TENDL-2015 Nuclear data library
Neutron sub-library for Pu (Z=94) and A=229: partial cross sections to discrete levels
Reaction types
Reaction #
229
Pu(n,a)
229
Pu(n,d)
229
Pu(n,g)
229
Pu(n,h)
229
Pu(n,inl)
229
Pu(n,p)
229
Pu(n,t)
229
Pu(n,a)