Basic Info
Fission Yield
element
|
Information about Iodine-143:
 |  |  | | | 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 |
1.24132E-07 |
| U-235 with 1.0 MeV
| .00000E+00 |
2.89926E-07 |
| U-238 with 1.0 MeV
| 9.15614E-06 |
9.16025E-06 |
| Pu-239 with 0.0253 eV
| 5.16704E-09 |
5.16920E-09 |
| Pu-239 with 1.0 MeV
| 7.68562E-09 |
7.68845E-09 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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