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INADVERTENT BLOWDOWN EVENT IN A NUCLEAR BOILING WATER REACTOR

机译:核沸水反应器中不良的排污事件

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On March 6th 2007, the Leibstadt Nuclear Power Plant in Switzerland experienced an automatic blowdown of eight safety/relief valves installed on the main steam lines caused by a faulty electrical manipulation while performing planned maintenance during full power operation. Due to the temperature measurements inside the reactor recirculation system and the reactor pressure vessel this event, at a first glance, appeared to be Event No. 23 (Automatic Blowdown event) as an Emergency (Service Level C) Condition in accordance with the relevant reactor pressure vessel Thermal Cycle Diagram. According to the ASME Code Section III, Service Level C limits permit large deformations in areas of structural discontinuity which may necessitate the removal of a component from service for inspection or repair. This paper presents a summary of thermal-hydraulic, stress, fatigue, and fracture mechanical evaluations as well as plant inspections performed to demonstrate the impact of the event on the reactor pressure vessel and associated components and to fulfill the requirements of the Swiss Federal Nuclear Safety Inspectorate. It is shown that the primary circuit of the plant was not inadmissibly stressed by the event and that it was acceptable from a safety-related point of view to return the plant to service. Corresponding to the 7-level International Nuclear and Radiological Event Scale this event was rated afterwards as level 1 (anomaly) by the Swiss Federal Nuclear Safety Inspectorate.
机译:2007年3月6日,瑞士的莱布施塔特核电站由于电气操作错误而在主蒸汽管道上安装了八个安全/泄压阀,导致自动排污,同时在全功率运行期间进行了计划的维护。由于反应堆再循环系统和反应堆压力容器内部的温度测量,根据相关反应堆,此事件乍一看似乎是第23号事件(自动排污事件),属于紧急情况(服务水平C)压力容器热循环图。根据ASME规范第III部分,服务等级C的限制允许结构不连续区域的较大变形,这可能需要从服务中移除组件以进行检查或维修。本文总结了热工液压,应力,疲劳和断裂力学评估以及进行的工厂检查,以证明该事件对反应堆压力容器及其相关组件的影响,并满足瑞士联邦核安全局的要求。视察。结果表明,该事件并未给工厂的主回路造成压力,从安全相关的角度来看,使工厂恢复运行是可以接受的。对应于7级国际核和放射事件量表,此事件此后被瑞士联邦核安全检查局评为1级(异常)。

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