JAEA-Data/Code 2007-004 - Welcome to Research Group for ...

The step number j=1,2,3,4,…,10,11,12,… corresponds to the burn-up tag of the
member in PDS b= 0,1,2,3,…,9,A,B…. , respectively.
(EXPST(j),j=1,NOWSTP)
Accumulated burn-up (MWd/t) of whole cell
(U235F(j),j=1,NOWSTP)
Depletion fraction (%) of nuclide STDNUC (cf. Block-4 of Sect.2.11)
U-235 is defaulted when IBC2>0 (cf. Block-1 of Sect.2.11)
U235F(j) ≤ 100 (negative value may be appeared for the nuclide increasing with
burn-up, e.g. blanket fuel)
(AKEFF(j),j=1,NOWSTP)
Effective multiplication factor by step. AKEFF(NOWSTP)=0.0, because flux
(eigenvalue) calculation is not done at the last step.
(AKINF(j),j=1,NOWSTP)
Infinite multiplication factor by step. AKINF(NOWSTP)=0.0
(INSCR(j),j=1,NOWSTP)
Instantaneous conversion ratio by step. INSCR(NOWSTP)=0.0
(INTCR(j),j=1,NOWSTP)
Integrated conversion ratio by step. INTCR(NOWSTP)=0.0
(POWERL(j),j=1,NOWSTP)
Thermal power per unit length of cell (MWt/cm) by step.
POWERL (NOWSTP)=0.0
In the constant flux calculation, POWER(j ≤ 1) are calculated by code.
(FLXNRM(j),j=1,NOWSTP)
Normalizing factor of neutron flux by step. FLXNRM(NOWSTP)=0.0.
Even in the restart calculation under constant flux level, the flux level is set to
FLXNRM(1) throughout the exposure.
((POWRZN(j,m),j=1,NOWSTP),m=1,NZON)
Power density (MW/cm 3 ) by step j by depleting material m
((EXPSZN(j,m),j=1,NPWSTP),m=1,NZON)
Burn-up (MWd/t) by step by depleting material
In the case of MTYPX(m)=2, time integrated absorption rate (n/cm 3 ) is given.
((HMINV(j,m),j=1,NOWSTP),m=1,NZON)
Heavy metal inventory (ton/cm 3 ) by step by depleting material
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