Analysis of the oecd mslb benchmark with the coupled neutronic and thermal-hydraulics code RELAP5/PARCS

T. Kozlowski, R. M. Miller, T. Downar, D. D. Ebert

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Abstract

The USNRC version of the 3D neutron kinetics code PARCS (Purdue Advanced Reactor Core Simulator) has been coupled with the USNRC thermal-hydraulics codes RELAP5. The OECD/NEA PWR MSLB benchmark problem was performed in order to provide an assessment of RELAP5/PARCS and in order to evaluate the differences in the point kinetics and spatial kinetics analysis of the MSLB transient. Results are presented using both the “best estimate” and “return to power” cross section sets provided in the benchmark problem. In both cases, an increase in the shutdown margin is provided by the spatial kinetics solution.

Original languageEnglish (US)
Title of host publicationProceedings of the PHYSOR 2000 - ANS International Topical Meeting on Advances in Reactor Physics and Mathematics and Computation into the Next Millennium
PublisherAmerican Nuclear Society
ISBN (Electronic)0894486551, 9780894486555
StatePublished - 2000
Externally publishedYes
Event2000 ANS International Topical Meeting on Advances in Reactor Physics and Mathematics and Computation into the Next Millennium, PHYSOR 2000 - Pittsburgh, United States
Duration: May 7 2020May 12 2020

Publication series

NameProceedings of the PHYSOR 2000 - ANS International Topical Meeting on Advances in Reactor Physics and Mathematics and Computation into the Next Millennium

Conference

Conference2000 ANS International Topical Meeting on Advances in Reactor Physics and Mathematics and Computation into the Next Millennium, PHYSOR 2000
Country/TerritoryUnited States
CityPittsburgh
Period5/7/205/12/20

ASJC Scopus subject areas

  • Nuclear Energy and Engineering
  • Nuclear and High Energy Physics
  • Radiation
  • Safety, Risk, Reliability and Quality

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