Basic Info
Fission Yield
n-XS summary
element
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Information about Silver-109:
 |  |  | | | 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
| 3.28704E-11 |
3.44818E-04 |
| U-235 with 1.0 MeV
| 2.66602E-11 |
1.15028E-03 |
| U-238 with 1.0 MeV
| 1.14699E-12 |
2.68437E-03 |
| Pu-239 with 0.0253 eV
| 1.14711E-08 |
1.87949E-02 |
| Pu-239 with 1.0 MeV
| 7.25212E-09 |
1.91922E-02 |
Fission Yields to Meta State
| Fissile with Neutron Energy |
Yields ( sum = 2 ) |
|---|
| Direct |
Accumulated |
|---|
| U-235 with 0.0253 eV
| 2.15075E-10 |
3.44646E-04 |
| U-235 with 1.0 MeV
| 2.00230E-10 |
1.14970E-03 |
| U-238 with 1.0 MeV
| 8.61438E-12 |
2.68303E-03 |
| Pu-239 with 0.0253 eV
| 7.50569E-08 |
1.87855E-02 |
| Pu-239 with 1.0 MeV
| 5.44666E-08 |
1.91826E-02 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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