Basic Info
Fission Yield
element
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Information about Copper-67:
 |  |  | | | 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
| 5.61875E-12 |
3.91331E-09 |
| U-235 with 1.0 MeV
| 2.09906E-11 |
2.83513E-08 |
| U-238 with 1.0 MeV
| 2.83332E-14 |
6.06170E-10 |
| Pu-239 with 0.0253 eV
| 1.84060E-11 |
3.68045E-09 |
| Pu-239 with 1.0 MeV
| 1.14035E-10 |
2.90987E-08 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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