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

Technical Report · Tue Mar 01 00:00:00 EST 2016

DOI:https://doi.org/10.2172/1260453· OSTI ID:1260453

Sterbentz, James William ^[1]; Bayless, Paul David ^[1]; Nelson, Lee Orville ^[1]; Gougar, Hans David ^[1]; Kinsey, J. ^[1]; Strydom, Gerhard ^[1]

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1. Idaho National Lab. (INL), Idaho Falls, ID (United States)

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.

• Research Organization: Idaho National Lab. (INL), Idaho Falls, ID (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE)
• DOE Contract Number: AC07-05ID14517
• OSTI ID: 1260453
• Report Number(s): INL/EXT-16-37661 (Revision 1); INL/EXT-16-37661 (Revision 1); TRN: US1601548
• Country of Publication: United States
• Language: English

Related Subjects

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