TENDL-2015 Nuclear data library
Neutron sub-library for Pu (Z=94) and A=231: partial cross sections to discrete levels
Reaction types
Reaction #
231
Pu(n,a)
231
Pu(n,d)
231
Pu(n,g)
231
Pu(n,h)
231
Pu(n,inl)
231
Pu(n,p)
231
Pu(n,t)
231
Pu(n,a)