Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Core design and safety analysis

doi:10.1016/j.anucene.2017.01.003

Title: Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Core design and safety analysis

Full Record
Other Related Research

Authors:: Brown, Nicholas R.; Betzler, Benjamin R.; Carbajo, Juan J.; Wysocki, Aaron J.; Greenwood, M. Scott; Gentry, Cole; Qualls, A. Louis

Publication Date:: 2017-05-01

Sponsoring Org.:: USDOE Office of Nuclear Energy (NE)

OSTI Identifier:: 1429507

Grant/Contract Number:: AC05-00OR22725

Resource Type:: Publisher's Accepted Manuscript

Journal Name:: Annals of Nuclear Energy (Oxford)

Additional Journal Information:: Journal Name: Annals of Nuclear Energy (Oxford) Journal Volume: 103 Journal Issue: C; Journal ID: ISSN 0306-4549

Publisher:: Elsevier

Country of Publication:: United Kingdom

Language:: English

Citation Formats


                    Brown, Nicholas R., Betzler, Benjamin R., Carbajo, Juan J., Wysocki, Aaron J., Greenwood, M. Scott, Gentry, Cole, and Qualls, A. Louis. Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Core design and safety analysis.  United Kingdom: N. p., 2017. 
        Web.  doi:10.1016/j.anucene.2017.01.003.

Copy to clipboard


                    Brown, Nicholas R., Betzler, Benjamin R., Carbajo, Juan J., Wysocki, Aaron J., Greenwood, M. Scott, Gentry, Cole, & Qualls, A. Louis. Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Core design and safety analysis.  United Kingdom.  doi:10.1016/j.anucene.2017.01.003.

Copy to clipboard


                    Brown, Nicholas R., Betzler, Benjamin R., Carbajo, Juan J., Wysocki, Aaron J., Greenwood, M. Scott, Gentry, Cole, and Qualls, A. Louis. Mon .  
        "Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Core design and safety analysis".  United Kingdom.  doi:10.1016/j.anucene.2017.01.003.

Copy to clipboard


                    
@article{osti_1429507,

  title        = {Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Core design and safety analysis},

  author       = {Brown, Nicholas R. and Betzler, Benjamin R. and Carbajo, Juan J. and Wysocki, Aaron J. and Greenwood, M. Scott and Gentry, Cole and Qualls, A. Louis},

  abstractNote = {},

  doi          = {10.1016/j.anucene.2017.01.003},

  journal      = {Annals of Nuclear Energy (Oxford)},

  number       = C,

  volume       = 103,

  place        = {United Kingdom},

  year         = {2017},

  month        = {5}

}

Copy to clipboard

Journal Article:

Free Publicly Available Full Text

Accepted Manuscript (Publisher)

Publisher's Version of Record
DOI: 10.1016/j.anucene.2017.01.003

Other availability

Search WorldCat to find libraries that may hold this journal

Citation Metrics:

Cited by: 7 works

Citation information provided by
Web of Science

Save / Share:

Export Metadata

Save to My Library

Similar Records in DOE PAGES and OSTI.GOV collections:

Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Core design and safety analysis

Journal Article Brown, Nicholas R. ; Betzler, Benjamin R. ; Carbajo, Juan J. ; ... - Annals of Nuclear Energy (Oxford)

Engineering demonstration reactors are nuclear reactors built to establish proof of concept for technology options that have never been built. Examples of engineering demonstration reactors include Peach Bottom 1 for high temperature gas-cooled reactors (HTGRs) and Experimental Breeder Reactor II (EBR-II) for sodium-cooled fast reactors. Engineering demonstrations have historically played a vital role in advancing the technology readiness level of reactor technologies. This paper details a preconceptual design for a fluoride salt-cooled engineering demonstration reactor. The fluoride salt-cooled high-temperature reactor (FHR) demonstration reactor (DR) is a concept for a salt-cooled reactor with 100 megawatts of thermal output (MWt). It wouldmore »« less
DOI: 10.1016/j.anucene.2017.01.003
Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Motivation and overview

Journal Article Qualls, A. Louis ; Betzler, Benjamin R. ; Brown, Nicholas R. ; ... - Annals of Nuclear Energy (Oxford)
Cited by 1
DOI: 10.1016/j.anucene.2016.11.021
Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Motivation and overview

Journal Article Qualls, A. Louis ; Betzler, Benjamin R. ; Brown, Nicholas R. ; ... - Annals of Nuclear Energy (Oxford)

Engineering demonstration reactors are nuclear reactors built to establish proof of concept for technology options that have never been built. Examples of engineering demonstration reactors include Peach Bottom 1 for high temperature gas-cooled reactors (HTGRs) and Experimental Breeder Reactor-II (EBR-II) for sodium-cooled fast reactors. Historically, engineering demonstrations have played a vital role in advancing the technology readiness level of reactor technologies. Our paper details a preconceptual design for a fluoride salt-cooled engineering demonstration reactor. The fluoride salt-cooled high-temperature reactor (FHR) demonstration reactor (DR) is a concept for a salt-cooled reactor with 100 megawatts of thermal output (MWt). It would usemore »« less
DOI: 10.1016/j.anucene.2016.11.021

Full Text Available
Core Design Characteristics of the Fluoride Salt-Cooled High Temperature Demonstration Reactor

Conference Brown, Nicholas ; Qualls, A L. ; Betzler, Benjamin R. ; ...

Fluoride salt-cooled high temperature reactors (FHRs) are a promising reactor technology option with significant knowledge gaps to implementation. One potential approach to address those technology gaps is via a small-scale demonstration reactor with the goal of increasing the technology readiness level (TRL) of the overall system for the longer term. The objective of this paper is to outline a notional concept for such a system, and to address how the proposed concept would advance the TRL of FHR concepts.Development of the proposed FHR Demonstration Reactor (DR) will enable commercial FHR deployment through disruptive and rapid technology development and demonstration. Themore »« less
Preliminary Demonstration Reactor Point Design for the Fluoride Salt-Cooled High-Temperature Reactor

Technical Report Qualls, A. L. ; Betzler, Benjamin R. ; Brown, Nicholas R. ; ...

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. Thismore »« less
DOI: 10.2172/1234355

Full Text Available

Similar Records