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Nuclear Technology Volume 209, 2023 - Issue 10: Selected papers from the 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19)
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Research Articles

High-Fidelity Modeling and Experiments to Inform Safety Analysis Codes for Heat Pipe Microreactors

Carolina da Silva Bourdot Dutraa Pennsylvania State University, Ken and Mary Alice Lindquist Department of Nuclear Engineering, 205 Hallowell Building, University Park, Pennsylvania16802Correspondence[email protected]
ORCID Iconhttps://orcid.org/0000-0002-8020-3363View further author information
ORCID Icon,
Elia Merzaria Pennsylvania State University, Ken and Mary Alice Lindquist Department of Nuclear Engineering, 205 Hallowell Building, University Park, Pennsylvania16802;b Argonne National Laboratory, Nuclear Science and Engineering Division, 9700 S. Cass Avenue, Lemont, Illinois60439View further author information
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John Aciernoa Pennsylvania State University, Ken and Mary Alice Lindquist Department of Nuclear Engineering, 205 Hallowell Building, University Park, Pennsylvania16802View further author information
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Adam Krausa Pennsylvania State University, Ken and Mary Alice Lindquist Department of Nuclear Engineering, 205 Hallowell Building, University Park, Pennsylvania16802View further author information
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Annalisa Manerac University of Michigan, Department of Nuclear Engineering & Radiological Sciences, 2355 Bonisteel Boulevard, Ann Arbor, Michigan48109;d ETH Zurich, Department of Mechanical and Process Engineering, Sonneggstrasse 3, 8092, Zurich, Switzerland;e Paul Scherrer Institute, Laboratory for Reactor Physics and Thermal-Hydraulics (LRT), 5232Villigen PSI, SwitzerlandView further author information
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Victor Petrovc University of Michigan, Department of Nuclear Engineering & Radiological Sciences, 2355 Bonisteel Boulevard, Ann Arbor, Michigan48109;d ETH Zurich, Department of Mechanical and Process Engineering, Sonneggstrasse 3, 8092, Zurich, Switzerland;e Paul Scherrer Institute, Laboratory for Reactor Physics and Thermal-Hydraulics (LRT), 5232Villigen PSI, SwitzerlandView further author information
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Taehwan Ahnc University of Michigan, Department of Nuclear Engineering & Radiological Sciences, 2355 Bonisteel Boulevard, Ann Arbor, Michigan48109View further author information
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Pei-Hsun Huangc University of Michigan, Department of Nuclear Engineering & Radiological Sciences, 2355 Bonisteel Boulevard, Ann Arbor, Michigan48109View further author information
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Dillon Shaverb Argonne National Laboratory, Nuclear Science and Engineering Division, 9700 S. Cass Avenue, Lemont, Illinois60439View further author information
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Pages 1592-1616 | Received 01 Aug 2022, Accepted 10 Feb 2023, Published online: 17 Apr 2023

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