Creation of problem-dependent Doppler-broadened cross sections in the KENO Monte Carlo code

Journal Article · 06 November 2015 · Annals of Nuclear Energy (Oxford)

DOI: https://doi.org/10.1016/j.anucene.2015.10.011 · OSTI ID:1286860

Hart, Shane W. D. ^[1]; Celik, Cihangir ^[1]; Maldonado, G. Ivan ^[2]; Leal, Luiz C. ^[1]

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1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
2. Univ. of Tennessee, Knoxville, TN (United States)

In this paper, we introduce a quick method for improving the accuracy of Monte Carlo simulations by generating one- and two-dimensional cross sections at a user-defined temperature before performing transport calculations. A finite difference method is used to Doppler-broaden cross sections to the desired temperature, and unit-base interpolation is done to generate the probability distributions for double differential two-dimensional thermal moderator cross sections at any arbitrarily user-defined temperature. The accuracy of these methods is tested using a variety of contrived problems. In addition, various benchmarks at elevated temperatures are modeled, and results are compared with benchmark results. Lastly, the problem-dependent cross sections are observed to produce eigenvalue estimates that are closer to the benchmark results than those without the problem-dependent cross sections.

• Research Organization: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA)
• Grant/Contract Number: AC05-00OR22725
• OSTI ID: 1286860
• Journal Information: Annals of Nuclear Energy (Oxford), Journal Name: Annals of Nuclear Energy (Oxford) Vol. 88; ISSN 0306-4549
• Publisher: ElsevierCopyright Statement
• Country of Publication: United States
• Language: English