Basic Info
Fission Yield
element
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Information about Copper-69:
 |  |  | | | 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
| 7.02843E-10 |
1.43186E-08 |
| U-235 with 1.0 MeV
| 3.67835E-09 |
1.06117E-07 |
| U-238 with 1.0 MeV
| 3.65428E-11 |
6.19202E-09 |
| Pu-239 with 0.0253 eV
| 4.79155E-09 |
4.59884E-08 |
| Pu-239 with 1.0 MeV
| 3.03359E-08 |
3.16834E-07 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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