CEFR事故余热排放系统优化设计
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摘要
为提高快堆管道设计的经济性,根据支吊架优化原则,对事故余热排放系统进行优化设计,使管道系统在各种预期的载荷工况下,都能满足ASME设计规范规定的应力限值,并减少阻尼器、弹簧支吊架的使用量。通过对CEFR的事故余热排放系统的优化设计,积累了高温管道支吊架的布置经验,为以后快堆的管道设计打下基础。
Background: China experimental fast reactor(CEFR) is the first fast reactor in China,the piping designs are very important for the fast reactor.Purpose: The purpose is to improve the economy of pipeline design for the fast reactor.Methods: According to the optimization principles,redesign the support system of emergency decay heat removal system.Results: The piping of emergency decay heat removal system meets the ASME standard stress limit value under various prospective loads,and reduces the number of dampers,spring hangers.Conclusions: We accumulate layout experience for the support design of high temperature piping by the optimization design for emergency decay heat removal system,lay the foundation for the fast reactor piping design in the future.
Background: China experimental fast reactor(CEFR) is the first fast reactor in China,the piping designs are very important for the fast reactor.Purpose: The purpose is to improve the economy of pipeline design for the fast reactor.Methods: According to the optimization principles,redesign the support system of emergency decay heat removal system.Results: The piping of emergency decay heat removal system meets the ASME standard stress limit value under various prospective loads,and reduces the number of dampers,spring hangers.Conclusions: We accumulate layout experience for the support design of high temperature piping by the optimization design for emergency decay heat removal system,lay the foundation for the fast reactor piping design in the future.
引文
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4 DL/T616-2006,火力发电厂汽水管道与支吊架维修调整导则[S]DL/T616-2006,Maintenance&adjusting guide for thermal power plant Steam-water piping and support-hangers[S]
5唐永进.压力管道应力分析[M].北京:中国石化出版社,2009 TANG Yongjin.Stress analysis of pressure pipelines[M].Beijing:China Petrochemical Press,2009
2美国机械工程师学会.核设备1995年规范案例[S].美国国家标准ACI标准359-95,1995 American Society of Mechanical Engineers.Nuclear components code cases 1995[S].ANSI,1995
3国家地震局.核电厂抗震设计规范GB50267-97[S].中国计划出版社,1998 National Earthquake Bureau.Code for seismic design of nuclear power plants GB50267-97[S].China Planning Press,1998
4 DL/T616-2006,火力发电厂汽水管道与支吊架维修调整导则[S]DL/T616-2006,Maintenance&adjusting guide for thermal power plant Steam-water piping and support-hangers[S]
5唐永进.压力管道应力分析[M].北京:中国石化出版社,2009 TANG Yongjin.Stress analysis of pressure pipelines[M].Beijing:China Petrochemical Press,2009
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