Fluoride-Salt-Cooled High-Temperature Test Reactor Thermal-Hydraulic Licensing and Uncertainty Propagation Analysis

Romatoski, R. R.; Hu, L. W.

doi:10.1080/00295450.2019.1610686

Title: Fluoride-Salt-Cooled High-Temperature Test Reactor Thermal-Hydraulic Licensing and Uncertainty Propagation Analysis

Journal Article · Wed Jun 05 00:00:00 EDT 2019 · Nuclear Technology

DOI:https://doi.org/10.1080/00295450.2019.1610686· OSTI ID:1848128

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Massachusetts Institute of Technology, Nuclear Engineering Department, 77 Massachusetts Avenue, Cambridge, Massachusetts 02139; St. Ambrose University, Engineering and Physics Department, 518 West Locust Street, Davenport, Iowa 52803
Massachusetts Institute of Technology, Nuclear Engineering Department, 77 Massachusetts Avenue, Cambridge, Massachusetts 02139; Massachusetts Institute of Technology, Nuclear Reactor Laboratory, 77 Massachusetts Avenue, Cambridge, Massachusetts 02139

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Research Organization:: Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE)

DOE Contract Number:: NE0008285

OSTI ID:: 1848128

Journal Information:: Nuclear Technology, Vol. 205, Issue 11; ISSN 0029-5450

Publisher:: Taylor & Francis - formerly American Nuclear Society (ANS)

Country of Publication:: United States

Language:: English

References (15)

Basis for Fluoride Salt–Cooled High-Temperature Reactors with Nuclear Air-Brayton Combined Cycles and Firebrick Resistance-Heated Energy Storage Forsberg, Charles; Peterson, Per F. Nuclear Technology, Vol. 196, Issue 1 https://doi.org/10.13182/NT16-28	journal	October 2016
Fluoride salt coolant properties for nuclear reactor applications: A review Romatoski, R. R.; Hu, L. W. Annals of Nuclear Energy, Vol. 109 https://doi.org/10.1016/j.anucene.2017.05.036	journal	November 2017
Neutronics modeling and analysis of the TMSR-SF1 fuel lattice and full core with explicit fuel particle distribution and random pebble loadings Sun, Kaichao; Wilson, Jarod; Hauptman, Sara Progress in Nuclear Energy, Vol. 109 https://doi.org/10.1016/j.pnucene.2018.08.005	journal	November 2018
Neutronic Design Features of a Transportable Fluoride-Salt-Cooled High-Temperature Reactor Sun, Kaichao; Hu, Lin-Wen; Forsberg, Charles Journal of Nuclear Engineering and Radiation Science, Vol. 2, Issue 3 https://doi.org/10.1115/1.4032873	journal	June 2016
Assessment of Candidate Molten Salt Coolants for the Advanced High Temperature Reactor (AHTR) Williams, D. F. https://doi.org/10.2172/885975 ORNL/TM-2006/12	report	March 2006
Status of Preconceptual Design of the Advanced High-Temperature Reactor (AHTR) Ingersoll, D. T. https://doi.org/10.2172/861752	report	July 2004
Analysis of the Limiting Safety System Settings of a Fluoride Salt–Cooled High-Temperature Test Reactor Xiao, Yao; Hu, Lin-Wen; Forsberg, Charles Nuclear Technology, Vol. 187, Issue 3 https://doi.org/10.13182/NT13-93	journal	September 2014
Turbulent convective heat transfer with molten salt in a circular pipe Bin, Liu; Yu-ting, Wu; Chong-fang, Ma International Communications in Heat and Mass Transfer, Vol. 36, Issue 9 https://doi.org/10.1016/j.icheatmasstransfer.2009.06.003	journal	November 2009
Convective heat transfer in the laminar–turbulent transition region with molten salt in a circular tube Yu-ting, Wu; Bin, Liu; Chong-fang, Ma Experimental Thermal and Fluid Science, Vol. 33, Issue 7 https://doi.org/10.1016/j.expthermflusci.2009.07.001	journal	October 2009
Investigation on forced convective heat transfer of molten salts in circular tubes Wu, Yu-Ting; Chen, Cong; Liu, Bin International Communications in Heat and Mass Transfer, Vol. 39, Issue 10 https://doi.org/10.1016/j.icheatmasstransfer.2012.09.002	journal	December 2012
Heat transfer and pressure drop characteristics of molten fluoride salt in circular pipe Srivastava, A. K.; Vaidya, A. M.; Maheshwari, N. K. Applied Thermal Engineering, Vol. 61, Issue 2 https://doi.org/10.1016/j.applthermaleng.2013.07.051	journal	November 2013
Computational Fluid Dynamics Analysis for Asymmetric Power Generation in a Prismatic Fuel Block of Fluoride-Salt-Cooled High-Temperature Test Reactor Cheng, Wen-Chi; Sun, Kaichao; Hu, Lin-Wen Journal of Nuclear Engineering and Radiation Science, Vol. 1, Issue 1 https://doi.org/10.1115/1.4026391	journal	January 2015
Thermal-Hydraulic Analyses of Transportable Fluoride Salt–Cooled High-Temperature Reactor with CFD Modeling Wang, Chenglong; Sun, Kaichao; Hu, Lin-Wen Nuclear Technology, Vol. 196, Issue 1 https://doi.org/10.13182/NT15-42	journal	October 2016
Options for Scaled Experiments for High Temperature Liquid Salt and Helium Fluid Mechanics and Convective Heat Transfer Bardet, Philippe M.; Peterson, Per F. Nuclear Technology, Vol. 163, Issue 3 https://doi.org/10.13182/NT163-344	journal	September 2008
Radiation Heat Transfer in the Molten Salt FLiNaK Chaleff, Ethan S.; Blue, Thomas; Sabharwall, Piyush Nuclear Technology, Vol. 196, Issue 1 https://doi.org/10.13182/NT16-52	journal	October 2016

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