Basic Info
Fission Yield
element
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Information about Bromine-91:
 |  |  | | | 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
| 2.44567E-03 |
2.45826E-03 |
| U-235 with 1.0 MeV
| 1.86357E-03 |
1.87590E-03 |
| U-238 with 1.0 MeV
| 4.58915E-03 |
4.70734E-03 |
| Pu-239 with 0.0253 eV
| 1.70975E-04 |
1.71391E-04 |
| Pu-239 with 1.0 MeV
| 3.82816E-04 |
3.83823E-04 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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