【24h】

ADMIRALTY BRASS MAIN CONDENSER TUBE DEGRADATION AT FITZPATRICK

机译:FITZPATRICK的ADMINALTY黄铜主冷凝器管降解

获取原文

摘要

The James A. FitzPatrick Nuclear Power Plant is a General Electric Boiling Water Reactor (BWR 4 design) located on the southeast shore of Lake Ontario. The main condenser was re-tubed in 1994, with all admiralty brass condenser tubes replaced in-kind (the titanium impingement tubes were not replaced). The station operates with low feedwater hydrogen injection and Online NobleChem™ (OLNC) for mitigation of intergranular stress corrosion cracking (IGSCC) of reactor internals. Feedwater zinc injection is implemented for primary system (i.e., reactor recirculation system) shutdown radiation field control. The main condenser circulating water system is chlorinated to minimize microbiological fouling of the main condenser tubes. Operating Cycle 21 ended in August 2014. During Cycle 21, the station experienced a number of large condenser tube leaks. Over 60 power reductions were performed since 2011 to isolate and plug leaking condenser tubes. Visual examinations showed that a number of the leaks were associated with longitudinal tube splits, some up to two feet in length. Some tubes were severed where the ends of the severed tube were flared outward. Significant wall thinning was also identified. Increasing impurity levels in the condenser hotwell from condenser leaks challenges a BWR in maintaining low levels of detrimental anions (e.g., sulfate and chloride). These impurities enter the reactor vessel directly from the feedwater system and can initiate or accelerate intergranular stress corrosion cracking (IGSCC) of reactor internals. Further, other impurities from condenser leaks, such as silica, can impact BWR fuel performance. This paper provides a summary discussion of the probable failure mechanism leading to the admiralty brass condenser tube splits, actions taken by the station to minimize impurity levels in the reactor coolant during Cycle 21, the effectiveness of these actions, and results of inspections in the fall 2014 refueling outage to assess fuel reliability and IGSCC of reactor vessel components from the unusual Cycle 21 chemistry conditions. The main condenser was completely re-tubed in the fall of 2014 with titanium.
机译:詹姆斯·菲茨·帕特里克(James A. FitzPatrick)核电站是位于安大略湖东南岸的通用电开水堆(BWR 4设计)。 1994年对主冷凝器进行了重新配管,所有金钟黄铜冷凝器管均进行了实物更换(未更换钛撞击管)。该站采用低给水氢注入量和Online NobleChem™(OLNC)进行操作,以减轻反应堆内部的晶间应力腐蚀开裂(IGSCC)。给水锌注入是针对主要系统(即反应堆再循环系统)停机辐射场控制而实施的。主冷凝器循环水系统经过氯化处理,以最大程度地减少主冷凝器管的微生物污染。 21号工作循环于2014年8月结束。在21号循环中,该站发生了许多大的冷凝器管泄漏。自2011年以来,已执行了60多次降电措施,以隔离和堵塞泄漏的冷凝器管。目视检查表明,许多泄漏与纵向管裂有关,有些泄漏长达两英尺。一些管子被切断,其中被切断的管子的末端向外张开。还发现了明显的壁变薄。冷凝器泄漏引起的冷凝器热井中杂质含量的增加对BWR保持低水平的有害阴离子(例如硫酸根和氯离子)提出了挑战。这些杂质直接从给水系统进入反应堆容器,并可能引发或加速反应堆内部的晶间应力腐蚀开裂(IGSCC)。此外,来自冷凝器泄漏的其他杂质(例如二氧化硅)会影响BWR燃料性能。本文对导致金钟黄铜冷凝器管分裂的可能故障机理,在第21轮周期中该站为使反应堆冷却剂中的杂质水平降至最低而采取的措施,这些措施的有效性以及秋季检查的结果进行了总结性讨论。 2014年的加油中断是为了从异常的21世纪化学条件下评估反应堆容器部件的燃料可靠性和IGSCC。主冷凝器已在2014年秋季完全重新铺设了钛管。

著录项

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号