Safety analysis of the molten salt fast reactor fuel composition using Moltres

Sun Myung Park, Andrei Rykhlevskii, Kathryn D. Huff

Research output: Contribution to conferencePaper

Abstract

The Molten Salt Fast Reactor (MSFR) has garnered much interest for its inherent safety and sustainbility features. The MSFR can adopt a closed thorium fuel cycle for sustainable operation through the breeding of 233U from 232Th. The fuel composition changes significantly over the course of its lifespan. In this study, we investigated the steady state and transient behavior of the MSFR using Moltres, a coupled neutronics/thermal-hydraulics code developed within the Multiphysics Object Oriented Simulation Environment (MOOSE) framework. Three different fuel compositions, start-up, early-life, and equilibrium, were examined for potentially dangerous core temperature excursions during a unprotected loss of heat sink (ULOHS) accident. The six-group and total neutron flux distributions showed good agreement with SERPENT and published MSFR results, while the temperature distribution and total power showed discrepancies which can be attributed to known sources of error. For the transient behavior under the ULOHS scenario, while the transition time towards the new steady state core temperature is also in good agreement with existing MSFR simulations by Fiorina et al., Moltres underestimated the temperature rise by a factor of ten, due to the same sources of error affecting the steady state results. While an MSFR loaded with start-up fuel composition operates at a higher temperature than with the other two fuel compositions, all three cases were shown to be inherently safe due to the strong negative temperature feedback.

Original languageEnglish (US)
Pages940-948
Number of pages9
StatePublished - Jan 1 2020
Event14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019 - Seattle, United States
Duration: Sep 22 2019Sep 27 2019

Conference

Conference14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019
CountryUnited States
CitySeattle
Period9/22/199/27/19

ASJC Scopus subject areas

  • Fuel Technology
  • Nuclear Energy and Engineering

Fingerprint Dive into the research topics of 'Safety analysis of the molten salt fast reactor fuel composition using Moltres'. Together they form a unique fingerprint.

  • Cite this

    Park, S. M., Rykhlevskii, A., & Huff, K. D. (2020). Safety analysis of the molten salt fast reactor fuel composition using Moltres. 940-948. Paper presented at 14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019, Seattle, United States.