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0519145 - ÚFP 2020 RIV KR eng J - Journal Article
Zacha, P. - Entler, Slavomír
High heat flux limits of the fusion reactor water-cooled first wall.
Nuclear Engineering and Technology. Roč. 51, č. 5 (2019), s. 1251-1260. ISSN 1738-5733. E-ISSN 1738-5733
Institutional support: RVO:61389021
Keywords : friction factor characteristics * helical screw-tape * turbulent-flow * enhancement * design * High heat flux * Thermal performance factors * Turbulator promoters * First wall * Cooling * cfd
OECD category: Nuclear physics
Impact factor: 1.846, year: 2019
Method of publishing: Limited access
https://www.sciencedirect.com/science/article/pii/S1738573318304182?via%3Dihub
Permanent Link: http://hdl.handle.net/11104/0304179