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:
-
- 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}
}
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