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Serpent - BISON - THM Preliminary Multiphysics Modeling of a Nuclear Thermal Propulsion System Fuel Assembly

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

Abstract

A high-fidelity framework coupling the Serpent Monte Carlo (MC) code with MOOSE-based tools was developed to rank the importance of feedback mechanisms on the multiphysics solution of an NTP fuel assembly. The study identified the fuel temperature coefficient as the most significant feedback mechanism, followed by hydrogen density changes both in channels and stagnant gaps, monolith temperature feedback, and structural material effects. The impact of neglecting specific feedback mechanisms in multiphysics simulations was also evaluated. Results showed that accurately capturing the fuel temperature feedback is essential for obtaining a physical system response, with a deviation of 695 pcm in effective multiplication factor observed when this feedback is omitted. Smaller deviations, on the order of tens of per cent mile (pcm), were noted when excluding moderator and coolant temperature feedback mechanisms.

Original languageEnglish (US)
Title of host publicationProceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2025
PublisherAmerican Nuclear Society
Pages1301-1310
Number of pages10
ISBN (Electronic)9780894482229
DOIs
StatePublished - 2025
Event2025 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2025 - Denver, United States
Duration: Apr 27 2025Apr 30 2025

Publication series

NameProceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2025

Conference

Conference2025 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2025
Country/TerritoryUnited States
CityDenver
Period4/27/254/30/25

All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering
  • Applied Mathematics

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