EPR项目蒸汽发生器下封头与管板环焊缝超声检验技术改进
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摘要
欧洲先迚压水堆(EPR)项目蒸汽収生器下封头和管板环焊缝是一回路的重要边界,焊缝厚度大且焊缝的一侧为球面,制定超声检验工艺时要充分考虑探头声束衰减、探头角度变化等影响,以满足相关检验标准的要求。对RCC-M和EN 1713等标准深入研究后,通过对探头能量和角度变化的分析与模拟演算,可得出:该焊缝超声检验增加60°探头,不仅满足标准要求,而且从检验工艺上大大降低了危险性缺陷漏检的风险。
The bottom seal head and the pipe plate circumferential weld of the steam generator in EPR project is the important boundary of the first loop. Because of the large thickness and the spherical shape of the weld, the ultrasonic inspection process should be made with full consideration of the effects such as the attenuation of the probe sound beam and the change of the angle of the probe, so as to meet the requirements of relevant inspection standards. With the in-depth study of the RCC-M and EN 1713 standards, conclusions can be made based on the analysis and simulation of the energy and angle change of the probe, that, by adding a 60 degree probe in the inspection process, the requirements of standard can be satisfied, and the risk of missing dangerous defects can be reduced so that the quality of nuclear safety equipment can be ensured.
The bottom seal head and the pipe plate circumferential weld of the steam generator in EPR project is the important boundary of the first loop. Because of the large thickness and the spherical shape of the weld, the ultrasonic inspection process should be made with full consideration of the effects such as the attenuation of the probe sound beam and the change of the angle of the probe, so as to meet the requirements of relevant inspection standards. With the in-depth study of the RCC-M and EN 1713 standards, conclusions can be made based on the analysis and simulation of the energy and angle change of the probe, that, by adding a 60 degree probe in the inspection process, the requirements of standard can be satisfied, and the risk of missing dangerous defects can be reduced so that the quality of nuclear safety equipment can be ensured.
引文
[1]景军涛,江才林,罗吾希,等.EPR蒸汽収生器制造技术[J].压力容器,2013,30(09):65-70.
[2]AFCEN.Design and construction rules for mechanical components of PWR nuclear islands:RCC-M(2007edition)[S].2007.
[3]丁训慎.压水堆核电站蒸汽収生器的制造[J].核电站,2003,(4):11-18.
[4]李双燕.百万千瓦级压水堆核电站核岛主设备蒸汽収生器焊接技术[J].压力容器,2011,28(2):38-43.
[5]吴根华,阎建芳,许遵言.核电站蒸汽収生器的无损检测[J].无损检测,2005,27(10):547-550.
[6]AFCEN.In-service inspection rules for mechanical components of PWR nuclear islands:RSE-M(1997edition+2000 add)[S].Paris:AFCEN,2000.
[7]CEN.Ultrasonic testing characterization of indications in welds:EN 1713(1998+A1:2002)[S].Brussels:CEN,2002.
[2]AFCEN.Design and construction rules for mechanical components of PWR nuclear islands:RCC-M(2007edition)[S].2007.
[3]丁训慎.压水堆核电站蒸汽収生器的制造[J].核电站,2003,(4):11-18.
[4]李双燕.百万千瓦级压水堆核电站核岛主设备蒸汽収生器焊接技术[J].压力容器,2011,28(2):38-43.
[5]吴根华,阎建芳,许遵言.核电站蒸汽収生器的无损检测[J].无损检测,2005,27(10):547-550.
[6]AFCEN.In-service inspection rules for mechanical components of PWR nuclear islands:RSE-M(1997edition+2000 add)[S].Paris:AFCEN,2000.
[7]CEN.Ultrasonic testing characterization of indications in welds:EN 1713(1998+A1:2002)[S].Brussels:CEN,2002.