首页> 外文会议>European Conference Non-Destructive Testing >Role of Weld root Geometry - Backing rings in Flow Accelerated Corrosion (FAC): Radiography testing is an alternate NDT method for detection - An experience at Tarapur Atomic Power Station-12; Nuclear Power Corporation of India Limited, India
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Role of Weld root Geometry - Backing rings in Flow Accelerated Corrosion (FAC): Radiography testing is an alternate NDT method for detection - An experience at Tarapur Atomic Power Station-12; Nuclear Power Corporation of India Limited, India

机译:焊接根几何形状的作用 - 背圈流动加速腐蚀(FAC):射线照相测试是一种用于检测的替代NDT方法 - 塔拉普尔原子发电站-1和2的经验;印度核电公司有限公司,印度有限公司

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Tarapur Atomic Power Station (TAPS) is one of the vintage nuclear reactors operating in the world and belongs to earlier generation of Boiling Water Reactors (BWRs) has completed 40 years of successful, commercial and safe operation. TAPS was designed to generate 210MWe out of which 70% was from reactor primary steam and the remaining from Secondary Steam Generators (SSGs). These SSGs were isolated in the year 1984 and units are operating at re-rated capacity of 160Mwe since then. Of late it has been identified that Flow Accelerated Corrosion (FAC) is one of the degradation mechanisms with High Energy system piping components. The sudden failure of high energy (Enthalpy) piping components lead to loss of human lives as well as property loss in addition to the unplanned down times. The power industry is now reviewing their effectiveness of detection and monitoring programmes to identify & mitigate the consequences. The recent pipe rupture incidents in overseas NPPs in secondary cycle piping have alarmed Indian NPPs. This issue was reviewed in detail at TAPS-1&2 and corrective & measures have been formulated for timely detection of degradations. During these four decades TAPS has engineered many inspection methodologies to detect various degradation mechanisms such as IGSCC (Inter Granular Stress Corrosion Cracking), TGSCC (Trans-Granular Stress Corrosion Cracking), Erosion-Corrosion (EC), Stress Corrosion Cracking (SCC) and Flow Accelerated Corrosion (FAC). These degradation mechanisms were timely detected using various inspection methodologies developed time to time. The expertise gained from the Operation & Maintenance (O&M) of reactors for the past four decades has strengthened the capabilities of station inspection personnel to develop various inspection methodologies & their application in the filed. One such inspection methodology was developed by the station QA group which has potential to detect the degradation of high energy system piping components vulnerable to FAC, especially the weld root inaccuracies. This inspection technique is established at site NDT facility with in-house expertise and effectively utilized to detect the piping components degradation due to FAC. This paper gives a brief insight into the various inspection methodologies followed at TAPS for timely detection of degradation mechanisms avoiding catastrophic failure of High Energy system piping components. TAPS has effectively utilized these inspection methodologies and implemented to assess such component's integrity have also been briefly discussed.
机译:Tarapur原子发电站(龙头)是世界上运营的老式核反应堆之一,属于早期一代沸水反应堆(BWR)已完成40年的成功,商业和安全运行。龙头设计用于产生210mme,其中70%来自反应器初级蒸汽和剩余的来自次级蒸汽发生器(SSG)。这些SSG在1984年中被隔离,从那时起,单位正在以160米的重新额定容量运行。已经识别出流动加速腐蚀(FAC)是具有高能量系统管道部件的降解机制之一。高能量(焓)管道部件的突然失败导致人类生活的丧失以及除了意外停机时间之外的性能损失。电力行业正在审查其检测和监测计划的有效性,以确定和减轻后果。近期循环管道中近期境外NPP的管道破裂事件令人鼓舞。在TAPS-1和2的详细审查此问题,并制定了纠正和措施以及时检测降解。在这四个十年中,TAPS已经设计了许多检测方法,以检测各种降解机制,例如IGSCC(颗粒应力腐蚀裂解),TGSCC(反式颗粒应力腐蚀裂解),腐蚀 - 腐蚀(EC),应力腐蚀裂纹(SCC)和流量加速腐蚀(FAC)。使用各种检测方法产生的时间及时地检测到这些降解机制。过去四十年反应堆运营与维护(O&M)中获得的专业知识加强了站点检验人员的能力,以在提交方面开发各种检验方法及其应用。一项这样的检查方法是由车站QA组开发的,这有可能检测容易受到FAC的高能量系统管道部件的降解,尤其是焊接根部不准确。该检验技术是在现场NDT设施的内部专业知识的设施,有效地利用,以检测由于FAC引起的管道部件降低。本文简要了解各种检验方法,以便及时检测避免高能量系统管道部件的灾难性失效的降解机制。水龙头已有效地利用了这些检验方法,并实施以评估此类组件的诚信也简要讨论过。

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