TENDL-2023 Nuclear data library

Neutron sub-library for Mt (Z=109) and A=277: Tabular production and total cross sections

Production and total cross sections

Reaction #	Mt(n,all)	Mt(n,x)a	Mt(n,x)d	Mt(n,el)	Mt(n,f)	Mt(n,x)g	Mt(n,x)he3	Mt(n,non)	Mt(n,x)n	Mt(n,x)p	Mt(n,reac)	Mt(other)	Mt(n,x)t

Reaction #

Partial cross sections

Reaction #	277Mt(n,g)	277Mt(n,a)	277Mt(n,2a)	277Mt(n,3a)

Reaction #	277Mt(n,He3)	277Mt(n,He3+a)	277Mt(n,He3+2a)	277Mt(n,t)

Reaction #	277Mt(n,t+a)	277Mt(n,t+2a)	277Mt(n,t+He3+a)	277Mt(n,d)

Reaction #	277Mt(n,d+a)	277Mt(n,d+2a)	277Mt(n,d+He3+a)	277Mt(n,d+t+a)

Reaction #	277Mt(n,d+t+2a)	277Mt(n,2d+2a)	277Mt(n,p)	277Mt(n,p+a)

Reaction #	277Mt(n,p+2a)	277Mt(n,p+He3+a)	277Mt(n,p+t+a)	277Mt(n,p+t+2a)

Reaction #	277Mt(n,p+d+a)	277Mt(n,p+d+2a)	277Mt(n,2p+a)	277Mt(n,2p+2a)

Reaction #	277Mt(n,2p+t+a)	277Mt(n,3p+a)	277Mt(n,n)	277Mt(n,n+a)

Reaction #	277Mt(n,n+2a)	277Mt(n,n+3a)	277Mt(n,n+He3+a)	277Mt(n,n+He3+2a)

Reaction #	277Mt(n,n+t)	277Mt(n,n+t+a)	277Mt(n,n+t+2a)	277Mt(n,n+d)

Reaction #	277Mt(n,n+d+a)	277Mt(n,n+d+2a)	277Mt(n,n+d+t+2a)	277Mt(n,n+2d+2a)

Reaction #	277Mt(n,n+p)	277Mt(n,n+p+a)	277Mt(n,n+p+2a)	277Mt(n,n+p+t+2a)

Reaction #	277Mt(n,n+p+d+2a)	277Mt(n,n+2p+a)	277Mt(n,n+2p+2a)	277Mt(n,2n)

Reaction #	277Mt(n,2n+a)	277Mt(n,2n+2a)	277Mt(n,2n+3a)	277Mt(n,2n+He3+2a)

Reaction #	277Mt(n,2n+t)	277Mt(n,2n+t+2a)	277Mt(n,2n+d)	277Mt(n,2n+d+2a)

Reaction #	277Mt(n,2n+p+a)	277Mt(n,2n+p+2a)	277Mt(n,2n+p+t+2a)	277Mt(n,2n+p+d+2a)

Reaction #	277Mt(n,2n+2p+2a)	277Mt(n,3n)	277Mt(n,3n+a)	277Mt(n,3n+2a)

Reaction #	277Mt(n,3n+3a)	277Mt(n,3n+He3+2a)	277Mt(n,3n+t)	277Mt(n,3n+t+2a)

Reaction #	277Mt(n,3n+d+2a)	277Mt(n,3n+p+2a)