Ex-Core Thermofluidic Optimization for Transformational Challenge Reactor
Author:
Affiliation:
1. Argonne National Laboratory, Nuclear Science and Engineering Division, 9700 South Cass Avenue, Lemont, Illinois 60439
2. Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, Tennessee 37831-6170
Funder
U.S. Department of Energy
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.1080/00295639.2022.2123195
Reference11 articles.
1. CAST3M/ARCTURUS: A coupled heat transfer CFD code for thermal–hydraulic analyzes of gas cooled reactors
2. Development of safety analysis codes and experimental validation for a very high temperature gas-cooled reactor Final report
3. J. BUSBY et al. “Technologies to Reactors: Enabling Accelerated Deployment of Nuclear Energy Systems,” ORNL/SPR-2018/1025, Oak Ridge National Laboratory (2018).
4. B. R. BETZLER et al. “Transformational Challenge Reactor Preliminary Core Design Report,” ORNL/TM-2020/1718, Oak Ridge National Laboratory (2020).
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