高温气冷堆主蒸汽管道双端断裂危害性分析方法  

Harmfulness analysis method for double ended break in main steam pipe of high temperature gas-cooled reactor

作　　者：祝欣慰[1] 张桂英[1] 邵杰[1] 钱秋裕[1] ZHU Xinwei ZHANG Guiying SHAO Jie QIAN Qiuyu(State Nuclear Electric Power Planning Design ~- Research Institute,Beijing 100095,China)

机构地区：[1]国核电力规划设计研究院,北京100095

出　　处：《热力发电》2016年第12期67-72,83,共7页Thermal Power Generation

基　　金：国家科技重大专项项目(2010ZX06906-005)

摘　　要：高能管道双端断裂危害性分析是核电站常规岛安全设计的关键内容。本文在总结核电站常用管道双端断裂危害性分析方法的基础上,针对高温气冷堆核电站的特点提出:高温气冷堆主蒸汽管道双端断裂破裂点选取可采用应力分析法;喷射力计算可采用简化算法和热工水力学算法;射流形态计算应根据ANSI/ANS—58.2—1988中的计算方法,计算出在不受限破裂和受限的有限分离破裂2种情况下的射流形状;管道动态响应分析可采用有限元模拟算法进行分析;高温气冷堆主蒸汽管道发生双端断裂后的超压、水淹效应应根据具体工程布置情况进行分析。该方法为主蒸汽管道防甩约束件的设计提供了依据。Hazard analysis for high energy piping double ended break is the key content of nuclear power plants conventional island design. On the basis of summarizing the hazard analysis of conventional pipe rup- ture in nuclear power plants, the paper puts forward a set of methods for main steam pipe rupture hazard a- nalysis for high temperature gas-cooled reactor,according to the characteristics of high temperature gas- cooled reactor. It suggests that the stress analysis method be adopted for break point selection,the simpli- fied algorithm and thermal-hydraulics algorithm be employed for spray force calculation, and the method given in the ANSI/ANS--58.2--1988 be used to compute the jet shape under two conditions,the unstinted rupture and confined finite separation rupture. The pipeline＇s dynamic response analysis can be realized u- sing the finite simulation algorithm, and the over-pressure watered out effect after the double ended break occurred on the steam pipeline of the high temperature gas-cooled reaction should be analyzed according to the specific engineering arrangement of the pipelines. This analysis method provides the basis for design of main steam pipe whip restraints for high temperature gas-cooled reactor nuclear power plants.

关 键 词：双端断裂 核电站 高温气冷堆 主蒸汽 应力分析法 喷射力 射流形态 超压、水淹效应 

分 类 号：TL334[核科学技术—核技术及应用]