Preliminary investigation on the primary heat exchanger lower head rupture accident of forced circulation LBE-cooled fast reactor

被引:26
作者
Gu, Zhixing [1 ,2 ]
Wang, Gang [1 ]
Bai, Yunqing [1 ]
Song, Yong [1 ]
Zhao, Zhumin [1 ]
机构
[1] Chinese Acad Sci, Inst Nucl Energy Safety Technol, Key Lab Neutron & Radiat Safety, Hefei 230031, Anhui, Peoples R China
[2] Univ Sci & Technol China, Hefei 230027, Anhui, Peoples R China
关键词
LBE-cooled fast reactor; HXLHR; NTC; Vapor; Safety analysis; CONCEPTUAL DESIGN; WATER INTERACTION; GENERATION; NEUTRONICS; BLANKET; SYSTEM; MODULE;
D O I
10.1016/j.anucene.2015.03.018
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 problem about the interaction between heavy liquid metal and water is one of the grand challenges in the development of lead or Lead-Bismuth Eutectic (LBE) cooled fast reactor. In this paper, the primary heat exchanger lower head rupture (HXLHR) accident of a forced circulation LBE-cooled fast reactor was simulated with a transient analysis code NTC (Neutronics and Thermal-hydraulics Coupled transient analysis program). The simulation results showed that the water in primary heat exchanger was injected into the primary circuit and vaporized immediately. Then the main vessel was pressurized and the maximum pressure was about 27 bar compared with 0.5 bar in normal condition. During the accident, some of the generated vapors were dragged into the core by LBE, which may cause a reactivity insertion accident. If any positive void coefficient exists in the core, a further study on the HXLHR accident should be performed to evaluate the reactivity insertion accident. (C)2015 Elsevier Ltd. All rights reserved.
引用
收藏
页码:84 / 90
页数:7
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