TENDL-2015 Nuclear data library
Neutron sub-library for Pu (Z=94) and A=247: partial cross sections to discrete levels
Reaction types
Reaction #
247
Pu(n,a)
247
Pu(n,d)
247
Pu(n,g)
247
Pu(n,h)
247
Pu(n,inl)
247
Pu(n,p)
247
Pu(n,t)
247
Pu(n,a)