Basic Info
Fission Yield
element
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Information about Zinc-74:
 |  |  |  | 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
| 2.30949E-06 |
3.54998E-06 |
U-235 with 1.0 MeV
| 7.65657E-06 |
1.48423E-05 |
U-238 with 1.0 MeV
| 3.26382E-07 |
9.62583E-07 |
Pu-239 with 0.0253 eV
| 3.69120E-06 |
4.92950E-06 |
Pu-239 with 1.0 MeV
| 1.14935E-05 |
1.63830E-05 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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