High heat flux limits of the fusion reactor water-cooled first wall

0519145 - ÚFP 2020 RIV KR eng J - Článek v odborném periodiku
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
Institucionální podpora: RVO:61389021
Klíčová slova: friction factor characteristics * helical screw-tape * turbulent-flow * enhancement * design * High heat flux * Thermal performance factors * Turbulator promoters * First wall * Cooling * cfd
Obor OECD: Nuclear physics
Impakt faktor: 1.846, rok: 2019
Způsob publikování: Omezený přístup
https://www.sciencedirect.com/science/article/pii/S1738573318304182?via%3Dihub

The water-cooled WCLL blanket is one of the possible candidates for the blanket of the fusion power reactors. The plasma-facing first wall manufactured from the reduced-activation ferritic-martensitic steel Eurofer97 will be cooled with water at a typical pressurized water reactor (PWR) conditions. According to new estimates, the first wall will be exposed to peak heat fluxes up to 7 MW/m(2) while the maximum operated temperature of Eurofer97 is set to 550 degrees C. The performed analysis shows the capability of the designed flat first wall concept to remove heat flux without exceeding the maximum Eurofer97 operating temperature only up to 0.75 MW/m(2). Several heat transfer enhancement methods (turbulator promoters), structural modifications, and variations of parameters were analysed. The effects of particular modifications on the wall temperature were evaluated using thermo-hydraulic three-dimensional numerical simulation. The analysis shows the negligible effect of the turbulators. By the combination of the proposed modifications, the permitted heat flux was increased up to 1.69 MW/m(2) only. The results indicate the necessity of the re-evaluation of the existing first wall concepts.
Trvalý link: http://hdl.handle.net/11104/0304179