Preliminary Demonstration Reactor Point Design for the Fluoride Salt-Cooled High-Temperature Reactor

A. L. Qualls, Benjamin R. Betzler, Nicholas R. Brown, Juan Carbajo, Michael Scott Greenwood, Richard Edward Hale, Thomas J. Harrison, Jeffrey J. Powers, Kevin R. Robb, Jerry W. Terrell

Research output: Book/ReportCommissioned report

Abstract

Development of the Fluoride Salt-Cooled High-Temperature Reactor (FHR) Demonstration Reactor (DR) is a necessary intermediate step to enable commercial FHR deployment through disruptive and rapid technology development and demonstration. The FHR DR will utilize known, mature technology to close remaining gaps to commercial viability. Lower risk technologies are included in the initial FHR DR design to ensure that the reactor can be built, licensed, and operated within an acceptable budget and schedule. These technologies include tristructural-isotropic (TRISO) particle fuel, replaceable core structural material, the use of that same material for the primary and intermediate loops, and tube-and-shell heat exchangers. This report provides an update on the development of the FHR DR. At this writing, the core neutronics and thermal hydraulics have been developed and analyzed. The mechanical design details are still under development and are described to their current level of fidelity. It is anticipated that the FHR DR can be operational within 10 years because of the use of low-risk, near-term technology options.
Original languageEnglish
Place of PublicationUnited States
DOIs
StatePublished - 2015

Keywords

  • 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
  • MOLTEN SALT COOLED REACTORS
  • TEMPERATURE RANGE 0400-1000 K
  • FLUORIDES
  • HEAT EXCHANGERS
  • DESIGN
  • FUEL PARTICLES
  • COMMERCIALIZATION
  • SHELLS
  • TUBES

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