Basic Info
Fission Yield
element
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Information about Zirconium-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
| 1.16348E-08 |
1.16349E-08 |
| U-235 with 1.0 MeV
| 3.82095E-08 |
3.82106E-08 |
| U-238 with 1.0 MeV
| 2.68341E-06 |
2.68368E-06 |
| Pu-239 with 0.0253 eV
| 2.09721E-08 |
2.09723E-08 |
| Pu-239 with 1.0 MeV
| 2.72881E-08 |
2.72884E-08 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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