nmat,maxw,length - c - cw 6 - c - cb format(6h 1d ,6i6) c - cd npart number of particles for which group - cd structures are given - cd ntype number of data types present in set - cd nholl number of words in set hollerith - cd identification record - cd nmat number of materials on file - cd maxw maximum record size for sub-blocking - cd length length of file - c - c----------------------------------------------------------------------- c c c----------------------------------------------------------------------- cr set hollerith identification - c - cl (hsetid(i),i=1,nholl) - c - cw nholl*mult - c - cb format(4h 2d /(9a8)) c - cd hsetid hollerith identification of set (a8) - cd (to be edited out 72 characters per line) - c - c----------------------------------------------------------------------- c c c----------------------------------------------------------------------- cr file data - c - cl (hprt(j),j=1,npart),(htype(k),k=1,ntype),(hmatn(i),i=1,nmat), - cl 1(ngrp(j),j=1,npart),(jinp(k),k=1,ntype,(joutp(k),k=1,ntype), - cl 2(nsubm(i)i=1,nmat),(locm(i),i=1,nmat) - c - cw (npart+ntype+nmat)*mult+2*ntype+npart+2*nmat - c - cb format(4h 3d ,4x,8a8/(9a8)) hprt,htype,hmatn cb format(12i6) ngrp,jinp,joutp,nsubm,locm - c - cd hprt(j) hollerith identification for particle j - cd n neutron - cd g gamma - cd p proton - cd d deuteron - cd t triton - cd h he-3 nucleus - cd a alpha (he-4 nucleus) - cd b beta - cd r residual or recoil - cd (heavier than alpha) - cd htype(k) hollerith identification for data type k - cd nscat neutron scattering - cd ng neutron induced gamma production - cd gscat gamma scattering (atomic) - cd gg gamma scattering (photonuclear) - cd pn proton induced neutron production - cd . . - cd . . - cd . . - cd dkn delayed neutron data - cd dkhg decay heat and gamma data - cd dkb decay beta data - cd hmatn(i) hollerith identification for material i - cd ngrp(j) number of energy groups for particle j - cd jinp(k) type of incident particle associated with - cd data type k. for dk data types, jinp is 0. - cd joutp(k) type of outgoing particle associated with - cd data type k - cd nsubm(i) number of submaterials for material i - cd locm(i) location of material i - c - c----------------------------------------------------------------------- c c c----------------------------------------------------------------------- cr group structure - c - cl (gpb(i),i=1,ngr),emin - c - cc ngr=ngrp(j) - c - cw ngrp(j)+1 - c - cb format(4h 4d ,8x,1p,5e12.5/(6e12.5)) c - cd gpb(i) maximum energy bound for group i for particle j - cd emin minimum energy bound for particle j - c - c----------------------------------------------------------------------- c c c----------------------------------------------------------------------- cr material control - c - cl hmat,amass,(temp(i),sigz(i),itype(i),n1d(i),n2d(i), - cl 1locs(i),i=1,nsubm) - c - cw mult+1+6*nsubm - c - cb format(4h 5d ,a8,1p,2e12.5/(2e12.5,5i6)) c - cd hmat hollerith material identifier - cd amass atomic weight ratio - cd temp ambient temperature or other parameters for - cd submaterial i - cd sigz dilution factor or other parameters for - cd submaterial i - cd itype data type for submaterial i - cd n1d number of vectors for submaterial i - cd n2d number of matrix blocks for submaterial i - cd locs location of submaterial i - c - c----------------------------------------------------------------------- c c c----------------------------------------------------------------------- cr vector control - c - cl (hvps(i),i=1,n1d),(nfg(i),i=1,n1d),(nlg(i),i=1,n1d) - c - cw (mult+2)*n1d - c - cb format(4h 6d ,4x,8a8/(9a8)) hvps cb format(12i6) iblk,nfg,nlg - c - cd hvps(i) hollerith identifier of vector - cd nelas neutron elastic scattering - cd n2n (n,2n) - cd nnf second chance fission - cd gabs gamma absorption - cd p2n protons in, 2 neutrons out - cd . . - cd . . - cd . . - cd nfg(i) number of first group in band for vector i - cd nlg(i) number of last group in band for vector i - c - c----------------------------------------------------------------------- c c c----------------------------------------------------------------------- cr vector block - c - cl (vps(i),i=1,kmax) - c - cc kmax=sum over group band for each vector in block j - c - cw kmax - c - cb format(4h 7d ,8x,1p,5e12.5/(6e12.5)) c - cd vps(i) data for group bands for vectors in block j. - cd block size is determined by taking all the group - cd bands that have a total length less than or equal - cd to maxw. - c - c----------------------------------------------------------------------- c c c----------------------------------------------------------------------- cr scattering