Basic Info
Fission Yield
element
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Information about Silver-113:
 |  |  | | | 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
| 9.76568E-08 |
1.63294E-04 |
| U-235 with 1.0 MeV
| 1.05705E-07 |
3.36669E-04 |
| U-238 with 1.0 MeV
| 8.56895E-09 |
5.26683E-04 |
| Pu-239 with 0.0253 eV
| 1.63779E-06 |
6.50517E-04 |
| Pu-239 with 1.0 MeV
| 2.54471E-06 |
1.26082E-03 |
Fission Yields to Meta State
| Fissile with Neutron Energy |
Yields ( sum = 2 ) |
|---|
| Direct |
Accumulated |
|---|
| U-235 with 0.0253 eV
| 6.38978E-07 |
6.38978E-07 |
| U-235 with 1.0 MeV
| 7.93891E-07 |
7.93891E-07 |
| U-238 with 1.0 MeV
| 6.43565E-08 |
6.43565E-08 |
| Pu-239 with 0.0253 eV
| 1.07162E-05 |
1.07162E-05 |
| Pu-239 with 1.0 MeV
| 1.91119E-05 |
1.91119E-05 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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