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Member caseBNUP Material-wise burn-up information
1 NOWSTP Number of burn-up steps including the initial step.
If the burn-up calculation is completed, NOWSTP=1+IBC1 (Sect.2.11).
2 NTNUC Total number of depleting nuclides
3 NZON Number of depleting materials in a cell
4 IDUM4 = 0 not used
5 IDUM5 = 0 not used
6 IDUM6 = 0 not used
7 IDUM7 = 0 not used
8 IDUM8 = 0 not used
9 IDUM9 = 0 not used
10 IDUM10 = 0 not used
11 CASE Case name (A4)
12 STDNUC Nuclide ID (A4) used for the measure of depletion fraction (cf. Block-4 of
Sect.2.11, ‘XU05’ is defaulted when IBC2>0 (cf. Block-1 of Sect.2.11)
(TITLE(i),i=1,18)
Comment of 72 characters (18A4)
(MTNM(m),m=1,NZON)
Former half of depleting material names specified in Sect.2.9. NZON is number of
depleting materials (by M-Region)
(MTYP(m),m=1,NZON)
Type of depleting materials
= 1 Fissionable material (e.g. UO 2 )
= 2 Non-fissionable material (e.g. Gd 2 O 3 )
(VOLDPZ(m),m=1,NZON)
Volumes of depleting materials (cm 3 )
(NUCLID(i),i=1,NTNUC)
Index of nuclide name by four characters. The first character is set to ‘X’, the
succeeding three characters denote zzm (e.g. XU05, XPU9).
(DAYS(j),j=1,NOWSTP)
Accumulated burn-up days (unit day) by step j
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