Thermohydraulic responses of a water-cooled tokamak fusion DEMO to loss-of-coolant accidents

被引：17
|
作者：
Nakamura, M. [1 ]
Tobita, K. [1 ]
Someya, Y. [1 ]
Utoh, H. [1 ]
Sakamoto, Y. [1 ]
Gulden, W. [2 ]
机构：
[1] Japan Atom Energy Agcy, Rokkasho 0393212, Japan
[2] Fus Energy, D-85748 Garching, Germany
来源：
NUCLEAR FUSION | 2015年 / 55卷 / 12期
基金：
日本学术振兴会;
关键词：
fusion DEMO; safety; loss-of-coolant accident; thermohydraulics; BROADER APPROACH; SAFETY DESIGN; REACTOR; MELCOR;
D O I：
10.1088/0029-5515/55/12/123008
中图分类号：
O35 [流体力学]; O53 [等离子体物理学];
学科分类号：
070204 ; 080103 ; 080704 ;
摘要：
Major in- and ex-vessel loss-of-coolant accidents (LOCAs) of a water-cooled tokamak fusion DEMO reactor have been analysed. Analyses have identified responses of the DEMO systems to these accidents and pressure loads to confinement barriers for radioactive materials. As for the in-VV LOCA, we analysed the multiple double-ended break of the first wall cooling pipes around the outboard toroidal circumference. As for the ex-VV LOCA, we analysed the doubleended break of the primary cooling pipe. The thermohydraulic analysis results suggest that the in- and ex-vessel LOCAs crucially threaten integrity of the primary and final confinement barriers, respectively. Mitigations of the loads to the confinement barriers are also discussed.
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收藏
页数：7
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