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Fuel management code development for molten salt reactor

  • Xi'an Jiaotong University

Research output: Contribution to journalArticlepeer-review

4 Scopus citations

Abstract

The fuels of molten salt reactor redistribute due to the circulation of fuel and the fission products in fuel are extracted by the online fuel reprocessing unit, which all lead to the fuel management code for the conventional reactors using solid fuel not applicable. The micro-depletion fuel management code named MOREL, adopting "two steps" method, was developed in this study based on the analytic basis functions expansion nodal method and transmutation trajectory analysis (TTA) method, and some numerical tests were chosen to verify the code. The results indicate that MOREL has high precision. At last, the preliminary fuel reprocessing simulation was examined for thorium-based molten salt reactor.

Original languageEnglish
Pages (from-to)425-429
Number of pages5
JournalYuanzineng Kexue Jishu/Atomic Energy Science and Technology
Volume49
DOIs
StatePublished - 20 May 2015

Keywords

  • Fuel management
  • Micro-depletion
  • Molten salt reactor

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