48-Cd-109
basic
fission yield
XS graphs
element
|
48-cadmium-109
Fission Yields
Fissile with Neutron Energy |
Yields ( sum = 2 ) |
Direct |
Accumulated |
U-235 with 0.0253 eV
| .00000E+00 |
1.00977E-14 |
U-235 with 1.0 MeV
| .00000E+00 |
7.74500E-15 |
U-238 with 1.0 MeV
| 6.94464E-17 |
6.94464E-17 |
Pu-239 with 0.0253 eV
| 6.56212E-12 |
6.56212E-12 |
Pu-239 with 1.0 MeV
| 3.91119E-12 |
3.91119E-12 |
CSWEG, ENDF/B-VI Summary Documentation,Report BNL-NCS-17541 (ENDF-201) (1991)
|