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Title: High Temperature Gas-Cooled Test Reactor Point Design: Summary Report

Abstract

A point design has been developed for a 200-MW high-temperature gas-cooled test reactor. The point design concept uses standard prismatic blocks and 15.5% enriched uranium oxycarbide fuel. Reactor physics and thermal-hydraulics simulations have been performed to characterize the capabilities of the design. In addition to the technical data, overviews are provided on the technology readiness level, licensing approach, and costs of the test reactor point design.

Authors:
 [1];  [1];  [1];  [1];  [1];  [1]
  1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1260453
Report Number(s):
INL/EXT-16-37661 (Revision 1)
INL/EXT-16-37661 (Revision 1); TRN: US1601548
DOE Contract Number:  
AC07-05ID14517
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; HTGR TYPE REACTORS; TEST REACTORS; TEMPERATURE RANGE 1000-4000 K; MODERATELY ENRICHED URANIUM; DESIGN; THERMAL HYDRAULICS; REACTOR PHYSICS; COST; NUCLEAR FUELS; OXYCARBIDES; LICENSING; SIMULATION; POWER RANGE 100-1000 MW; URANIUM COMPOUNDS; ART; High Temperature Gas-Cooled; permanent side reflector; TDO; UCO

Citation Formats

Sterbentz, James William, Bayless, Paul David, Nelson, Lee Orville, Gougar, Hans David, Kinsey, J., and Strydom, Gerhard. High Temperature Gas-Cooled Test Reactor Point Design: Summary Report. United States: N. p., 2016. Web. doi:10.2172/1260453.
Sterbentz, James William, Bayless, Paul David, Nelson, Lee Orville, Gougar, Hans David, Kinsey, J., & Strydom, Gerhard. High Temperature Gas-Cooled Test Reactor Point Design: Summary Report. United States. https://doi.org/10.2172/1260453
Sterbentz, James William, Bayless, Paul David, Nelson, Lee Orville, Gougar, Hans David, Kinsey, J., and Strydom, Gerhard. 2016. "High Temperature Gas-Cooled Test Reactor Point Design: Summary Report". United States. https://doi.org/10.2172/1260453. https://www.osti.gov/servlets/purl/1260453.
@article{osti_1260453,
title = {High Temperature Gas-Cooled Test Reactor Point Design: Summary Report},
author = {Sterbentz, James William and Bayless, Paul David and Nelson, Lee Orville and Gougar, Hans David and Kinsey, J. and Strydom, Gerhard},
abstractNote = {A point design has been developed for a 200-MW high-temperature gas-cooled test reactor. The point design concept uses standard prismatic blocks and 15.5% enriched uranium oxycarbide fuel. Reactor physics and thermal-hydraulics simulations have been performed to characterize the capabilities of the design. In addition to the technical data, overviews are provided on the technology readiness level, licensing approach, and costs of the test reactor point design.},
doi = {10.2172/1260453},
url = {https://www.osti.gov/biblio/1260453}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Mar 01 00:00:00 EST 2016},
month = {Tue Mar 01 00:00:00 EST 2016}
}