TENDL-2015 Nuclear data library
Alpha sub-library for Md (Z=101) and A=256: Tabulated neutron spectra
Spectra for different incident energy
Energy (MeV) #
15
16
17
18
19
20
22
24
26
28
30
35
40
45
50
55
60
65
Energy (MeV) #
70
75
80
90
100
110
120
130
140
150
160
180
200