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

(E(g),g=1,NGF+1)
structure.
Boundary energies in eV.
Member FISSYILD /NGF/
The member keeps the fission neutron yield of U-235 to provide the fixed source in
calculating the fast neutron spectrum for non-fissile material.
(X(g),g=1,NGF)
Fission neutron yields in the g-th group normalized as
∑
g
Χ( g)
= 1.0
Member Czzm0000 /42/
The member keeps the control information of the nuclide in a vector.
ICAP = 0 No capture
= 1 Capture cross-sections stored
IFISS = 0 No fission
= 1 Fission cross-sections stored
IRP = 0 No resonance parameter
= 1 Resonance parameters used in the IR approximation.
LTOT Vector length of the member Mzzm0000 described below.
(LTH(i),i=1,4) Partial vector length which contains the i-th scattering matrix, where i=1 for
inelastic, i=2 for (n,2n), i=3 for elastic P 0 and i=4 for elastic P 1 .
(LA(i),i=1,4) The lowest group number of the energy range where the i-th scattering occurs.
(LD(i),i=1,4) Number of energy groups to which the slowing-down occurs in the i-th scattering.
IFS
Index for shielding factor tables
= 0 No shielding factor
= 1 Shielding factors for any reaction are tabulated
IFTR, IFC, IFF, IFE, and IFER
Indices for self-shielding factor tables for partial reaction of transport, capture,
fission, elastic and elastic slowing-down, respectively.
NGMIN and NGMAX
The highest and lowest group number for self-shielding factor tabulation.
151