Basic Info
Fission Yield
element
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Information about Zinc-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
| 1.37445E-12 |
1.43259E-08 |
| U-235 with 1.0 MeV
| 3.99469E-12 |
1.06141E-07 |
| U-238 with 1.0 MeV
| 1.73804E-14 |
6.19212E-09 |
| Pu-239 with 0.0253 eV
| 1.61192E-11 |
4.60742E-08 |
| Pu-239 with 1.0 MeV
| 7.40333E-11 |
3.17276E-07 |
Fission Yields to Meta State
| Fissile with Neutron Energy |
Yields ( sum = 2 ) |
|---|
| Direct |
Accumulated |
|---|
| U-235 with 0.0253 eV
| 5.94391E-12 |
5.94391E-12 |
| U-235 with 1.0 MeV
| 1.98446E-11 |
1.98446E-11 |
| U-238 with 1.0 MeV
| 8.63411E-14 |
8.63411E-14 |
| Pu-239 with 0.0253 eV
| 6.97085E-11 |
6.97085E-11 |
| Pu-239 with 1.0 MeV
| 3.67778E-10 |
3.67778E-10 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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