Core design characteristics of the fluoride salt-cooled high temperature demonstration reactor

N. R. Brown, A. L. Qualls, B. R. Betzler, J. J. Carbajo, M. S. Greenwood, R. Hale, T. J. Harrison, J. J. Powers, K. R. Robb

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

    Abstract

    Fluoride salt-cooled high-temperature reactors (FHRs) represent a promising technology. Significant knowledge gaps to implementation may be addressed via a small-scale demonstration reactor (DR) to increase the technology readiness level (TRL) of the system for the longer term. This paper outlines a notional concept and addresses how the concept would advance the TRL of FHR concepts. This notional concept is under development as part of a U.S. Department of Energy Office of Nuclear Energy study of options for advanced test and demonstration reactor systems. Development of the FHR DR will enable commercial FHR deployment through disruptive and rapid technology development and demonstration, closing gaps to commercial viability. Lower risk technologies in the initial design help ensure that the reactor is built, licensed, and operated within an acceptable budget and schedule. Important capabilities to be demonstrated by building and operating the FHR DR include core design methodologies; fabrication and operation of high temperature reactors; salt procurement, handling, maintenance and ultimate disposal; salt chemistry control to maximize vessel life; tritium management; heat exchanger performance (including passive decay heat removal); pump performance; and reactivity control. The FHR DR is part of the broader FHR technology development and demonstration efforts already underway. Nonreactor test efforts (e.g., heated salt loops or loops using simulant fluids) can demonstrate technologies necessary for commercial deployment of FHRs. The FHR DR advances the technical maturity and readiness level of the system.

    Original languageEnglish (US)
    Title of host publicationInternational Congress on Advances in Nuclear Power Plants, ICAPP 2016
    PublisherAmerican Nuclear Society
    Pages810-818
    Number of pages9
    ISBN (Electronic)9781510825949
    StatePublished - Jan 1 2016
    Event2016 International Congress on Advances in Nuclear Power Plants, ICAPP 2016 - San Francisco, United States
    Duration: Apr 17 2016Apr 20 2016

    Publication series

    NameInternational Congress on Advances in Nuclear Power Plants, ICAPP 2016
    Volume2

    Other

    Other2016 International Congress on Advances in Nuclear Power Plants, ICAPP 2016
    CountryUnited States
    CitySan Francisco
    Period4/17/164/20/16

    All Science Journal Classification (ASJC) codes

    • Energy Engineering and Power Technology
    • Nuclear Energy and Engineering

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