Basic Info
Fission Yield
n-XS summary
element
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Information about Gallium-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
| 5.06337E-16 |
1.43259E-08 |
| U-235 with 1.0 MeV
| 5.10604E-15 |
1.06141E-07 |
| U-238 with 1.0 MeV
| 3.85468E-18 |
6.19212E-09 |
| Pu-239 with 0.0253 eV
| 4.61132E-14 |
4.60743E-08 |
| Pu-239 with 1.0 MeV
| 2.23412E-13 |
3.17276E-07 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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