TENDL-2015 Nuclear data library
Neutron sub-library for Cf (Z=98) and A=240: partial cross sections to discrete levels
Reaction types
Reaction #
240
Cf(n,a)
240
Cf(n,d)
240
Cf(n,g)
240
Cf(n,h)
240
Cf(n,inl)
240
Cf(n,p)
240
Cf(n,t)
240
Cf(n,a)