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DOE OSTI · 1995191

HTGR Validation: NEUP Survey and Database Database Development for HTGR Thermal-Fluid Experiments

Qin, Sunming·Strydom, Gerhard
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Abstract

This set of slides is aimed to improve access to the High-Temperature Gas-cooled Reactor (HTGR) validation data and optimize the return on the significant investment made by DOE. Supported by the Advanced Reactor Technologies (ART) Gas-Cooled Reactor (GCR) program. Slides include information from FY2009 to FY2023, there are in total 35 DOE NEUP projects focusing on the thermal-fluid experiments related with High-Temperature Gas-cooled Reactor (HTGR), producing a large amount of high-quality validation data. NEUP Survey and Database Development for HTGR Thermal-Fluid Experiments is distributed at universities and has not been disseminated to the HTGR community. More collaborating with university PIs and refining the HTGR phenomena summary chart continuously is expected in the future.

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11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS99 GENERAL AND MISCELLANEOUSHigh-Temperature Gas-cooled ReactorHTGRHTGR Thermal-Fluid ExperimentsNuclear Energy University Program (NEUP)

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Qin, Sunming, Strydom, Gerhard. 2023-07-27. HTGR Validation: NEUP Survey and Database Database Development for HTGR Thermal-Fluid Experiments. https://www.osti.gov/biblio/1995191

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