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Nuclear Science and Engineering Volume 187, 2017 - Issue 2
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Technical Papers

Neutronic Evaluation of a Liquid Salt–Cooled Reactor Assembly

Cole GentryUniversity of Tennessee–Knoxville, Department of Nuclear Engineering, Knoxville, Tennessee37996-2300ORCID Iconhttp://orcid.org/0000-0002-3773-0707
ORCID Icon,
G. Ivan MaldonadoUniversity of Tennessee–Knoxville, Department of Nuclear Engineering, Knoxville, Tennessee37996-2300Correspondence[email protected]
ORCID Iconhttp://orcid.org/0000-0001-7377-4494
ORCID Icon,
Ondrej ChvalaUniversity of Tennessee–Knoxville, Department of Nuclear Engineering, Knoxville, Tennessee37996-2300ORCID Iconhttp://orcid.org/0000-0003-4614-6649
ORCID Icon &
Bojan PetrovicGeorgia Institute of Technology, Nuclear and Radiological Engineering, Atlanta, Georgia30332-0745ORCID Iconhttp://orcid.org/0000-0001-9217-7863
ORCID Icon
Pages 166-184 | Received 09 Dec 2014, Accepted 25 Mar 2017, Published online: 09 Jun 2017

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Read on this site (2)

Blair P. Bromley. (2022) Initial Exploratory Reactor Physics Assessment of Nonconventional Fuel Concepts for Very Compact Small Modular Reactors Using Hydroxides as Coolants and/or Moderators. Nuclear Technology 208:1, pages 160-191.
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Cole Gentry, Kang Seog Kim & G. Ivan Maldonado. (2018) Two-Step Procedure for Liquid-Salt-Cooled-Reactor Analysis. Nuclear Technology 204:3, pages 299-317.
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Articles from other publishers (5)

Vitesh Krishna, Ching Hiong Yap & Sicong Xiao. (2020) Assembly design of a fluoride salt-cooled high temperature commercial-scale reactor: Neutronics evaluation and parametric analysis. Annals of Nuclear Energy 141, pages 107288.
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P. Avigni & B. Petrovic. (2020) Thermal hydraulics modeling of On-line refueling for the Advanced High Temperature Reactor (AHTR). Nuclear Engineering and Design 358, pages 110440.
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P. Avigni & B. Petrovic. (2018) On-line refueling for the Advanced High Temperature Reactor (AHTR). Nuclear Engineering and Design 340, pages 166-182.
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L. Michael Huang & Bojan Petrovic. (2018) Development of methodology for efficient fuel design evaluation of the Advanced High Temperature Reactor (AHTR). Annals of Nuclear Energy 121, pages 646-660.
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Kyle M. Ramey & Bojan Petrovic. (2018) Monte Carlo modeling and simulations of AHTR fuel assembly to support V&V of FHR core physics methods. Annals of Nuclear Energy 118, pages 272-282.
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