Basic Info
Fission Yield
element
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Information about Iodine-144:
 |  |  | | | 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 |
1.56200E-09 |
| U-235 with 1.0 MeV
| .00000E+00 |
6.94045E-09 |
| U-238 with 1.0 MeV
| 3.92274E-07 |
3.92314E-07 |
| Pu-239 with 0.0253 eV
| 4.95051E-11 |
4.95188E-11 |
| Pu-239 with 1.0 MeV
| 7.81519E-11 |
7.81704E-11 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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