Reevaluation of the {sup 235}U crosss sections for ENDF/B-VI
Journal Article
·
· Transactions of the American Nuclear Society
OSTI ID:411806
- Oak Ridge National Lab., TN (United States)
The ENDF/B-VI {sup 235}U resonance representation of the neutron cross sections in the resolved energy range has been included in several nuclear data libraries throughout the world; it is the cross-section representation used in the European files, the Joint Evaluation File, and the Japanese files, Japanese Evaluated Nuclear Data Library. Consequently, the {sup 235}U evaluation has undergone several tests. The French Laboratory, CEN Cadarche, has indicated that the current {sup 235}U parametric representation gives a value of the capture cross section 13% lower than that expected in integral calculations for the energy range 22.6 to 454 eV. In addition, it has been found that the ENDF/B-VI parametric representation of the {sup 235}U cross sections is unable to resolve a long-standing problem to properly predict the desired capture-to-fission ratio, the {alpha} ratio. These results clearly point out deficiencies in ENDF/B-VI in reproducing integral results.
- OSTI ID:
- 411806
- Report Number(s):
- CONF-951006--
- Journal Information:
- Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 73; ISSN 0003-018X; ISSN TANSAO
- Country of Publication:
- United States
- Language:
- English
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