Input Instructions for GROUPR
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* *
* card1 *
* nendf unit for endf/b tape *
* npend unit for pendf tape *
* ngout1 unit for input gout tape (default=0) *
* ngout2 unit for output gout tape (default=0) *
* card2 *
* matb material to be processed *
* matb lt 0 is a flag to add mts to and/or replace *
* individual mts on ngout1. *
* ign neutron group structure option *
* igg gamma group structure option *
* iwt weight function option *
* lord legendre order *
* ntemp number of temperatures *
* nsigz number of sigma zeroes *
* iprint long print option (0/1=minimum/maximum) *
* (default=1) *
* card3 *
* title run label (up to 80 characters delimited by *, *
* ended with /) (default=blank) *
* card4 *
* temp temperatures in kelvin *
* card5 *
* sigz sigma zero values (including infinity) *
* *
* if ign=1, read neutron group structure (6a and 6b) *
* card6a *
* ngn number of groups *
* card6b *
* egn ngn+1 group breaks (ev) *
* *
* if igg=1, read gamma group structure (7a and 7b) *
* card7a *
* ngg number of groups *
* card7b *
* egg ngg+1 group breaks (ev) *
* *
* weight function options (8a,8b,8c,8d) *
* card8a flux calculator parameters (iwt.lt.0 only) *
* ehi break between computed flux and bondarenko flux *
* (must be in resolved range) *
* sigpot estimate of potential scattering cross section *
* nflmax maximum number of computed flux points *
* ninwt tape unit for new flux parameters (default=0) *
* jsigz index of reference sigma zero in sigz array *
* (default=0) *
* alpha2 alpha for admixed moderator (def=o=none) *
* sam admixed moderator xsec in barns per absorber *
* atom (def=0=none) *
* beta heterogeniety parameter (def=0=none) *
* alpha3 alpha for external moderator (def=0=none) *
* gamma fraction of admixed moderator cross section in *
* external moderator cross section (def=0) *
* card8b tabulated (iwt=1 or -1 only) *
* wght read weight function as tab1 record. *
* end with a /. *
* card8c analytic flux parameters (iwt=4 or -4 only) *
* eb thermal break (ev) *
* tb thermal temperature (ev) *
* ec fission break (ev) *
* tc fission temperature (ev) *
* card8d input resonance flux (iwt=0 only) *
* ninwt tape unit for flux parameters *
* *
* card9 *
* mfd file to be processed *
* mtd section to be processed *
* mtname description of section to be processed *
* repeat for all reactions desired *
* mfd=0/ terminates this temperature/material. *
* card10 *
* matd next mat number to be processed *
* matd=0/ terminates groupr run. *
* *
*---options for input variables----------------------------------*
* *
* ign meaning *
* --- ------- *
* 1 arbitrary structure (read in) *
* 2 csewg 239-group structure *
* 3 lanl 30-group structure *
* 4 anl 27-group structure *
* 5 rrd 50-group structure *
* 6 gam-i 68-group structure *
* 7 gam-ii 100-group structure *
* 8 laser-thermos 35-group structure *
* 9 epri-cpm 69-group structure *
* 10 lanl 187-group structure *
* 11 lanl 70-group structure *
* 12 sand-ii 620-group structure *
* 13 lanl 80-group structure *
* 14 eurlib 100-group structure *
* 15 sand-iia 640-group structure *
* 16 vitamin-e 174-group structure *
* 17 vitamin-j 175-group structure *
* *
* igg meaning *
* --- ------- *
* 0 none *
* 1 arbitrary structure (read in) *
* 2 csewg 94-group structure *
* 3 lanl 12-group structure *
* 4 steiner 21-group gamma-ray structure *
* 5 straker 22-group structure *
* 6 lanl 48-group structure *
* 7 lanl 24-group structure *
* 8 vitamin-c 36-group structure *
* 9 vitamin-e 38-group structure *
* 10 vitamin-j 42-group structure *
* *
* iwt meaning *
* --- ------- *
* 1 read in smooth weight function *
* 2 constant *
* 3 1/e *
* 4 1/e + fission spectrum + thermal maxwellian *
* 5 epri-cell lwr *
* 6 (thermal) -- (1/e) -- (fission + fusion) *
* 7 same with t-dep thermal part *
* 8 thermal--1/e--fast reactor--fission + fusion *
* 9 claw weight function *
* 10 claw with t-dependent thermal part *
* 11 vitamin-e weight function (ornl-5505) *
* 12 vit-e with t-dep thermal part *
* -n compute flux with weight n *
* 0 read in resonance flux from ninwt *
* *
* mfd meaning *
* --- ------- *
* 3 cross section or yield vector *
* 5 fission chi by short-cut method *
* 6 neutron-neutron matrix (mf4/5) *
* 8 neutron-neutron matrix (mf6) *
* 12 photon prod. xsec (photon yields given, mf12) *
* 13 photon prod. xsec (photon xsecs given, mf13) *
* 16 neutron-gamma matrix (photon yields given) *
* 17 neutron-gamma matrix (photon xsecs given) *
* 18 neutron-gamma matrix (mf6) *
* note: if necessary, mfd=13 will automatically change *
* to 12 and mfd=16 will automatically change to 17 or 18.*
* 21 proton production matrix (mf6) *
* 22 deuteron production (mf6) *
* 23 triton production (mf6) *
* 24 he-3 production (mf6) *
* 25 alpha production (mf6) *
* 26 residual nucleus (a>4) production (mf6) *
* 31 proton production matrix (mf4) *
* 32 deuteron production (mf4) *
* 33 triton production (mf4) *
* 34 he-3 production (mf4) *
* 35 alpha production (mf4) *
* 36 residual nucleus (a>4) production (mf4) *
* note: if necessary, mfd=21-26 will *
* automatically change to 31-36. *
* 90+n radioactive nuclide production from nth *
* subsection for mtd in file 9. *
* 100+n radioactive nuclide production from nth *
* subsection for mtd in file 10. *
* *
* mtd meaning *
* --- ------- *
* -n process all mt numbers from the previous *
* entry to n inclusive *
* 221-250 reserved for thermal scattering *
* 258 average lethargy *
* 259 average inverse velocity (m/sec) *
* *
* automatic reaction processing options *
* ------------------------------------- *
* 3/ do all reactions in file3 on input pendf *
* 6/ do all matrix reactions in endf dictionary *
* 10/ do all radioactive isotope productions *
* 13/ do all photon production cross sections *
* 16/ do all photon production matrices *
* 21/ do all proton production matrices *
* 22/ do all deuteron production matrices *
* 23/ do all triton production matrices *
* 24/ do all he-3 production matrices *
* 25/ do all alpha production matrices *
* 26/ do all a>4 production matrices *
* *
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