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* *
* card 1 *
* ngendf unit for input gendf tape *
* nout unit for output wims tape *
* *
* card 2 *
* iprint print option *
* 0=minimum (default) *
* 1=regular *
* 2=1+intermediate results *
* iverw wims version *
* 4=wims-d (default) *
* 5=wims-e *
* igroup group option *
* 0=69 groups (default) *
* 9=user's choice *
* *
* card 2a (igroup.eq.9 only) *
* ngnd number of groups *
* nfg number of fast groups *
* nrg number of resonance groups *
* igref reference group (default is last fast group) *
* *
* card 3 *
* mat endf mat number of the material to be processed *
* nfid not used *
* rdfid identification of material for the wims library *
* iburn burnup data option *
* -1=suppress printout of burnup data *
* 0=no burnup data is provided (default) *
* 1=burnup data is provided in cards 5 and 6 *
* *
* card 4 *
* ntemp no. of temperatures to process for this material *
* in the thermal energy range
* (0=all found on input tape) *
* nsigz no. of sigma zeroes to process for this material *
* (0=all found on input tape) *
* sgref reference sigma zero *
* (.ge. 1.e10 to select all cross sect. at inf.dil.*
* but fully shielded elastic x-sect, *
* .lt. 1.e10 to select all x-sect at inf.dil. *
* =sig0 from the list on groupr input to *
* select all x-sect. at that sig0) *
* ires resonance absorber indicator *
* 0=no resonance tables *
* >0=ires temperatures processed *
* sigp potential cross section from endf/b. *
* (if zero, replace by the elastic cross section) *
* mti thermal inelastic mt (default=0=none) *
* mtc thermal elastic mt (default=0=none) *
* ip1opt include p1 matrices *
* 0=yes *
* 1=no, correct p0 ingroups (default) *
* inorf resonance fission (if found) *
* 0=include resonance fission (default) *
* 1=do not include *
* isof fission spectrum *
* 0=do not include fission spectrum (default) *
* 1=include fission spectrum *
* ifprod fission product flag *
* 0=not a fission product (default) *
* 1=fission product, no resonance tables *
* 2=fission product, resonance tables *
* jp1 transport correction neutron current spectrum flag *
* 0=use p1-flux for transport correction (default) *
* >0=read in jp1 values of the neutron current *
* spectrum from input *
* *
* following two cards are for iburn gt 0 only *
* card 5 *
* ntis no. of time-dependent isotopes *
* efiss energy released per fission *
* *
* card 6 (repeat this card ntis times) *
* identa ident of fission product isotope *
* yield fission yield of identa from burnup of mat *
* *
* card 7 *
* lambda resonance-group goldstein lambdas (13 for *
* default 69-group structure, nrg otherwise). *
* *
* card 8 (only when jp1>0)
* p1flx current spectrum (jp1 entries read, the rest are *
* set with the default p1-flux calculated by njoy). *
* *
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