重大事故早期血管内注射的可行性分析与论证

Shaoxiong Xia, D. Zhan, Zijie Wu, Xinhai Zhao, Yiqun Yu
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引用次数: 0

摘要

核反应堆发生严重事故时,堆芯会发生熔毁,破坏反应堆压力容器和安全壳的完整性,向环境释放放射性物质。第三代压水堆配备了严重事故缓解系统,以防止高温(3000K)堆芯熔化通过反应堆压力容器。严重事故缓解系统主要包括:一次降压系统、堆坑注水系统、安全壳可燃物系统、安全壳排热系统等。得益于这些系统,大释放频率(LRF)被限制在一个较低的水平。然而,这些系统无法阻止堆芯退化的过程。如果发生严重事故,堆芯将熔化,整个反应堆无法再使用,造成不可逆转的经济损失。为了提高核电站的经济性和安全性,本文提出了在严重事故早期采用船内注入(IVI)的措施,并验证了该措施的有效性。分析认为,在严重事故发生初期进行容器内注入,可以防止严重事故发生时堆芯的大规模熔化,大大降低氢源物品的风险。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Feasibility Analysis and Demonstration of In-Vessel-Injection in the Early Stage of Severe Accident
The core of the nuclear reactor will melt during severe accidents, which may damage the integrity of the reactor pressure vessel and containment, and release radioactive materials to the environment. The third-generation pressurized water reactor is equipped with severe accident mitigation systems to prevent the high temperature (3000K) corium from melting through the reactor pressure vessel. The severe accident mitigation system mainly includes: primary depressurization system, reactor pit flooding system, containment combustible system, containment heat removal system, etc.. Benefit from these systems, large release frequency (LRF) is restricted to a low level. However, these systems cannot stop the process of core degradation. If severe accident happens, the core will melt and the whole reactor cannot be reused again, causing irreversible economic losses. In order to improve the economy and safety of nuclear power plants, this paper proposes in-vessel-injection (IVI) in the early stage of severe accident, and proves the effectiveness of this measure. According to the analysis, in-vessel-injection in the early stage of severe accident can prevent the large-scale melting of the core during severe accident, and the risk of hydrogen and source items will be greatly reduced.
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