Noble metal mass transport model for molten salt reactor analysis in VERA-CS

Samuel A. Walker, Zack Taylor, Robert Salko, Benjamin Collins, Wei Ji

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

4 Scopus citations

Abstract

Molten salt reactor (MSR) designs require robust multiphysics modelling capabilities to further the development of this next generation technology. Due to the unique liquid fuel design, traditional reactor physics analysis codes do not capture all of the important physics of these reactors. This work builds upon a general species transport model implemented into the multiphysics core simulator suite VERA-CS, by adding source and sink models for insoluble fission products, specifically the noble metals. Noble metal (NM) fission products are born in the fuel-salt, but do not form stable fluorides, and instead plate-out on various surfaces in the reactor fuel loop. A concentration gradient advection-diffusion based mass transfer model is implemented into the general species transport model within CTF – the subchannel thermal hydraulics code in VERA-CS – and verified using convergence tests in space and time. Two noble metal decay chains are analyzed, and their steady state bulk liquid densities and surface concentrations are calculated for a simple flow loop in CTF that is roughly representative of the Oak Ridge National Laboratory Molten Salt Reactor Experiment (MSRE) [1]. Insoluble species 99Mo decaying to 99Tc captures wall accumulation of decaying species, and insoluble 131Sb to semi-soluble 131Te to soluble 131I captures wall loss of decaying species. Results are compared with MSRE data and the possible multiphysics effects of this phenomena are identified. Future work to enhance the robustness of the physical model and couple it with neutronics to evaluate the effects of NM mass transport is discussed.

Original languageEnglish
Title of host publicationInternational Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019
PublisherAmerican Nuclear Society
Pages2268-2277
Number of pages10
ISBN (Electronic)9780894487699
StatePublished - 2019
Event2019 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019 - Portland, United States
Duration: Aug 25 2019Aug 29 2019

Publication series

NameInternational Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019

Conference

Conference2019 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019
Country/TerritoryUnited States
CityPortland
Period08/25/1908/29/19

Keywords

  • CTF
  • Mass transport
  • Molten salt reactor
  • VERA-CS

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