科技报告详细信息
High-Temperature Gas-Cooled Test Reactor Point Design | |
Sterbentz, James William1  Bayless, Paul David1  Nelson, Lee Orville1  Gougar, Hans David1  Kinsey, James Carl1  Strydom, Gerhard1  Kumar, Akansha1  | |
[1]Idaho National Laboratory | |
关键词: design; gas-cooled; high-temperature; test reactor; | |
DOI : 10.2172/1261012 RP-ID : INL/EXT--16-38296 PID : OSTI ID: 1261012 |
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美国|英语 | |
来源: SciTech Connect | |
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【 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 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.【 预 览 】
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