Comparison of serpent and HELIOS-2 as applied for the PWR few-group cross section generation

Emil Fridman, Jaakko Leppänen, Charles Wemple

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

14 Scopus citations

Abstract

This paper discusses recent modifications to the Serpent Monte Carlo code methodology and related to the calculation of few-group diffusion coefficients and reflector discontinuity factors The new methods were assessed in the following manner. First, few-group homogenized cross sections calculated by Serpent for a reference PWR core were compared with those generated 1 commercial deterministic lattice transport code HELIOS-2. Second, Serpent and HELIOS-2 fe group cross section sets were later employed by nodal diffusion code DYN3D for the modeling the reference PWR core. Finally, the nodal diffusion results obtained using the both cross sectii sets were compared with the full core Serpent Monte Carlo solution. The test calculations shov that Serpent can calculate the parameters required for nodal analyses similar to conventional deterministic lattice codes.

Original languageEnglish
Title of host publicationInternational Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2013
Pages693-703
Number of pages11
StatePublished - 9 Sep 2013
Externally publishedYes
EventInternational Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2013 - Sun Valley, ID, United States
Duration: 5 May 20139 May 2013

Publication series

NameInternational Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2013
Volume1

Conference

ConferenceInternational Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2013
Country/TerritoryUnited States
CitySun Valley, ID
Period5/05/139/05/13

Keywords

  • Few-group cross section generation
  • HELIOS
  • Monte Carlo
  • PWR
  • Serpent

ASJC Scopus subject areas

  • Nuclear Energy and Engineering
  • Applied Mathematics

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