CODE | NUCLIDE | ORIGINAL DATA TAKEN FROM | MODIFICATION | ADDITIONAL FILE MODIFICATIONS | ORIGINAL DATA TAKEN FROM | MODIFICATION | ADDITIONAL FILE MODIFICATIONS | ORIGINAL DATA TAKEN FROM | MODIFICATION | ADDITIONAL FILE MODIFICATIONS | COMMENTS |
1045103 | Rh103 | Modified parts for JENDL-3.2 Modified parts for JENDL-4.0 | (1,451) Updated. (2,151) Updated. (3,1) Re-calculated from partial cross sections. (3,2) Calculated from URP in lower energy range. (3,4) Re-calculated from partial cross sections. (3,102) Calculated from URP in lower energy range. |
In JENDL-4.0, the radiation width of 1.259-eV resonance wa changed to 139.6 meV in order to reproduce the thermal capture cross section of 133.0+-0.93 b measured by Lee et al./26/ For JENDL-4.0, the unresolved resonance parameters were re-evaluated by the ASREP /27/ code so as to reproduce the total and capture cross sections given in JENDL3.3 in the energy region from 3.58 keV to 100 keV. The parameters shoul be used only for self-shielding calculations. |
JENDL-3.2 | (2,151) Resolved and unresolved resonace parameters (3,1), (3,2), (3,4), (3,51-91), (3,102), (3,251) (4,2), (4,51-91) New OMP was determined and renormalization of capture cross section was made. |
JENDL-3.2 data were automatically transformed to JENDL-3.3. Interpolation of spectra: 22 (unit base interpolation) (3,251) deleted, T-matrix of (4,2) deleted, and others. Resonance parameters in JENDL-3.3 were revised for JENDL-4. |