43-Tc-101
basic
fission yield
element
|
43-technetium-101
Fission Yields
| Fissile with Neutron Energy |
Yields ( sum = 2 ) |
|---|
| Direct |
Accumulated |
|---|
| U-235 with 0.0253 eV
| 4.57898E-06 |
5.08143E-02 |
| U-235 with 1.0 MeV
| 2.06907E-06 |
5.34979E-02 |
| U-238 with 1.0 MeV
| 9.96167E-08 |
6.08223E-02 |
| Pu-239 with 0.0253 eV
| 2.61585E-05 |
5.89788E-02 |
| Pu-239 with 1.0 MeV
| 2.41773E-05 |
6.54032E-02 |
CSWEG, ENDF/B-VI Summary Documentation,Report BNL-NCS-17541 (ENDF-201) (1991)
|