43-Tc-107
basic
fission yield
element
|
43-technetium-107
Fission Yields
| Fissile with Neutron Energy |
Yields ( sum = 2 ) |
|---|
| Direct |
Accumulated |
|---|
| U-235 with 0.0253 eV
| 1.75041E-04 |
1.20533E-03 |
| U-235 with 1.0 MeV
| 1.59333E-03 |
3.02278E-03 |
| U-238 with 1.0 MeV
| 3.02073E-03 |
1.27300E-02 |
| Pu-239 with 0.0253 eV
| 1.89182E-02 |
2.62688E-02 |
| Pu-239 with 1.0 MeV
| 1.77226E-02 |
2.48455E-02 |
CSWEG, ENDF/B-VI Summary Documentation,Report BNL-NCS-17541 (ENDF-201) (1991)
|