TENDL-2023 Nuclear data library

Neutron sub-library for Bi (Z=83) and A=209: Tabular production and total cross sections

Production and total cross sections
Reaction # Bi(n,all) Bi(n,x)a Bi(n,x)d Bi(n,el) Bi(n,x)g Bi(n,x)he3 Bi(n,non) Bi(n,x)n Bi(n,x)p Bi(n,reac) Bi(other) Bi(n,x)t
Reaction #
Partial cross sections
Reaction # 209Bi(n,g) 209Bi(n,a) 209Bi(n,2a) 209Bi(n,3a)
Reaction # 209Bi(n,He3) 209Bi(n,t) 209Bi(n,t+a) 209Bi(n,d)
Reaction # 209Bi(n,d+a) 209Bi(n,p) 209Bi(n,p+a) 209Bi(n,p+2a)
Reaction # 209Bi(n,p+t) 209Bi(n,p+d) 209Bi(n,2p) 209Bi(n,n)
Reaction # 209Bi(n,n+a) 209Bi(n,n+2a) 209Bi(n,n+3a) 209Bi(n,n+He3)
Reaction # 209Bi(n,n+t) 209Bi(n,n+d) 209Bi(n,n+p) 209Bi(n,n+p+a)
Reaction # 209Bi(n,n+2p) 209Bi(n,2n) 209Bi(n,2n+a) 209Bi(n,2n+d)
Reaction # 209Bi(n,2n+p) 209Bi(n,3n) 209Bi(n,3n+a) 209Bi(n,3n+p)
Reaction #
Last update: Mon Dec 18 11:47:26 2023