Impacts of fast-spectrum molten salt reactor characteristics on fuel cycle performance

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

Research output: Contribution to conferencePaperpeer-review

Abstract

The System Analysis and Integration Campaign nuclear fuel cycle evaluation and screening study was conducted to outline the potential benefits and challenges of nuclear fuel cycle options. The study identified continuous recycle in fast critical reactors as a common characteristic shared among some of the most promising future nuclear fuel cycles. This study was technology agnostic to focus on the underpinning physics that drives fuel cycle outcomes. This process used an analysis example to generate a physics-based understanding of the fuel cycle, and it yielded performance metrics over ranges rather than comparing absolute numbers. While no fast-spectrum molten salt reactor (MSR) has ever been built, several concepts exist using different fuels and carrier salts, many of which target high-burnup objectives, such as light-water reactor nuclear waste consumption. Putting the resulting fuel cycle impacts of these reactor choices (e.g., fuel and neutron spectrum) into perspective is informative for our current understanding of a given fuel cycle's performance, and it also demonstrates the applicability of MSRs to different fuel cycles. It has been established that in a fuel cycle transition, performance of a given fast-spectrum MSR depends in part on the initial fuel loading requirements and processing methods.

Original languageEnglish (US)
Pages514-521
Number of pages8
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 'Impacts of fast-spectrum molten salt reactor characteristics on fuel cycle performance'. Together they form a unique fingerprint.

Cite this