Basic Info
Fission Yield
element
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Information about Tellurium-141:
| | | | 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 |
2.44072E-08 |
U-235 with 1.0 MeV
| .00000E+00 |
8.42131E-08 |
U-238 with 1.0 MeV
| 3.68478E-06 |
3.68504E-06 |
Pu-239 with 0.0253 eV
| 7.83733E-10 |
7.83892E-10 |
Pu-239 with 1.0 MeV
| 1.14704E-09 |
1.14726E-09 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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