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压水堆核电厂主设备力学分析和研究:从设计到寿命管理

Structural mechanics research and development for main components of Chinese 300 Mwe PWR NPPs:from design to life management

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【作者】 姚伟达贺寅彪窦一康谢永诚张明梁星筠

【Author】 YAO Wei-da,HE Yin-biao,DOU Yi-kang,XIE Yong-cheng, ZHANG Ming,LIANG Xing-yun (Shanghai Nuclear Engineering Research and Design Institute,Shanghai 200233,China)

【机构】 上海核工程研究设计院

【摘要】 秦山核电厂(1秦山一期)是中国第一座自行设计、建造和运行管理的300MWe压水堆核电厂。上海核工程研究设计院作为秦山核电厂的总体设计单位,于20世纪70年代初开展大量设计、研究和开发工作,解决设计、建造和运行中遇到的各类工程问题,其中反应堆结构力学是确保核电厂主设备安全可靠运行重要的预测与仿真手段之一。概要地介绍反应堆结构力学在核电厂设计、建造、调试和运行等不同阶段,在设备的安全性和可靠性评估及老化、寿命评估方面所扮演的角色。主要内容涵盖核蒸汽供应系统主设备的分析法设计、安全分析相关的力学问题、承压设备的一些特殊问题(快速断裂的防止、密封分析及试验验证等)、流致振动的试验研究、设备的抗震鉴定、设备的失效诊断及原因分析、振动鉴定和诊断技术、承压设备的在线监测技术、缺陷评估方法、核电厂主设备的老化与寿命评估方法等。还对第三代先进压水堆技术中提出了需要进一步研究的力学问题,对现代应用力学如何在反应堆结构力学中更加发挥作用提出了方向。

【Abstract】 Qinshan Nuclear Power Plant(UnitⅠ),is a 300 MWe prototype PWR independently developed by Chinese own efforts,from design,manufacture,construction,installation,commissioning,to operation,inspection,maintenance,ageing management and lifetime assessment.Shanghai Nuclear Engineering Research and Design Institute(SNERDI) has taken up with and involved in deeply the R&D to tackle problems of this type of reactor since very beginning in early 1970s. Structural mechanics is one of the important aspects to ensure the safety and reliability for NPP components.This paper makes a summary on role of structural mechanics for component safety and reliability assessment in different stages of design,commissioning,operation,as well as lifetime assessment on this type PWR NPPs,including Qinshan-Ⅰand Chashma-Ⅰ,a sister plant in Pakistan designed by SNERDI.The main contents of the paper cover design by analysis for key components of NSSS;mechanical problems relating to safety analysis;special problems relating to pressure retaining components,such as fracture mechanics,sealing analysis and its test verifications,etc.;experimental research on flow-induced vibration;seismic qualification for components;component failure diagnosis and root cause analysis;vibration qualification and diagnosis technique;component online monitoring technique;development of defect assessment; methodology of aging management and lifetime assessment for key components of NPPs,etc.

  • 【会议录名称】 中国核科学技术进展报告——中国核学会2009年学术年会论文集(第一卷·第2册)
  • 【会议名称】“创新——核科学技术发展的不竭源泉”——中国核学会2009年学术年会
  • 【会议时间】2009-11-18
  • 【会议地点】中国北京
  • 【分类号】TM623.4
  • 【主办单位】中国核学会
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