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Title: Neutronic Evaluation of a Liquid Salt–Cooled Reactor Assembly

Abstract

This study presents a thorough parametric neutronic analysis of a plate-based tristructual isotropic (TRISO) fuel particle bearing liquid salt–cooled reactor assembly. The analyses presented investigated the effects of altering fuel enrichment, packing fraction, plate region thicknesses, assembly structure thicknesses, assembly size, numbers of plates per assembly, use of burnable poison materials, replacement of assembly and plate carbon material with silicon carbide, and use of uranium nitride fuel kernels. The effects or trends observed included reactivity behavior, discharge burnup, cycle length, and other key design parameters such as moderator temperature coefficients, coolant density coefficients, control blade worth, and impacts upon power peaking (i.e., power and flux distributions).

Authors:
ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [2]
  1. University of Tennessee–Knoxville, Department of Nuclear Engineering, Knoxville, Tennessee 37996-2300
  2. Georgia Institute of Technology, Nuclear and Radiological Engineering, Atlanta, Georgia 30332-0745
Publication Date:
Research Org.:
UT-Battelle LLC/ORNL, Oak Ridge, TN (Unted States); Oak Ridge National Laboratory, Oak Ridge Leadership Computing Facility (OLCF)
Sponsoring Org.:
USDOE Office of Science (SC)
OSTI Identifier:
1565596
DOE Contract Number:  
AC05-00OR22725; AC07-05ID14517
Resource Type:
Journal Article
Journal Name:
Nuclear Science and Engineering
Additional Journal Information:
Journal Volume: 187; Journal Issue: 2; Journal ID: ISSN 0029-5639
Publisher:
American Nuclear Society - Taylor & Francis
Country of Publication:
United States
Language:
English
Subject:
Nuclear Science & Technology

Citation Formats

Gentry, Cole, Maldonado, G. Ivan, Chvala, Ondrej, and Petrovic, Bojan. Neutronic Evaluation of a Liquid Salt–Cooled Reactor Assembly. United States: N. p., 2017. Web. doi:10.1080/00295639.2017.1312931.
Gentry, Cole, Maldonado, G. Ivan, Chvala, Ondrej, & Petrovic, Bojan. Neutronic Evaluation of a Liquid Salt–Cooled Reactor Assembly. United States. doi:10.1080/00295639.2017.1312931.
Gentry, Cole, Maldonado, G. Ivan, Chvala, Ondrej, and Petrovic, Bojan. Wed . "Neutronic Evaluation of a Liquid Salt–Cooled Reactor Assembly". United States. doi:10.1080/00295639.2017.1312931.
@article{osti_1565596,
title = {Neutronic Evaluation of a Liquid Salt–Cooled Reactor Assembly},
author = {Gentry, Cole and Maldonado, G. Ivan and Chvala, Ondrej and Petrovic, Bojan},
abstractNote = {This study presents a thorough parametric neutronic analysis of a plate-based tristructual isotropic (TRISO) fuel particle bearing liquid salt–cooled reactor assembly. The analyses presented investigated the effects of altering fuel enrichment, packing fraction, plate region thicknesses, assembly structure thicknesses, assembly size, numbers of plates per assembly, use of burnable poison materials, replacement of assembly and plate carbon material with silicon carbide, and use of uranium nitride fuel kernels. The effects or trends observed included reactivity behavior, discharge burnup, cycle length, and other key design parameters such as moderator temperature coefficients, coolant density coefficients, control blade worth, and impacts upon power peaking (i.e., power and flux distributions).},
doi = {10.1080/00295639.2017.1312931},
journal = {Nuclear Science and Engineering},
issn = {0029-5639},
number = 2,
volume = 187,
place = {United States},
year = {2017},
month = {5}
}

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Selection and evaluation of potential burnable absorbers incorporated into modified TRISO particles
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Alternative configurations for the QUADRISO fuel design concept
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