史国宝¹, 郑明光¹, 张琨¹(), 匡波², 刘鹏飞²

1.上海核工程研究设计院有限公司,上海 200233
2.上海交通大学 机械与动力工程学院,上海 200240

收稿日期:2020-11-26出版日期:2022-01-28发布日期:2022-01-21
通讯作者:张琨E-mail:zhangkun@snerdi.com.cn
作者简介:史国宝(1965-),男,浙江省宁波市人,研究员级高级工程师,主要从事核电厂总体设计和安全分析.
基金资助:国家科技重大专项资助项目(2018ZX06002004)

Test of Critical Heat Flux on Outer Surface of CAP1400 Pressurized Reactor Vessel

SHI Guobao¹, ZHENG Mingguang¹, ZHANG Kun¹(), KUANG Bo², LIU Pengfei²

1. Shanghai Nuclear Engineering Research and Design Institute Co., Ltd., Shanghai 200233, China
2. School of Mechanical Engineering, Shanghai Jiao Tong University, Shanghai 200240, China

Received:2020-11-26Online:2022-01-28Published:2022-01-21
Contact:ZHANG Kun E-mail:zhangkun@snerdi.com.cn

摘要/Abstract

摘要： 根据模化原则建立了全高度切片型试验台架,采用爆炸焊技术研制了加热段,表面碳钢薄层可以真实模拟压力容器表面特性,开展了流道、压力、过冷度、流体水化学、表面状态等关键因素对压力容器外壁面临界热通量影响试验研究,获得了CAP1400压力容器外壁面传热极限规律,验证了熔融物堆内滞留措施中压力容器外流动和传热过程.
关键词: 压力容器外壁面, 临界热通量试验, 熔融物堆内滞留
Abstract: A full height sliced test facility is established based on the modeling process. The heating test section is manufactured by adopting the explosive welding technology, and the surface of carbon steel can simulate the actual surface characteristic of a pressurized reactor. Critical heat flux tests on flow, pressure, subcooling degree, chemical material in water, and surface characteristics are performed on the outer surface of the pressurized reactor vessel. Therefore, the law of heat transfer limit on the outer surface of the CAP1400 pressurized reactor vessel is obtained, and the process of flow and heat transfer for in-vessel retention is validated.
Key words: outer surface of pressurized reactor vessel, critical heat flux test, in-vessel retention


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