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“华龙一号”反应堆压力容器主螺栓缺陷处理工艺研究

Analysis on the Defect Treatment Process of the Pressure Vessel Stud of the HPR1000
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摘要 “华龙一号”示范工程的核反应堆压力容器是影响核安全的重要机械设备。机组换料大修期间,个别核反应堆压力容器主螺栓旋至一定深度时卡住,无法继续旋入,且出现无法退出的缺陷问题,该缺陷将直接影响核反应回路边界完整性,对核安全构成威胁,因此核反应堆压力容器主螺栓修复工艺方法一直是国内外研究重点。结合某“华龙一号”核电站主螺栓受损案例,提出并研究一套缺陷处理工艺,完成“华龙一号”压力容器主螺栓高效取出、本体螺栓孔完整修复,通过对主螺栓取出工艺的可操作性描述,论证该套工艺方法实际应用可行性及过程质量管控有效性,为后续“华龙一号”机组压力容器主螺栓的修复提供参考和借鉴。 The nuclear reactor pressure vessel of HPR1000 demonstration project is an important mechanical equipment affecting nuclear safety. The studs of individual nuclear reactor pressure vessel are stuck when they are screwed to a certain depth during the refueling outage, and they cannot be screwed in. It will affect the boundary integrity of the nuclear reaction circuit and pose a threat to nuclear safety. Therefore, the repair process method of the studs of nuclear reactor pressure vessel has always been the focus of research at home and abroad. A set of defect treatment process is proposed and studied to complete the efficient removal of the stud of HPR1000 pressure vessel and the complete repair of the bolt hole of the body. The feasibility of the practical application of the process method and the effectiveness of process quality control are demonstrated, through the operable analysis and kinematic calculation of the stud removal process.
作者 韩文悦 王永鹏 崔运佳 庄泽楠 HANWen-yue;WANG Rong-peng;CUI Yun-jia;ZHUANG Ze-nan(Guodian Zhangzhou Energy Co.,Ltd.,CNNP,Zhangzhou,Fujian Prov,363300,China)
出处 《中国核电》 2022年第3期358-363,共6页 China Nuclear Power
关键词 反应堆压力容器 主螺栓 缺陷处理工艺 修复 reactor pressure vessel stud defect treatment process repair
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