TENDL-2015 Nuclear data library
Neutron sub-library for Pu (Z=94) and A=245: partial cross sections to discrete levels
Reaction types
Reaction #
245
Pu(n,a)
245
Pu(n,d)
245
Pu(n,g)
245
Pu(n,h)
245
Pu(n,inl)
245
Pu(n,p)
245
Pu(n,t)
245
Pu(n,a)