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NEUTRONICS SIMULATION OF THE MOLTEN SALT REACTOR EXPERIMENT WITH SCALE/SHIFT AND SERPENT/PARCS

  • Jin Li
  • , Shai Kinast
  • , Volkan Seker
  • , Jipu Wang
  • , Andrew Ward
  • , Brendan Kochunas
  • , Thomas Downar
  • , Ugur Mertyurek

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

Abstract

The Monte Carlo code Serpent 2 was used to generate homogenized few-group constants for the nodal diffusion analysis of the Molten Salt Reactor Experiment (MSRE) zero-power criticality benchmark. A 3D full core model of MSRE was built with Serpent 2 and SCALE/Shift. A good agreement was achieved for the multiplication factor between Serpent 2, SCALE/Shift and the benchmark reference result, demonstrating the consistency between the models. The nodal diffusion analysis of a 3D graphite core model of MSRE was performed with the few-group constants generated by Serpent 2 using nodal diffusion code PARCS. A good agreement between Serpent 2 and PARCS was observed demonstrating the feasibility of using Serpent 2 as a few-group constant generator and using PARCS as a nodal diffusion core simulator for the deterministic MSRE analysis.

Original languageEnglish
Title of host publicationProceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021
PublisherAmerican Nuclear Society
Pages530-539
Number of pages10
ISBN (Electronic)9781713886310
DOIs
StatePublished - 1 Jan 2021
Externally publishedYes
Event2021 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021 - Virtual, Online
Duration: 3 Oct 20217 Oct 2021

Publication series

NameProceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021

Conference

Conference2021 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021
CityVirtual, Online
Period3/10/217/10/21

Keywords

  • MC few-group constant
  • MSRE
  • PARCS
  • Serpent 2
  • nodal diffusion

ASJC Scopus subject areas

  • Nuclear Energy and Engineering
  • Applied Mathematics

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