TENDL-2015 Nuclear data library

Neutron sub-library for Md (Z=101) and A=247: partial cross sections to discrete levels

Reaction types

Reaction #	²⁴⁷Md(n,a)	²⁴⁷Md(n,d)	²⁴⁷Md(n,g)	²⁴⁷Md(n,h)	²⁴⁷Md(n,inl)	²⁴⁷Md(n,p)	²⁴⁷Md(n,t)	²⁴⁷Md(n,a)

Last update: Thu Jan 14 13:58:41 2016