TENDL-2023 Nuclear data library

Neutron sub-library for C (Z=6) and A=10: Tabular production and total cross sections

Production and total cross sections
Reaction # C(n,all) C(n,x)a C(n,x)d C(n,el) C(n,x)g C(n,x)he3 C(n,non) C(n,x)n C(n,x)p C(n,reac) C(other) C(n,x)t
Reaction #
Partial cross sections
Reaction # 10C(n,g) 10C(n,a) 10C(n,He3) 10C(n,t)
Reaction # 10C(n,d) 10C(n,d+He3) 10C(n,2d) 10C(n,p)
Reaction # 10C(n,p+a) 10C(n,p+He3) 10C(n,p+t) 10C(n,p+d)
Reaction # 10C(n,p+2d) 10C(n,2p) 10C(n,2p+t) 10C(n,2p+d)
Reaction # 10C(n,3p) 10C(n,n) 10C(n,n+He3) 10C(n,n+d)
Reaction # 10C(n,n+p) 10C(n,n+p+He3) 10C(n,n+p+d) 10C(n,n+2p)
Reaction # 10C(n,n+2p+d) 10C(n,n+3p) 10C(n,2n) 10C(n,2n+p)
Reaction # 10C(n,2n+2p) 10C(n,2n+3p)
Last update: Tue Aug 20 09:04:52 2024