Basic Info
Fission Yield
element
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Information about Zirconium-97:
 |  |  |  | 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
| 7.18085E-03 |
5.99541E-02 |
U-235 with 1.0 MeV
| 7.04590E-03 |
5.98385E-02 |
U-238 with 1.0 MeV
| 2.29688E-03 |
5.57417E-02 |
Pu-239 with 0.0253 eV
| 1.56656E-02 |
5.36591E-02 |
Pu-239 with 1.0 MeV
| 1.33305E-02 |
5.29568E-02 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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