An Integrated Experimental Test Facility to Support Development of the Passive Containment Cooling System of HPR1000

Linshan Wei, Shuhong Du, W. Gu, N. Zhang, M. Ding, Zhong-ning Sun, Zhaoming Meng
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Abstract

HPR1000 is an advanced nuclear power plant with the significant feature of an active and passive safety design philosophy, developed by the China National Nuclear Corporation. It is based on the large accumulated knowledge from the design, construction as well as operations experience of nuclear power plants in China. The passive containment cooling system (PCS) of HPR1000 is an important and innovative passive safety system to suppress the pressure in the containment during LOCA. In this paper, the detailed design process of PCS is reviewed, and an integrated experiment facility for the study on the coupling behavior between PCS and thermal hydraulic characteristics in the containment is described, and arrangement of measuring points including temperature, pressure, gas composition and so on are introduced in detailed. Also, the experimental energy released and energy vent to ensure the similarity of containment pressure response, thermal stratification and PCS heat removal is introduced. According to this versatile experiment facility can conduct real-engineering system test which is designed to support the PCS development. In addition, this valuable experience in the design and manufacture of integrated experiment facility can provide important technical support and guidance for the China next generation advanced PWR as well as safety related system.
支持HPR1000被动安全壳冷却系统开发的综合实验测试设施
HPR1000是中国核工业集团公司研制的先进核电站,具有主动式和被动式安全设计理念的显著特点。它是基于在中国核电站的设计、建设和运行经验中积累的大量知识。HPR1000的被动安全壳冷却系统(PCS)是一种重要的创新被动安全系统,用于在失稳过程中抑制安全壳内的压力。本文回顾了PCS的详细设计过程,介绍了用于研究PCS与安全壳内热液特性耦合行为的综合实验装置,并详细介绍了温度、压力、气体成分等测点的布置。此外,还介绍了为保证安全壳压力响应、热分层和PCS排热的相似性而进行的实验能量释放和能量释放。该多功能实验设备可进行实际工程系统测试,是为支持PCS开发而设计的。此外,这一宝贵的综合实验设施设计和制造经验可为中国下一代先进压水堆及安全相关系统提供重要的技术支持和指导。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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