Article ID Journal Published Year Pages File Type
11001916 Fusion Engineering and Design 2018 11 Pages PDF
Abstract
The system-level code GETTHEM is applied to the thermal-hydraulic analysis of an entire segment of the Water-Cooled Lithium-Lead (WCLL) First Wall (FW) of the EU DEMO reactor, parametrically varying the heat load of the FW and the coolant mass flow rate. The results show that the WCLL FW design can tolerate variations of the distribution of the heat flux with respect to the design value, without requiring modifications. The top inboard and the bottom outboard regions are identified as most critical from the point of view of the cooling of the FW. Finally, the largest possible extent of the WCLL FW surface where the peak heat load can be safely applied is identified through a parametric analysis, performed on the critical regions, to understand which is the limit of the cooling capacity of the system.
Related Topics
Physical Sciences and Engineering Energy Energy Engineering and Power Technology
Authors
, , , , ,