Fuel cycle performance of fast spectrum molten salt reactor designs

Andrei Rykhlevskii, Benjamin R. Betzler, Andrew Worrall, Kathryn Huff

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Abstract

In the search for new ways to generate low-carbon, reliable base-load power, a resurgence of interest in advanced nuclear energy technologies, including Molten Salt Reactors (MSRs), has produced multiple new conceptual MSRs including fast neutron spectrum designs. The fuel cycle performance of four historical fast MSR designs is analyzed using a recently developed SCALE/TRITON 6.2.4 Alpha with a continuous online reprocessing functionality. The fast spectrum and continuous feed and removal of material enable these concepts to have remarkable fuel cycle metrics: (1) resource utilization is approximately 18 times better than for a typical low-enriched thermal spectrum once-through fuel cycle (i.e., from approximately 180 t/GWe-year to 1 t/GWe-year); (2) fast MSRs generate approximately 25 times less nuclear waste than the current once-through fuel cycle. These metrics are consistent with the Evaluation and Screening Study [1], which produced a technology-agnostic quantification of the characteristic performance of alternate fuel cycles. Additionally, full-core and unit cell transport models were created and compared to verify the viability of using simplified unit cell geometries for long-term depletion simulation. The unit cell approximation provided a speedup of 20 times relative to the full-core simulation, with depleted mass relative error for major isotopes of less than 2%. Additional fast MSRs design and analysis challenges associated with different fuel cycles and the use of MSR technology are addressed and discussed.

Original languageEnglish (US)
Title of host publicationInternational Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019
PublisherAmerican Nuclear Society
Pages342-353
Number of pages12
ISBN (Electronic)9780894487699
StatePublished - Jan 1 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
CountryUnited States
CityPortland
Period8/25/198/29/19

Fingerprint

Salt
Reactor
Cycle
Unit
Cell
Metric
Depletion
Relative Error
Radioactive wastes
Neutron
Viability
Nuclear energy
Alternate
Quantification
Isotopes
Screening
Design
Molten salt reactor
Neutrons
Carbon

Keywords

  • Depletion
  • Fast reactor
  • Fuel cycle
  • Molten salt reactor
  • Salt separations
  • Salt treatment

ASJC Scopus subject areas

  • Applied Mathematics
  • Nuclear Energy and Engineering

Cite this

Rykhlevskii, A., Betzler, B. R., Worrall, A., & Huff, K. (2019). Fuel cycle performance of fast spectrum molten salt reactor designs. In International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019 (pp. 342-353). (International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019). American Nuclear Society.

Fuel cycle performance of fast spectrum molten salt reactor designs. / Rykhlevskii, Andrei; Betzler, Benjamin R.; Worrall, Andrew; Huff, Kathryn.

International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019. American Nuclear Society, 2019. p. 342-353 (International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Rykhlevskii, A, Betzler, BR, Worrall, A & Huff, K 2019, Fuel cycle performance of fast spectrum molten salt reactor designs. in International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019. International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019, American Nuclear Society, pp. 342-353, 2019 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019, Portland, United States, 8/25/19.
Rykhlevskii A, Betzler BR, Worrall A, Huff K. Fuel cycle performance of fast spectrum molten salt reactor designs. In International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019. American Nuclear Society. 2019. p. 342-353. (International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019).
Rykhlevskii, Andrei ; Betzler, Benjamin R. ; Worrall, Andrew ; Huff, Kathryn. / Fuel cycle performance of fast spectrum molten salt reactor designs. International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019. American Nuclear Society, 2019. pp. 342-353 (International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019).
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