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Member mmmmebfM or caseebxM /10*ng+ LGV( g)
/
The (n,2n) matrix data for the mixture or the homogenized cell. The data
organization is the same as for the standard member mmmmebfp or caseebxp
while null values are filled in the position of
Σ υ through
Σ a
.
ng
∑
g=
1
Member mmmmebfY or caseebxY /3*ng*IFM/
The delayed neutron data for the mixture or the homogenized cell used for the one
point kinetics parameter calculation in CITATION (cf. Sect.2.8). IFM is number of
delayed neutron families: usually IFM=6, and IFM=15 if D 2 O is concerned.
(BVFSIG(j,g),j=1,IFM),g=1,ng)
The parameter for delayed neutron fraction by family j
BVFSIG(
j n
j , g)
= ∑ β nνσ
f , g
n
N
n
(n: nuclide)
( χ d
(j,g),j=1,IFM),g=1,ng)
Delayed neutron spectrum by family j
(BVLSIG(j,g),j=1,IFM),g=1,ng)
The parameter for decay constant by family j
j
β nνσ
f , g N
BVLSIG ( j,
g)
= ∑
(n: nuclide)
n
n λ
n
j
n
3.1.6 Coarse Group Macroscopic Cross-section File [MACRO]
The macroscopic cross-sections by material and by X-Region collapsed by calculated or
asymptotic spectrum are stored in the coarse group macroscopic cross-sections file (MACRO) in the
coarse (few) group structure.
Member name
Contents
**********************************************************************************
CONTe000 Energy group structure for the energy range specified by e-tag
mmmmebfp Cross-sections of material mmmm
mmmmebfN (n,2n) cross-sections of material mmmm
mmmmebfZ Delayed neutron data of material mmmm
caseebxp Cross-sections of X-Region x
caseebxN (n,2n) cross-sections of X-Region x
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