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ASSESSMENT OF PASSIVELY ACTUATED IN-SITU CYCLIC SURVEILLANCE TEST SPECIMENS FOR ADVANCED NON-LIGHT WATER REACTORS

机译:先进的非轻型反应堆被动式原位循环监测测试标本的评估

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The use of surveillance specimens was identified in a roadmap (Sims, 2010, ASME HTGR Code Development Roadmap, STP-NU-045, American Society of Mechanical Engineers, New York, NY) developed for the U.S. Nuclear Regulatory Commission for non-light water reactors that are intended to have very long design lives on the order of 500,000 hours. Creep-rupture, long term strain accumulation, creep-fatigue damage, and their interaction with environmental effects require significant extrapolation from shorter term tests. Surveillance specimens provide a means for confirmation of these extrapolations in-situ. The effects of cyclic service on creep-fatigue damage would be particularly challenging based on conventional mechanical testing. Proposed herein is a passive cyclic testing methodology that lends itself well to in-situ surveillance applications. The concept is based on utilizing the difference in the thermal expansion coefficient of candidate materials to generate cyclic loading based on operational thermal transients. Prototypical specimen designs are proposed and their in-situ response to representative plant operation are evaluated.
机译:为美国轻水核监管委员会制定的路线图(Sims,2010年,ASME HTGR代码开发路线图,STP-NU-045,美国机械工程师协会,纽约,纽约)中确定了监视标本的使用。预期具有很长设计寿命的反应堆约为500,000小时。蠕变断裂,长期应变累积,蠕变疲劳损伤及其与环境影响的相互作用需要从短期试验中进行大量推断。监视标本为现场推断这些推断提供了一种手段。基于常规的机械测试,周期性服务对蠕变疲劳损伤的影响将特别具有挑战性。本文提出了一种被动循环测试方法,该方法非常适合于现场监视应用。该概念基于利用候选材料的热膨胀系数差异来基于操作热瞬变生成循环载荷。提出了原型样品设计,并评估了它们对代表性工厂运行的原位响应。

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