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NDT for Characterizing Ageing and Degradation of Nuclear Power Plant Materials - Fatigue and Irradiation

机译:用于表征核电站材料的老化和降解的NDT - 疲劳和辐照

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Following the design rules and considering the safety factors, the lifetime of nuclear power plants (NPP), worldwide is expected to be in the range of 40 years. Obviously, within such a lifespan the components and systems under heavy mechanical (static and dynamic pressure, vibration), thermic and irradiation loads, suffer ageing phenomena which are Thermal Ageing, Corrosion, Low Cycle Fatigue (LCF), High Cycle Fatigue(HCF), Very high Cycle Fatigue (VHCF) and Irradiation Damage due to neutrons - and the possible synergy of the phenomena together. However, the electrical power producing utilities as operators of the NPP, perform a `predictive maintenance', also called `retrofitting', by timely performing the replacement of especially stressed components. Examples for these replacement procedures are the change of heat-exchangers and parts of the main cooling pipes, like hot knees near heat-exchangers or components of the surge-line in pressurized-water NPP. As the components, which are replaced, always are manufactured according the newest technical state of the art, the retrofitting enhances inherently also the safety standard. In Germany, where due to the Atomic Law, the safety of the plants is asked for, this law - beside economic reasons of a higher technical availability - is the driver for replacement. The IAAEA has introduced safety standards for Ageing Management and according these documents, worldwide most of the atomic energy producing countries have adopted their national guidelines, newly introducing mainly fatigue condition monitoring. The proposed paper discusses, on one hand, the application of the 3MA-strategy (Micromagnetic, Multiparameter, Microstructure and Stress Analysis) on ferromagnetic components and Eddy-Current-based and Ultrasonic techniques on austenitic materials for early-characterizing fatigued microstructures - before cracking and, on the other hand, characterization of irradiation damage in pressure-vessel steels.
机译:遵循设计规则并考虑安全因素,全球核电站(NPP)的一生预计将在40年的范围内。显然,在这种寿命中,在重型机械(静电和动态压力,振动),热和辐射负荷下的组件和系统内,患有衰老现象,腐蚀,腐蚀,低循环疲劳(LCF),高循环疲劳(HCF) ,非常高的循环疲劳(VHCF)和由于中子引起的照射损坏 - 以及现象的可能协同作用。然而,通过及时执行替换尤其压力的组件,将电力产生公用事业作为NPP的运营商执行“预测性维护”,也称为“改装”。这些替换程序的示例是更换热交换器和主冷却管的部件,如热交换器附近的热膝盖或加压水NPP中的电涌线的组分。由于更换的组件,始终根据最新的技术技术制造,因此改装也是固有的安全标准。在德国,由于原子法,植物的安全被要求掌握了这项法律 - 凭借更高技术可用性的经济原因 - 是更换的司机。 IAAEA已引入老化管理安全标准,并根据这些文件,全球大多数原子能生产国都采用了其国家指导方针,新引入了疲劳状态监测。拟议的论文一方面讨论了3mA策略(微磁,多路径计,微观结构和应力分析)对奥氏体材料的铁磁性分量和涡流和超声波技术,用于早期表征疲劳微观结构 - 在开裂之前另一方面,压力容器钢中辐照损伤的表征。

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