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Fuel Flow Modeling under Thermal Fluidics Considerations within Operational Domains of Molten Salt Reactors

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

2 Scopus citations

Abstract

Molten Salt Reactors (MSRs) offer significant versatility supported by their design flexibility and safety advantages due to high temperatures, design customization capabilities, strong negative reactivity feedback effects, and salt chemistry characteristics.Different control schedules and different mass flow rates in the MSR primary systems impact neutronics and thermal hydraulics coupling.The result is twofold.First, it leads to adaptability in various applications when the customization of a MSR unit is desired.Second, it calls for the quantification of dynamics and safety characteristics to assess the operational domain and make sure reactor stability and inherent safety characteristics are maintained.This paper provides an in-depth transient analysis of the operational implications of MSRs having heat-generating fuel and heat-transporting salt mixed forming liquid fuel salts contained within primary systems.A coupling model was developed to simulate fuel flow in molten salt reactors.A zero-dimensional reactor kinetics model was used with a one-dimensional heat transfer model in the reactor core.The temperature reactivity feedbacks of the fuel salt resulting from the thermal-hydraulics model were used in the reactor kinetics model to complete the coupled code.The model was first validated with the experimental results from the Molten Salt Reactor Experiment (MSRE).Then, it was applied to simulate the Molten Salt Breeder Reactor (MSBR) response at steady state and transients.The developed model was shown to be a suitable tool for the dynamic analysis of molten salt reactors.

Original languageEnglish
Title of host publicationProceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
PublisherAmerican Nuclear Society
Pages3208-3221
Number of pages14
ISBN (Electronic)9780894487934
DOIs
StatePublished - 2023
Event20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023 - Washington, United States
Duration: Aug 20 2023Aug 25 2023

Publication series

NameProceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023

Conference

Conference20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
Country/TerritoryUnited States
CityWashington
Period08/20/2308/25/23

Keywords

  • Fuel Flow
  • Fueled Salt
  • Molten Salt Reactors
  • Reactor Operation
  • Transient Behavior

INL Publication Number

  • INL/MIS-23-73970
  • 159691

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