matrix control - c - cl hmtx,lord,jconst, cl 1(jband(l),l=1,noutg(k)),(ijj(l),l=1,noutg(k)) - c - cw mult+2+2*noutg(k) - c - cb format(4h 8d ,4x,a8/(12i6)) hmtx,lord,jconst, cb jband,ijj - c - cd hmtx hollerith identification of block - cd lord number of orders present - cd jconst number of groups with constant spectrum - cd jband(l) bandwidth for group l - cd ijj(l) lowest group in band for group l - c - c----------------------------------------------------------------------- c c c----------------------------------------------------------------------- cr scattering sub-block - c - cl (scat(k),k=1,kmax) - c - cc kmax=lord times the sum over all jband in the group range of - cc this sub-block - c - cb format(4h 9d ,8x,1p,5e12.5/(6e12.5)) c - cw kmax - c - cd scat(k) matrix data given as bands of elements for initial - cd groups that lead to each final group. the order - cd of the elements is as follows: band for p0 of - cd group i, band for p1 of group i, ... , band for p0 - cd of group i+1, band for p1 of group i+1, etc. the - cd groups in each band are given in descending order. - cd the size of each sub-block is determined by the - cd total length of a group of bands that is less than - cd or equal to maxw. - cd - cd if jconst.gt.0, the contributions from the jconst - cd low-energy groups are given separately. - c - c----------------------------------------------------------------------- c - c - c----------------------------------------------------------------------- cr constant sub-block - c - cl (spec(l),l=1,noutg(k)),(prod(l),l=l1,ning(k)) - c - cc l1=ning(k)-jconst+1 - c - cw noutg(k)+jconst - c - cb format(4h10d ,8x,1p,5e12.5/(6e12.5)) c - cd spec normalized spectrum of final particles for initial - cd particles in groups l1 to ning(k) - cd prod production cross section (e.g., nu*sigf) for - cd initial groups l1 through ning(k) - cd - cd this option is normally used for the energy-independent - cd neutron and photon spectra from fission and radiative - cd capture usually seen at low energies. - c - c----------------------------------------------------------------------- c c ****************************************************************** c RESXSR c c ****************************************************************** c * * c * construct an resxs resonance cross section * c * file from njoy pendf cross sections. * c * * c * user input * c * * c * card 1 units * c * nout output unit * c * * c * card 2 control * c * nmat number of materials * c * maxt max. number of temperatures * c * nholl number of lines of descriptive comments * c * efirst lower energy limit (ev) * c * elast upper energy limit * c * eps thinning tolerance * c * * c * card 3 user id * c * huse hollerith user identification (up to 16 chars) * c * ivers file version number * c * * c * card 4 descriptive data (repeat nholl times) * c * holl line of hollerith data (72 chars max) * c * * c * card 5 material specifications (repeat nmat times) * c * hmat hollerith name for material (up to 8 chars) * c * mat endf mat number for material * c * unit njoy unit number for pendf data * c * * c * the resxs format specification follows: * c * * c*********************************************************************** c proposed 09/24/90 - c - cf resxs - ce resonance cross section file - c - cn this file contains pointwise cross - cn sections for the epithermal resonance - cn range to be used for hyper-fine flux - cn calculations. elastic, fission, and - cn capture cross sections are given vs - cn temperature. linear interpolation is - cn assumed. - c - cn formats given are for file exchange only - c - c*********************************************************************** c c c----------------------------------------------------------------------- cs file structure - cs - cs record type present if - cs ============================== =============== - cs file identification always - cs file control always - cs set hollerith identification always - cs file data always - cs - cs *************(repeat for all materials) - cs * material control always - cs * - cs * ***********(repeat for all cross section blocks) - cs * * cross section block always - cs * *********** - cs ************* - c - c----------------------------------------------------------------------- c c c----------------------------------------------------------------------- cr file identification - c - cl hname,(huse(i),i=1,2),ivers - c - cw 1+3*mult - c - cb format(4h ov ,a8,1h*,2a8,1h*,i6) - c - cd hname hollerith file name - resxs - (a8) - cd huse hollerith user identifiation (a8) - cd ivers file version number - cd mult double precision parameter