首页> 外文会议>International conference on nuclear engineering;ASME power conference >HYDROGEN INGRESS INTO ZIRCONIUM ALLOYS AS A LIFE-LIMITING FACTOR- METHODS OF IN-LINE MONITORING, PREDICTION AND CONTROL
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HYDROGEN INGRESS INTO ZIRCONIUM ALLOYS AS A LIFE-LIMITING FACTOR- METHODS OF IN-LINE MONITORING, PREDICTION AND CONTROL

机译:限制合金中氢进入锆合金的在线监测,预测和控制方法

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Zirconium alloys are used as structural components in most nuclear reactors. For example Zr-2.5 wt.%Nb alloy is currently used in the fabrication of pressure tubes in CANDU® (Canada Deuterium Uranium) reactors, and "Zircaloys" are used as fuel cladding in many BWR reactors. In general, zirconium alloys pick up hydrogen (or its isotope deuterium) in reactor primary heat transport system coolant during aqueous corrosion, raising the possibility of hydride formation and delayed hydride cracking at high levels of hydrogen concentration. As a result, the buildup of hydrogen in components due to corrosion could be life limiting. In this paper several mechanisms of in-service hydrogen ingress into zirconium alloys will be discussed to identify the main factors controlling the rate of uptake by the alloy under specific reactor operating conditions. The redistribution of hydrogen due to diffusion will be described along with methods of monitoring and predicting the buildup of hydrogen concentration as a function of operating time. Possible approaches to slow down the rate of ingress will be discussed, which include water chemistry modification and surface conditioning. Innovative non-destructive monitoring techniques developed at "KINECTRICS Inc." will also be addressed.
机译:锆合金在大多数核反应堆中用作结构部件。例如,Zr-2.5wt。%Nb合金当前被用于(加拿大氘铀)反应堆中的压力管的制造中,并且“锆合金”被用作许多BWR反应堆中的燃料包壳。通常,锆合金在水腐蚀期间会在反应堆主传热系统冷却剂中吸收氢(或其同位素氘),从而增加了在高氢浓度下形成氢化物和延迟氢化物裂解的可能性。结果,由于腐蚀而导致的部件中氢的积累可能会限制使用寿命。在本文中,将讨论在役氢进入锆合金的几种机理,以确定在特定反应器操作条件下控制合金吸收速率的主要因素。将描述由于扩散而引起的氢的重新分布,以及监测和预测氢浓度随操作时间而变化的方法。将讨论减慢进入速度的可能方法,包括水化学改性和表面调节。 “ KINECTRICS Inc.”开发了创新的无损监测技术也将得到解决。

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