Hypervapotron High Heat Flux Cooling Numerical and Experimental Study

0584217 - ÚFP 2024 RIV CA eng C - Konferenční příspěvek (zahraniční konf.)
Smolík, Vojtěch - Gleitz, M. - Entler, Slavomír - Zacha, P.
Hypervapotron High Heat Flux Cooling Numerical and Experimental Study.
Proceedings of the 10th International Conference on Fluid Flow, Heat and Mass Transfer. Orleans: Avestia Publishing, 2023, (2023), č. článku 181. ISBN 978-1-990800-24-5. ISSN 23693029.
[10th International Conference on Fluid Flow, Heat and Mass Transfer. Ottawa (CA), 07.06.2023-09.06.2023]
Grant CEP: GA MŠMT EF16_019/0000778
Grant ostatní: AV ČR(CZ) StrategieAV21/27
Program: StrategieAV
Institucionální podpora: RVO:61389021
Klíčová slova: ANSYS Fluent * hypervapotron * nuclear fusion * subcooled boiling * tokamak
Obor OECD: Nuclear physics
https://avestia.com/FFHMT2023_Proceedings/files/paper/FFHMT_181.pdf

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.
Trvalý link: https://hdl.handle.net/11104/0352183