Basic Info
Fission Yield
n-XS summary
element
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Information about Tellurium-124:
| | | | 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
| .00000E+00 |
1.24284E-07 |
U-235 with 1.0 MeV
| .00000E+00 |
4.97904E-08 |
U-238 with 1.0 MeV
| 5.00586E-14 |
5.36678E-10 |
Pu-239 with 0.0253 eV
| 7.12219E-10 |
8.22977E-07 |
Pu-239 with 1.0 MeV
| 9.88278E-10 |
1.29138E-06 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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