TENDL-2015 Nuclear data library
Neutron sub-library for Md (Z=101) and A=256: partial cross sections to discrete levels
Reaction types
Reaction #
256
Md(n,a)
256
Md(n,d)
256
Md(n,g)
256
Md(n,h)
256
Md(n,inl)
256
Md(n,p)
256
Md(n,t)
256
Md(n,a)