Parametric thermal-hydraulic analysis of the EU DEMO Water-Cooled Lithium-Lead First Wall using the GETTHEM code

被引:6
|
作者
Froio, A. [1 ]
Del Nevo, A. [2 ]
Martelli, E. [2 ,3 ]
Savoldi, L. [1 ]
Zanino, R. [1 ]
机构
[1] Politecn Torino, NEMO Grp, Dipartimento Energia, I-10129 Turin, Italy
[2] ENEA CR Brasimone, I-40032 Camugnano, BO, Italy
[3] Univ Roma La Sapienza, I-00185 Rome, Italy
关键词
Nuclear fusion; EU DEMO; Breeding blanket; WCLL; First Wall; Thermal-hydraulics; Modelling; WCLL BREEDING BLANKET;
D O I
10.1016/j.fusengdes.2018.10.003
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
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.
引用
收藏
页码:257 / 267
页数:11
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