TENDL-2023 Nuclear data library

Neutron sub-library for Rg (Z=111) and A=283: Tabular production and total cross sections

Production and total cross sections
Reaction # Rg(n,all) Rg(n,x)a Rg(n,x)d Rg(n,el) Rg(n,f) Rg(n,x)g Rg(n,x)he3 Rg(n,non) Rg(n,x)n Rg(n,x)p Rg(n,reac) Rg(other) Rg(n,x)t
Reaction #
Partial cross sections
Reaction # 283Rg(n,g) 283Rg(n,He3) 283Rg(n,He3+a) 283Rg(n,t)
Reaction # 283Rg(n,t+a) 283Rg(n,d) 283Rg(n,d+a) 283Rg(n,p)
Reaction # 283Rg(n,p+He3+a) 283Rg(n,p+d+a) 283Rg(n,2p+a) 283Rg(n,3p+a)
Reaction # 283Rg(n,n) 283Rg(n,n+a) 283Rg(n,n+t) 283Rg(n,n+t+a)
Reaction # 283Rg(n,n+d+a) 283Rg(n,n+p+a) 283Rg(n,n+2p+a) 283Rg(n,2n)
Reaction # 283Rg(n,2n+a) 283Rg(n,2n+t) 283Rg(n,2n+t+2a) 283Rg(n,2n+p+a)
Reaction # 283Rg(n,3n) 283Rg(n,3n+2a) 283Rg(n,3n+t) 283Rg(n,3n+t+2a)
Reaction # 283Rg(n,3n+d+2a)
Last update: Tue Aug 20 09:04:52 2024