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核电厂蒸汽发生器与主泵对接焊缝检查系统开发 被引量:1

Development of Inspection System for Weld Joint between Steam Generator and Reactor Coolant Pump in Nuclear Power Plants
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摘要 AP1000核电厂蒸汽发生器出口接管与主泵泵壳对接焊缝泵壳侧为粗晶奥氏体铸造材料,由于该焊缝壁厚大、超声衰减、晶粒散射严重等导致焊缝的超声检测技术开发难度大。本研究采用特殊的设计,开发了一套从蒸汽发生器出口接管内壁实施超声检测的自动检查系统,并将该系统应用于国内某AP1000核电厂的役前检查。结果表明,该检查系统完全满足现场检查要求,检验结果与焊缝出厂检验结果具有良好的一致性。 The reactor coolant pump casing of weld joint between steam generator outlet nozzle and reactor coolant pump is made by coarse-grain austenitic material.The weld joint is with thick wall,ultrasonic attenuation and grain scattering,the development of ultrasonic technique is very difficult.In this study,a special design is adopted to develop an automatic ultrasonic inspection system from inner surface of the steam generator outlet nozzle,and this system has been applied to the pre-service inspection of AP1000 Nuclear Power Plant in China.The results show that this system could fully meets the on-site inspection requirements,and the inspection results are in good agreement with the factory results.
作者 于岗 周路生 陶泽勇 张宝军 Yu Gang;Zhou Lusheng;Tao Zeyong;Zhang Baojun(State Nuclear Power Plant Service Company,Shanghai,200233,China)
出处 《核动力工程》 EI CAS CSCD 北大核心 2019年第5期150-155,共6页 Nuclear Power Engineering
关键词 AP1000 蒸汽发生器与主泵对接焊缝 超声波 检查系统 AP1000 Weld joint between reactor coolant pump and steam generator Ultrasonic Inspection system
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