TENDL-2023 Nuclear data library
Neutron sub-library for C (Z=6) and A=11: Tabular residual cross sections
Tabulated residual cross sections
Reaction #
C
(n,x)
6
Li
C
(n,x)
7
Li
C
(n,x)
8
Li
C
(n,x)
9
Li
C
(n,x)
7
Be
C
(n,x)
8
Be
Reaction #
C
(n,x)
9
Be
C
(n,x)
10
Be
C
(n,x)
8
B
C
(n,x)
9
B
C
(n,x)
10
B
C
(n,x)
11
B
Reaction #
C
(n,x)
9
C
C
(n,x)
10
C
C
(n,x)
11
C
C
(n,x)
12
C