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Initial inventory in the restart calculation is given by
∑
m
{HMINV(1,m)*VOLDPZ(m)}
((RLHT(j,m),j=1,NOWSTP), m=1,NZON)
Heat generation (Joule/fission) by step by depleting material
((YDXE(j,m),j=1,NOWSTP),m=1,NZON)
Fission yield of Xe-135 by step by depleting material
((YDIO(j,m),j=1,NOWSTP), m=1,NZON)
Fission yield of I-135 by step by depleting material
((YDSM(j,m),j=1,NOWSTP),m=1,NZON)
Fission yield of Sm-149 by step by depleting material
((YDPM(j,m),j=1,NOWSTP),m=1,NZON)
Fission yield of Pm-149 by step by depleting material
((DENSTY(j,i,m),j=1,NOWSTP),i=1,NTNUC),m=1,NZON
Atomic number density (10 24 n/cm 3 ) by step by nuclide by depleting material
(((SIGXE(g,j,m),g=1,ng),j=1,NOWSTP),m=1,NZON)
Few group microscopic capture cross-sections of Xe-135 by group g by step j by
depleting material m. If no collapsing is done, fine group cross-sections are given.
(((SIGIO(g,j,m),g=1,ng),j=1,NOWSTP),m=1,NZON)
Few group microscopic capture cross-sections of I-135 by group by step by
depleting material.
(((SIGSM(g,j,m),g=1,ng),j=1,NOWSTP),m=1,NZON)
Few group microscopic capture cross-sections of Sm-149 by group by step by
depleting material. If no collapsing is done, fine group cross-sections are given.
(((SIGPM(g,j,m),g=1,ng),j=1,NOWSTP),m=1,NZON)
Few group microscopic capture cross-sections of Pm-149 by group by step by
depleting material. If no collapsing is done, fine group cross-sections are given.
Member
caseDNxT Homogenized burn-up information
Contents of the member are same as those of the member caseBNUP, however, all
data in this member is homogenized in the x-th X-Region.
1 NOWSTP Number of burn-up steps including the initial step.
If the burn-up calculation is completed, NOWSTP=1+IBC1 (Sect.2.11).
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