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Magnox Steel Reactor Pressure Vessel Monitoring Schemes-An Overview

机译:Magnox钢反应堆压力容器监控方案概述

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The steel pressure vessel Magnox reactors were designed in the 1950s and were made from C-Mn plate steel and forgings welded together using a mixture of submerged-arc and manual metal arc weld metals. Each reactor contained surveillance capsules with specimens of plate steel, forgings, and the different weld metals to monitor the effects of irradiation on the Charpy impact and tensile properties. Canisters were withdrawn over the operating life and measurements were taken. During the lifetime of the fleet, there were developments in testing, observed changes in properties, and understanding of the radiation damage process that challenged the safety cases to support the operation of the stations. At the time the reactors were designed, the concept of fracture toughness was only beginning to be investigated, yet during the lifetime of the stations, fracture toughness testing was successfully adopted as standard practice as an input to fracture mechanics based assessment of the steel vessels. Both hardening and non-hardening embrittlements, the latter due to impurity phosphorus segregation in weld metal, were successfully addressed. At a relatively late stage the contribution of "thermal neutrons" to embrittlement was identified as being significant and was successfully incorporated into the assessment process. This led to the adoption of sophisticated statistical techniques to assess changes in properties of the most critical construction material-submerged-arc weld metal. A large scale sampling and testing programme of submerged-arc weld metal from a decommissioned reactor validated the assessment process. As a result of successfully addressing these and other challenges when the last two steel pressure vessel stations closed in December 2006, they had achieved lifetimes of nearly 40 years.
机译:钢制压力容器Magnox反应堆是在1950年代设计的,由C-Mn板钢和锻件组成,这些锻件使用埋弧和手工电弧焊金属的混合物焊接在一起。每个反应堆都装有监视舱,舱内装有钢板,锻件和不同的焊接金属标本,以监测辐射对夏比冲击和拉伸性能的影响。在使用期限内撤回了碳罐并进行了测量。在车队的整个生命周期中,测试的发展,观察到的特性变化以及对辐射破坏过程的理解,这些挑战对安全案例提供了支持,以支持站点的运行。在设计反应堆时,断裂韧性的概念才刚刚开始研究,但是在工位的使用寿命内,断裂韧性测试已被成功地用作标准实践,作为基于断裂力学的钢制容器评估的输入。成功解决了硬化和非硬化脆化(后者是由于焊缝金属中的杂质磷偏析所致)。在相对较晚的阶段,“热中子”对脆化的贡献被认为是重要的,并成功地纳入了评估过程。这导致采用复杂的统计技术来评估最关键的建筑材料埋弧焊金属的性能变化。退役反应堆中的大型埋弧焊金属取样和测试程序验证了评估过程。在2006年12月关闭了最后两个钢制压力容器站后,由于成功应对了这些挑战和其他挑战,它们的使用寿命已接近40年。

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