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material (denominator of conversion ratio calculation: Eq.(2.11-3))
U03A 1 +1.0 (+N U-233 σ U-233 a Φ)
U05A 0 +0.5 (+0.5× σ U-235 a Φ)
PA3A 1 -1.0 (-N Pa-233 σ Pa-233 a Φ)
PU1D 1 +0.2 (+0.2× λ Pu-241 N Pu-241 )
However, the tabulated values of fissile absorption cross-sections along burn-up
are defined as:
fissile
Σ a = N U-233 σ U-233 a + 0.5*σ U-235 a Φ - N Pa-233 Pa-233
σ a ,
where no contribution of decay is included.
Repeat Block-7-2 NFIS times.
Block-7-3 Required if IBC5=5 /A4, 1, 1/
1 NAMFRT Number of nuclides to contribute to production of fissile nuclides by 4 characters.
The first 3 characters are for nuclide name and the fourth character for reaction
type (Fission/ Capture/ Absorption/ N2N/ Decay). Enter as; ‘U08C’, ‘PU0C’,
‘PU0N’.
Note:
Nuclide name and reaction type should be appropriately selected by taking into
account the burn-up chain model used in the calculation. (cf. Sect.3.3)
Even if ‘D’ is specified, contribution of decay is not reflected in the tabulation
of capture cross-section of fertile material (
The fertile capture cross-section (
fertile
Σ c,g
fertile
Σ c,g
) to be stored in MACRO file.
) is used by COREBN to calculate
fissile
Σ a,g
conversion ratio together with fissile absorption cross-section ( ).
2 IFRTFLG
= 0 Do not multiply atomic number density of this nuclide (microscopic
cross- sections are used)
= 1 Multiply atomic number density of this nuclide (macroscopic
cross-sections are used)
3 FRTFACT The factor to indicate sign or branching ratio. (same as FISFACT in Block 7-2)
Repeat Block-7-3 NFER times.
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