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Hypervapotron High Heat Flux Cooling Numerical and Experimental Study
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SYSNO ASEP 0584217 Document Type C - Proceedings Paper (int. conf.) R&D Document Type Conference Paper Title Hypervapotron High Heat Flux Cooling Numerical and Experimental Study Author(s) Smolík, Vojtěch (UFP-V)
Gleitz, M. (CZ)
Entler, Slavomír (UFP-V) ORCID
Zacha, P. (CZ)Number of authors 4 Article number 181 Source Title Proceedings of the 10th International Conference on Fluid Flow, Heat and Mass Transfer. - Orleans : Avestia Publishing, 2023 - ISSN 23693029 - ISBN 978-1-990800-24-5 Pages (2023) Number of pages 6 s. Publication form Online - E Action 10th International Conference on Fluid Flow, Heat and Mass Transfer Event date 07.06.2023 - 09.06.2023 VEvent location Ottawa Country CA - Canada Event type WRD Language eng - English Country CA - Canada Keywords ANSYS Fluent ; hypervapotron ; nuclear fusion ; subcooled boiling ; tokamak Subject RIV JF - Nuclear Energetics OECD category Nuclear physics R&D Projects EF16_019/0000778 GA MŠMT - Ministry of Education, Youth and Sports (MEYS) Institutional support UFP-V - RVO:61389021 EID SCOPUS 85166401282 DOI 10.11159/ffhmt23.181 Annotation High heat flux cooling is one of the leading engineering challenges of the nuclear fusion reactor construction. Plasma facing components (divertor targets and the first wall) of tokamaks are operating under extreme heat load conditions. ITER first wall hypervapotron cooling channel is designed to withstand high heat fluxes up to 7 MW/m2. Water cooled hypervapotron is investigated by CFD simulation in ANSYS Fluent and the results are experimentally validated. Numerical solutions of various CFD codes are also compared to evaluate the ability of each numerical approach to solve subcooled boiling regime. Workplace Institute of Plasma Physics Contact Vladimíra Kebza, kebza@ipp.cas.cz, Tel.: 266 052 975 Year of Publishing 2024 Electronic address https://avestia.com/FFHMT2023_Proceedings/files/paper/FFHMT_181.pdf
Number of the records: 1