Basic Info
Fission Yield
element
|
Information about Silver-116:
 |  |  | | | 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
| 4.62889E-06 |
1.49064E-04 |
| U-235 with 1.0 MeV
| 7.59113E-06 |
3.09889E-04 |
| U-238 with 1.0 MeV
| 1.59189E-06 |
4.10021E-04 |
| Pu-239 with 0.0253 eV
| 2.81152E-05 |
3.67170E-04 |
| Pu-239 with 1.0 MeV
| 3.12561E-05 |
4.36206E-04 |
Fission Yields to Meta State
| Fissile with Neutron Energy |
Yields ( sum = 2 ) |
|---|
| Direct |
Accumulated |
|---|
| U-235 with 0.0253 eV
| 1.94657E-05 |
1.94657E-05 |
| U-235 with 1.0 MeV
| 3.68090E-05 |
3.68090E-05 |
| U-238 with 1.0 MeV
| 7.71900E-06 |
7.71900E-06 |
| Pu-239 with 0.0253 eV
| 1.18232E-04 |
1.18232E-04 |
| Pu-239 with 1.0 MeV
| 1.51559E-04 |
1.51559E-04 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
|