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

Sterbentz, James William¹  Bayless, Paul David¹  Nelson, Lee Orville¹  Gougar, Hans David¹  Strydom, Gerhard¹ 

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

关键词: HTGR TYPE REACTORS;    POWER RANGE 100-1000 MW;    ENRICHED URANIUM REACTORS;    TEST REACTORS;    DESIGN;    OXYCARBIDES;    COMPUTERIZED SIMULATION;    THERMAL HYDRAULICS;    REACTOR PHYSICS;    REACTOR LICENSING;    COST ART;    High Temperature;   

DOI  :  10.2172/1238543
RP-ID  :  INL/EXT--16-37661
PID  :  OSTI ID: 1238543
Others  :  TRN: US1600538

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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.