首页> 外文会议>International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors >CHARACTERIZATION OF IN-SERVICE THERMAL AGING EFFECTS IN BASE METALS AND WELDS OF THE PRESSURE VESSEL OF A DECOMMISSIONED PWR PRESSURIZER, AFTER 27 YEARS OF OPERATION
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CHARACTERIZATION OF IN-SERVICE THERMAL AGING EFFECTS IN BASE METALS AND WELDS OF THE PRESSURE VESSEL OF A DECOMMISSIONED PWR PRESSURIZER, AFTER 27 YEARS OF OPERATION

机译:在27年的操作后,在退役的PWW加压器压力容器的基础金属和焊缝中表征在贱金属和焊缝中

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In 2012, after the replacement of the Pressurizer ofthe Ringhals 4 nuclear power plant, sections of thedecommissioned pressurizer pressure vessel were cut byRinghals and made available to a group of members ofthe FROG?* Aging Network for investigations onthermal aging. At its decommissioning date, thiscomponent had been in operation for more than ~ 27years (close to 190 000 h) at a temperature close to350°C.The cut sections included pieces of the welds and of theadjacent base metals (BM) between the lower shell ringand the bottom dome. The original base materials of thepressure vessel wall were SA533 Gr B Cl1 plates. TheEnd of Manufacturing Report (EOMR) for the Pressurizerwas also made available, and acceptance tests resultswere retrieved, for comparison with the properties after27 years of operation.Tensile tests and Charpy impact tests were performed inthe in-service-aged conditions. The program wascompleted by some detailed microstructuralinvestigations, including fractographic examinations,Auger electron spectroscopy of grain boundaries, andatom probe tomography observations.The paper presents the results of these investigations andshows that the effects of thermal aging on the ductilebrittletransition temperature are not significant for basematerials and heat affected zone. Some effects aremeasured for weld metals (WM). In the discussion, themeasured embrittlement is related to the variation oftensile properties and the chemical composition of thematerials, in terms of impurity content (phosphorus) andother elements (nickel) of the WM chemical composition.
机译:2012年,更换了加压后Ringhals 4核电站,部分切割退役的加压仪压力容器Ringhals并为一群成员提供青蛙?*老化网络进行调查热老化。在退役日期,这组件已经运行超过〜27靠近的温度(接近190 000小时)350°C。切割部分包括焊缝和件下壳环之间的相邻基金金属(BM)和底部圆顶。原始基础材料压力容器壁是SA533 GR B CL1板。这用于加压器的制造报告(EOMR)结束也可用,并验收测试结果被检索,以便与属性相比27年的运作。进行拉伸试验和夏比冲击试验在役老化的条件下。该计划是通过一些详细的微观结构完成调查包括Fretoction Chequations,谷物边界的螺旋钻电子光谱,和原子探测断层摄影观察。本文提出了这些调查的结果表明热老化对延性血症的影响过渡温度对基部不显着材料和热影响区。有些效果是测量焊接金属(WM)。在讨论中,测量的脆化与变异有关拉伸性质和化学成分材料,就杂质含量(磷)和WM化学成分的其他元素(镍)。

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