The modeling of advanced BWR fuel designs with the U.S. NRC fuel depletion codes PARCS/PATHS

A. Wysocki, J. March-Leuba, C. Thurston, N. Hudson, A. Ireland, A. Ward, A. Manera, Y. Xu, T. Downar

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

1 Scopus citations

Abstract

The modeling of advanced BWR fuel designs during fuel depletion requires the explicit treatment of part length fuel rods and a heterogeneous axial flow geometry in the fuel channel. The U.S. NRC fuel depletion codes PARCS/PATHS were modified to model advanced fuel designs and validated using previously benchmarked advanced core simulators as well as BWR plant and experimental data. The modifications to the codes and the results of the validation are described in this paper.

Original languageEnglish
Title of host publicationEmbedded Topical Meeting on Advances in Thermal Hydraulics, ATH 2014, Held at the American Nuclear Society 2014 Annual Meeting
PublisherAmerican Nuclear Society
Pages136-147
Number of pages12
ISBN (Electronic)9781632668509
StatePublished - 2014
Externally publishedYes
EventEmbedded Topical Meeting on Advances in Thermal Hydraulics, ATH 2014, Held at the American Nuclear Society 2014 Annual Meeting - Reno, United States
Duration: Jun 15 2014Jun 19 2014

Publication series

NameEmbedded Topical Meeting on Advances in Thermal Hydraulics, ATH 2014, Held at the American Nuclear Society 2014 Annual Meeting

Conference

ConferenceEmbedded Topical Meeting on Advances in Thermal Hydraulics, ATH 2014, Held at the American Nuclear Society 2014 Annual Meeting
Country/TerritoryUnited States
CityReno
Period06/15/1406/19/14

Keywords

  • BWR
  • Depletion
  • Simulator

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