Basic Info
Fission Yield
n-XS summary
element
|
Information about Ruthenium-103:
![](/KAERI/images/Wikipedia-Logo.png) | ![](/KAERI/images/Janis-4-Logo.gif) | ![](/KAERI/images/NIST-Logo.png) | ![](/KAERI/images/NIST-Logo.png) | 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
| 5.79871E-07 |
3.02742E-02 |
U-235 with 1.0 MeV
| 2.08906E-07 |
3.27491E-02 |
U-238 with 1.0 MeV
| 1.75205E-08 |
6.20956E-02 |
Pu-239 with 0.0253 eV
| 6.54212E-06 |
6.95001E-02 |
Pu-239 with 1.0 MeV
| 4.25129E-06 |
6.83408E-02 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
|