Basic Info
Fission Yield
n-XS summary
element
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Information about Silver-110:
 |  |  | | | 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
| 7.60735E-10 |
7.85678E-10 |
| U-235 with 1.0 MeV
| 9.59580E-10 |
9.96201E-10 |
| U-238 with 1.0 MeV
| 2.37530E-11 |
2.46595E-11 |
| Pu-239 with 0.0253 eV
| 1.14637E-07 |
1.18396E-07 |
| Pu-239 with 1.0 MeV
| 9.00970E-08 |
9.35355E-08 |
Fission Yields to Meta State
| Fissile with Neutron Energy |
Yields ( sum = 2 ) |
|---|
| Direct |
Accumulated |
|---|
| U-235 with 0.0253 eV
| 1.78169E-09 |
1.78169E-09 |
| U-235 with 1.0 MeV
| 2.61582E-09 |
2.61582E-09 |
| U-238 with 1.0 MeV
| 6.47506E-11 |
6.47506E-11 |
| Pu-239 with 0.0253 eV
| 2.68487E-07 |
2.68487E-07 |
| Pu-239 with 1.0 MeV
| 2.45604E-07 |
2.45604E-07 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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