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

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 UCO 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 technological readiness level, licensing approach and costs.

Authors:
 [1];  [1];  [1];  [1];  [1];  [1];  [1]
  1. Idaho National Laboratory
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1261012
Report Number(s):
INL/EXT-16-38296
DOE Contract Number:  
AC07-05ID14517
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; design; gas-cooled; high-temperature; test reactor

Citation Formats

Sterbentz, James William, Bayless, Paul David, Nelson, Lee Orville, Gougar, Hans David, Kinsey, James Carl, Strydom, Gerhard, and Kumar, Akansha. High-Temperature Gas-Cooled Test Reactor Point Design. United States: N. p., 2016. Web. doi:10.2172/1261012.
Sterbentz, James William, Bayless, Paul David, Nelson, Lee Orville, Gougar, Hans David, Kinsey, James Carl, Strydom, Gerhard, & Kumar, Akansha. High-Temperature Gas-Cooled Test Reactor Point Design. United States. https://doi.org/10.2172/1261012
Sterbentz, James William, Bayless, Paul David, Nelson, Lee Orville, Gougar, Hans David, Kinsey, James Carl, Strydom, Gerhard, and Kumar, Akansha. 2016. "High-Temperature Gas-Cooled Test Reactor Point Design". United States. https://doi.org/10.2172/1261012. https://www.osti.gov/servlets/purl/1261012.
@article{osti_1261012,
title = {High-Temperature Gas-Cooled Test Reactor Point Design},
author = {Sterbentz, James William and Bayless, Paul David and Nelson, Lee Orville and Gougar, Hans David and Kinsey, James Carl and Strydom, Gerhard and Kumar, Akansha},
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 UCO 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 technological readiness level, licensing approach and costs.},
doi = {10.2172/1261012},
url = {https://www.osti.gov/biblio/1261012}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Apr 01 00:00:00 EDT 2016},
month = {Fri Apr 01 00:00:00 EDT 2016}
}