Neutronics calculations for denatured molten salt reactors: Assessing resource requirements and proliferation-risk attributes

Ali Ahmad, Edward B. McClamrock, Alexander Glaser

Research output: Contribution to journalArticlepeer-review

20 Scopus citations

Abstract

Molten salt reactors (MSRs) are often advocated as a radical but worthwhile alternative to traditional reactor concepts based on solid fuels. This article builds upon the existing research into MSRs to model and simulate the operation of thorium-fueled single-fluid and two-fluid reactors. The analysis is based on neutronics calculations and focuses on denatured MSR systems. Resource utilization and basic proliferation-risk attributes are compared to those of standard light-water reactors. Depending on specific design choices, even fully denatured reactors could reduce uranium and enrichment requirements by a factor of 3-4. Overall, denatured single-fluid designs appear as the most promising candidate technology minimizing both design complexity and overall proliferation risks despite being somewhat less attractive from the perspective of resource utilization.

Original languageEnglish (US)
Pages (from-to)261-267
Number of pages7
JournalAnnals of Nuclear Energy
Volume75
DOIs
StatePublished - Jan 2015

All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering

Keywords

  • Denatured fuel
  • Molten salt reactors
  • Proliferation resistance

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