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- W2342000115 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 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." @default.
- W2342000115 created "2016-06-24" @default.
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- W2342000115 date "2016-03-01" @default.
- W2342000115 modified "2023-10-11" @default.
- W2342000115 title "High Temperature Gas-Cooled Test Reactor Point Design: Summary Report" @default.
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- W2342000115 doi "https://doi.org/10.2172/1260453" @default.
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