Basic Info
Fission Yield
n-XS summary
element
|
Information about Cadmium-113:
 |  |  |  | Wikipedia | Neutron Cross Sections | X-Ray Transitions | X-Ray Attenuation |
Fission Yields
Fissile with Neutron Energy |
Yields ( sum = 2 ) |
Direct |
Accumulated |
U-235 with 0.0253 eV
| .00000E+00 |
1.60748E-04 |
U-235 with 1.0 MeV
| .00000E+00 |
3.31368E-04 |
U-238 with 1.0 MeV
| 6.40717E-12 |
5.18271E-04 |
Pu-239 with 0.0253 eV
| 1.24567E-08 |
6.41202E-04 |
Pu-239 with 1.0 MeV
| 1.63854E-08 |
1.24259E-03 |
Fission Yields to Meta State
Fissile with Neutron Energy |
Yields ( sum = 2 ) |
Direct |
Accumulated |
U-235 with 0.0253 eV
| .00000E+00 |
2.61378E-06 |
U-235 with 1.0 MeV
| .00000E+00 |
5.38758E-06 |
U-238 with 1.0 MeV
| 2.42588E-11 |
8.42696E-06 |
Pu-239 with 0.0253 eV
| 4.07606E-08 |
1.04490E-05 |
Pu-239 with 1.0 MeV
| 6.20383E-08 |
2.02351E-05 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
|