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

Sterbentz, James William¹  Bayless, Paul David¹  Nelson, Lee Orville¹  Gougar, Hans David¹  Kinsey, J.¹  Strydom, Gerhard¹ 

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

关键词: 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 100-10;   

DOI  :  10.2172/1260453
RP-ID  :  INL/EXT--16-37661
PID  :  OSTI ID: 1260453
Others  :  TRN: US1601548

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来源: SciTech Connect

【 摘 要 】

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.