Preliminary thermal hydraulic safety analysis of water-cooled ceramic breeder blanket for CFETR

被引:12
|
作者
Cheng, Xiaoman [1 ]
Ma, Xuebin [1 ]
Chen, Youhua [2 ]
Huang, Kai [1 ]
Liu, Songlin [1 ]
机构
[1] Chinese Acad Sci, Inst Plasma Phys, Hefei, Peoples R China
[2] Univ Sci & Technol China, Sch Nucl Sci & Technol, Hefei, Peoples R China
基金
中国国家自然科学基金;
关键词
CFETR; blanket; thermal hydraulics; accident analysis; RELAP5; DESIGN; MODULE; ITER; SYSTEM; TBM;
D O I
10.1080/00223131.2016.1158670
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 Chinese fusion engineering test reactor (CFETR) was expected to bridge from the international thermonuclear experimental reactor (ITER) to the demonstration fusion reactor (DEMO). The water-cooled ceramic breeder (WCCB) blanket is one of the blanket candidates for CFETR. In this paper, preliminary thermal hydraulic safety analyses have been carried out using the system safety analysis code RELAP5 originally developed for light water fission reactors. The pulse operation and three typical loss of coolant accidents (LOCAs), namely, in-vessel LOCA, in-box LOCA, and ex-vessel LOCA, were simulated based on steady-state initialization. Simulation results show that important thermal hydraulic parameters, such as pressure and temperature can meet the design criterion which preliminarily verifies the feasibility of the WCCB blanket from the safety point of view.
引用
收藏
页码:1673 / 1680
页数:8
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