TENDL-2015 Nuclear data library

Neutron sub-library for Md (Z=101) and A=246m: partial cross sections to discrete levels

Reaction types

Reaction #	^246mMd(n,a)	^246mMd(n,d)	^246mMd(n,g)	^246mMd(n,h)	^246mMd(n,inl)	^246mMd(n,p)	^246mMd(n,t)	^246mMd(n,a)

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