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Parameterized representation of macroscopic cross section for PWR reactor

Authors
Journal
Annals of Nuclear Energy
0306-4549
Publisher
Elsevier
Identifiers
DOI: 10.1016/j.anucene.2014.07.037
Keywords
  • Cross-Section
  • Parameterized Cross-Sections
  • Chebyshev Polynomials
  • Fuel Burnup

Abstract

Abstract The purpose of this work is to describe, by means of Chebyshev polynomials, a parameterized representation of the homogenized macroscopic cross section for PWR fuel element as a function of soluble boron concentration, moderator temperature, fuel temperature, moderator density and U92235 enrichment. The cross-section data analyzed are fission, scattering, total, transport, absorption and capture. The parameterization enables a quick and easy determination of problem-dependent cross-sections to be used in few group calculations. The methodology presented in this paper will allow generation of group cross-section data from stored polynomials to perform PWR core calculations without the need to generate them based on computer code calculations using standard steps. The results obtained by the proposed methodology when compared with results from the SCALE code calculations show very good agreement.

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