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High heat flux limits of the fusion reactor water-cooled first wall
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SYSNO 0519145 Title High heat flux limits of the fusion reactor water-cooled first wall Author(s) Zacha, P. (CZ)
Entler, Slavomír (UFP-V) [TOK] ORCIDSource Title Nuclear Engineering and Technology. Roč. 51, č. 5 (2019), s. 1251-1260. - : Korean Nuclear Society Document Type Článek v odborném periodiku Institutional support UFP-V - RVO:61389021 Language eng Country KR Keywords friction factor characteristics * helical screw-tape * turbulent-flow * enhancement * design * High heat flux * Thermal performance factors * Turbulator promoters * First wall * Cooling * cfd URL https://www.sciencedirect.com/science/article/pii/S1738573318304182?via%3Dihub Permanent Link http://hdl.handle.net/11104/0304179
Number of the records: 1