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Oxidation and Stress Corrosion Cracking of Stainless Steels in SCWRs

机译:SCWRs中不锈钢的氧化和应力腐蚀开裂

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SCWRs are high-temperature, high-pressure, water-cooled reactors that operate above the thermodynamic critical point of water (374℃, 22.1 MPa). The SCWR offers many advantages compared to state-of- the-art LWRs including the use of a single phase coolant with high enthalpy, the elimination of components such as steam generators and steam separators and dryers, a low coolant mass inventory resulting in smaller components, and a much higher efficiency (~44% vs. 33% in current LWRs). In these systems high pressure (25 MPa) coolant enters the vessel at 280℃ which is heated to about 500℃ and delivered to a power conversion cycle.rnSupercritical water (SCW) exhibits properties significantly different from those of liquid water below the critical point. Supercritical water acting essentially as a non-polar dense gas with solvation properties approaching those of a low-polarity organic. In this conditions, can dissolve gases like oxygen to complete miscibility. Depending upon what species are present and how much oxygen is present in the solution can becomes a very aggressive oxidising environment.rnMost of the data on corrosion in supercritical water are from fossil plant or oxidation waste disposal systems. However there is very limited data on corrosion in low conductivity de-aerated SCW and less on stress corrosion cracking behaviour under operating conditions foreseen for SCWR.rnCandidate materials for structural components are materials for high temperatures and include ferritic-martensitic alloys; oxide dispersion strengthened (ODS) ferritic/martensitic steels and strengthened steels by precipitation and for lower temperatures the austenitic stainless steels, such as 304 and 316, used in the LWR. Low swelling austenitic steels are also of high interest for areas with high dpa and high temperature.rnA review of the available information on corrosion and stress corrosion behaviour of different types of stainless steels in supercritical water at high temperatures is presented in this paper. The experimental programme to be performed in our lab for the study of these topics is discussed.
机译:超临界水冷堆是在水的热力学临界点(374℃,22.1 MPa)以上运行的高温高压水冷反应堆。与最先进的轻水堆相比,SCWR具有许多优势,包括使用具有高焓的单相冷却剂,省去了诸如蒸汽发生器,蒸汽分离器和干燥机之类的组件,较低的冷却剂质量库存而导致了更小的组件,效率更高(约为44%,而当前的轻水堆则为33%)。在这些系统中,高压(25 MPa)冷却剂在280℃进入容器,然后加热到约500℃,并输送至动力转换循环。超临界水(SCW)的性能与临界点以下的液态水明显不同。超临界水基本上起非极性稠密气体的作用,其溶剂化性能接近于低极性有机物。在这种条件下,可以溶解像氧气这样的气体以完全混溶。取决于存在的物种和溶液中存在的氧气量,它们会变成非常具有腐蚀性的氧化环境。超临界水中腐蚀的大多数数据来自化石厂或氧化废物处理系统。然而,关于低电导率脱气的SCW中腐蚀的数据非常有限,而在SCWR预期的工作条件下,有关应力腐蚀开裂行为的数据则较少。rn结构部件的候选材料是高温材料,包括铁素体-马氏体合金;氧化物弥散强化(ODS)铁素体/马氏体钢和析出强化钢。在较低温度下,LWR中使用的奥氏体不锈钢,例如304和316。低溶胀性奥氏体钢也对高dpa和高温领域引起了浓厚的兴趣。本文对高温下不同类型的不锈钢在超临界水中的腐蚀和应力腐蚀行为的可用信息进行了综述。讨论了要在我们的实验室中研究这些主题的实验程序。

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