首页> 外文会议>Workshop on Structural Materials for Innovative Nuclear Systems >Oxidation and Stress Corrosion Cracking of Stainless Steels in SCWRs
【24h】

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裂纹

获取原文

摘要

SCWRs are high-temperature, high-pressure, water-cooled reactors that operate above the thermodynamic critical point of water (374°C, 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°C which is heated to about 500°C and delivered to a power conversion cycle. Supercritical 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. Most 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. Candidate 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. A 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:SCWRS是高温,高压,水冷式反应器,在热力学临界点(374°C,22.1MPa)上方工作。与最先进的LWR相比,SCWR提供了许多优点,包括使用具有高焓的单相冷却剂,消除蒸汽发生器和蒸汽分离器和蒸汽分离器和烘干机的组件,低冷却剂质量库存导致较小的组件,效率更高(当前LWR的33%〜44%)。在这些系统中,高压(25MPa)冷却剂在280℃下进入容器,其被加热至约500℃并递送到电力转换循环。超临界水(SCW)表现出与临界点以下液体水显着不同的性质。基本上作为非极性致密气体的超临界水,其溶剂化性能接近低极性有机物。在这种情况下,可以将气体溶解如氧气,以完全混溶。取决于存在的物种以及溶液中存在多少氧气可以成为一个非常激进的氧化环境。超临界水中的大多数数据来自化石厂或氧化废物处理系统。然而,对低导电性的腐蚀数据存在非常有限的数据,其在为SCWR预见的操作条件下对应力腐蚀开裂行为的腐蚀较少。结构部件的候选材料是高温材料,包括铁素体 - 马氏体合金;氧化物分散体强化(ODS)铁素体/马氏体钢并通过沉淀加强钢,并且对于在LWR中使用的奥氏体不锈钢等奥氏体不锈钢如304和316的温度。低膨胀奥氏体钢对具有高DPA和高温的区域也高。本文介绍了高温下超临界水中不同类型不锈钢腐蚀和应力腐蚀行为的可用信息的审查。讨论了在我们实验室中进行的实验计划进行研究,以研究这些主题。

著录项

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号