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On the ENDF/B unresolved resonance region formalism representation for sup 239 Pu

Conference · · Transactions of the American Nuclear Society; (USA)
OSTI ID:6126832
;  [1]; ;
  1. Oak Ridge National Lab., TN (USA)
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The calculation of self-shielded group cross sections is a main ingredient in determining reactor neutronics. During the past few years, core physicists have shown concern about the reliability of self-shielding factor calculations in the unresolved resonance region. The representation of the neutron cross sections in the unresolved resonance region is based on the statistical theory of nuclear reactions. In this region, the cross sections are specified by the average values and distribution functions of the resonance parameters. Cross-section statistics are obtained by the generation of ladders of pseudoresonances and the construction of cross-section probability tables or by deterministic methods. 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.
OSTI ID:
6126832
Report Number(s):
CONF-900608--
Conference Information:
Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 61
Country of Publication:
United States
Language:
English

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Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
654003 -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
CROSS SECTIONS
EVEN-ODD NUCLEI
HEAVY NUCLEI
ISOTOPES
NUCLEAR DATA COLLECTIONS
NUCLEI
PERFORMANCE
PHYSICS
PLUTONIUM 239
PLUTONIUM ISOTOPES
RADIOISOTOPES
REACTOR COMPONENTS
REACTOR CORES
REACTOR PHYSICS
RELIABILITY
SELF-SHIELDING
SHIELDING
YEARS LIVING RADIOISOTOPES