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

Member mmmmebfp or caseebxp /10*ng+∑ LGV( g)
/
The member keeps a complete set of group cross-sections in a one-dimensional
array. We shall show below a partial vector corresponding to a energy group g.
DO g=1,ng (ng: in CONTe000)
1 LSS(g) Position of the self-scatter on the scattering vector
2 LGV(g) Length of the scattering vector
3 Σ (g) Constant related to neutron velocity ( υ ) for the calculation of point kinetics
υ
parameters
g
ng
g=
1
Σ
υ,
g
≡
1
E
υ ( m / sec) =
g
g
=
1
( E ( eV ) + E ( eV ))
g
g+
1
2 × 1.60219E
−19
1
m ( kg)
Σ
n
υ
/
,
2
1
= 13831.68 ×
Σ
υ
4 Σ f (g) Fission cross-section
5 ν Σ f (g) Production cross-section
6 Σ t
(g) Total (p=2) or transport (p=4) cross-section
7 χ (g) Fission neutron yield
8 D1(g) Diffusion coefficient 1
9 D2(g) Diffusion coefficient 2
10 Σ a
(g) Absorption cross-section followed by the scattering vector
1 Σ g→g1 where g1=g-LSS(g)+1
2 Σ g→g1+
1
3 Σ g→g1+
2
LSS(g)
LGV(g)
-
-
Σ g→ g
-
-
Σ g→g 2
where g2=g+LGV(g)-LSS(g)
END DO (The above organization is repeated ‘ng’ times in the whole vector.)
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