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

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

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

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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

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                    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.  https://doi.org/10.1016/j.anucene.2017.01.003.

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                    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.  https://doi.org/10.1016/j.anucene.2017.01.003

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                    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.  https://doi.org/10.1016/j.anucene.2017.01.003.

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@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}

}

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

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