Basic Info
Fission Yield
n-XS summary
element
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Information about Silver-107:
 |  |  | | | 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
| 1.77606E-15 |
1.40280E-03 |
| U-235 with 1.0 MeV
| 1.37756E-15 |
3.27016E-03 |
| U-238 with 1.0 MeV
| 1.97960E-17 |
1.29612E-02 |
| Pu-239 with 0.0253 eV
| 8.04836E-13 |
3.36101E-02 |
| Pu-239 with 1.0 MeV
| 4.08681E-13 |
3.05265E-02 |
Fission Yields to Meta State
| Fissile with Neutron Energy |
Yields ( sum = 2 ) |
|---|
| Direct |
Accumulated |
|---|
| U-235 with 0.0253 eV
| 1.16209E-14 |
1.16209E-14 |
| U-235 with 1.0 MeV
| 1.03461E-14 |
1.03461E-14 |
| U-238 with 1.0 MeV
| 1.48676E-16 |
1.48676E-16 |
| Pu-239 with 0.0253 eV
| 5.26612E-12 |
5.26612E-12 |
| Pu-239 with 1.0 MeV
| 3.06937E-12 |
3.06937E-12 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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