TENDL-2015 Nuclear data library
Neutron sub-library for Pu (Z=94) and A=236: partial cross sections to discrete levels
Reaction types
Reaction #
236
Pu(n,a)
236
Pu(n,d)
236
Pu(n,g)
236
Pu(n,h)
236
Pu(n,inl)
236
Pu(n,p)
236
Pu(n,t)
236
Pu(n,a)