Basic Info
Fission Yield
element
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Information about Technetium-107:
 |  |  |  | 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
| 1.75041E-04 |
1.20533E-03 |
U-235 with 1.0 MeV
| 1.59333E-03 |
3.02278E-03 |
U-238 with 1.0 MeV
| 3.02073E-03 |
1.27300E-02 |
Pu-239 with 0.0253 eV
| 1.89182E-02 |
2.62688E-02 |
Pu-239 with 1.0 MeV
| 1.77226E-02 |
2.48455E-02 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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