On the ENDF/B unresolved resonance region formalism representation for sup 239 Pu
Conference
·
OSTI ID:6989445
- Centro Tecnico Aerospacial, Sao Jose dos Campos, SP (Brazil). Inst. de Estudos Avancados
- Tennessee Univ., Knoxville, TN (USA). Dept. of Nuclear Engineering
- Oak Ridge National Lab., TN (USA)
The purpose of this work is to compare the performance of several cross-section evaluation files for the calculation of average cross sections in the unresolved resonance region and to test the validity of the ENDF/B methodology for the calculation of self-shielding factors in this region. The {sup 239}Pu neutron cross sections were used for this comparison since a multilevel R-matrix analysis was available, which extended the resolved resonance region from its present ENDF/B limit of 300 eV up to 1 keV. 12 refs., 2 tabs.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- Sponsoring Organization:
- DOE/ER
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6989445
- Report Number(s):
- CONF-900608-6; ON: DE90005675
- Country of Publication:
- United States
- Language:
- English
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