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IMPACT OF REACTOR PRESSURE VESSEL DEGRADATION

机译：反应堆压力容器降解的影响

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摘要

This paper discusses the impact of the reactor pressure vessel (RPV) degradation that was discovered at the Davis-Besse Nuclear Power Station in March 2002. On February 16, 2002, the Davis-Besse Nuclear Power Station near Oak Harbor, Ohio, began a refueling outage that included a special inspection of the Alloy 600 nozzles that enter the closure head of the low alloy carbon steel reactor pressure vessel (RPV). The inspection focused on the nozzles associated with the mechanism that drives the control rods, known as the control rod drive mechanism (CRDM). This inspection was consistent with the plant's commitments made in response to United States Nuclear Regulatory Commission Bulletin 2001-01, "Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles," which was issued on August 3, 2001. In conducting this inspection, it was discovered that three CRDM nozzles had indications of axial cracking (one with circumferential cracking also), which had resulted in leakage of the RPV's pressure boundary. Specifically, these indications were in CRDM nozzles 1, 2, and 3, which are located near the center of the RPV head. Significant degradation of the RPV's head was found adjacent to CRDM nozzle 3 and the plant entered an extended repair shutdown.
机译：本文讨论了2002年3月在戴维斯-贝斯核电站发现的反应堆压力容器（RPV）退化的影响。2002年2月16日，俄亥俄州橡树港附近的戴维斯-贝斯核电站开始了核反应堆的建造。加油中断，包括对进入低合金碳钢反应堆压力容器（RPV）封闭头的Alloy 600喷嘴的特殊检查。检查集中在与驱动控制杆的机构（称为控制杆驱动机构（CRDM））相关的喷嘴上。该检查符合该工厂根据2001年8月3日发布的美国核监管委员会第2001-01号公告“反应堆压力容器头穿透喷嘴的周向破裂”所作的承诺。发现三个CRDM喷嘴有轴向裂纹迹象（一个也有圆周裂纹），这导致RPV压力边界泄漏。具体而言，这些指示出现在位于RPV喷头中心附近的CRDM喷嘴1、2和3中。发现在CRDM喷嘴3附近，RPV的机头明显退化，工厂进入了长期维修停工期。

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