Basic Info
Fission Yield
element
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Information about Zinc-66:
 |  |  | | | 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
| 7.23375E-18 |
7.62319E-10 |
| U-235 with 1.0 MeV
| 1.01210E-16 |
8.81737E-09 |
| U-238 with 1.0 MeV
| 2.54304E-20 |
1.74947E-10 |
| Pu-239 with 0.0253 eV
| 5.22409E-16 |
1.84292E-09 |
| Pu-239 with 1.0 MeV
| 1.72997E-15 |
8.80570E-09 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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