• 主题
高级搜索  >
历史搜索 清空历史
首页> 外文期刊>Journal of Engineering for Gas Turbines and Power >Investigation of the Beltline Welding Seam and Base Metal of the Greifswald WWER-440 Unit 1 Reactor Pressure Vessel
【24h】

Investigation of the Beltline Welding Seam and Base Metal of the Greifswald WWER-440 Unit 1 Reactor Pressure Vessel

机译：格赖夫斯瓦尔德WWER-440 1号反应堆压力容器的带线焊缝和母材的研究

获取原文
获取原文并翻译 | 示例
           
页面导航
  • 摘要
  • 著录项
  • 相似文献
  • 相关主题

摘要

The investigation of reactor pressure vessel (RPV) materials from decommissioned nuclear power plants (NPPs) offers the unique opportunity to scrutinize the irradiation behavior under real conditions. Material samples taken from the RPV wall enable a comprehensive material characterization. The paper describes the investigation of trepans taken from the decommissioned WWER-440 first generation RPVs of the Greifswald NPP. Those RPVs represent different material conditions such as irradiated (I); irradiated and recovery annealed (IA); and irradiated, recovery annealed, and re-irradiated (IAI). The working program is focused on the characterization of the RPV steels (base and weld metal) through the RPV wall. The key part of the testing is aimed at the determination of the reference temperature T_o following the American Society for Testing of Materials (ASTM) Test Standard EJ921-08 to determine the fracture toughness of the RPV steel in different thickness locations. In a first step, the trepans taken from the RPV Greifswald unit 1 containing the X-butt multilayer submerged welding seam and from base metal ring 0.3.1 both located in the beltline region were investigated. Unit 1 represents the IAI condition. It is shown that the master curve (MC) approach as adopted in ASTM El 921 is applicable to the investigated original WWER-440 weld metal. The evaluated T_o varies through the thickness of the welding seam. The lowest T_o value was measured in the root region of the welding seam representing a uniform fine grain ferritic structure. Beyond the welding root T_o shows a wavelike behavior. The highest T_o of the weld seam was not measured at the inner wall surface. This is important for the assessment of ductile-to-brittle temperatures measured on subsize Charpy specimens made of weld metal compact samples removed from the inner RPV wall. Our findings imply that these samples do not represent the most conservative condition. Nevertheless, the Charpy-V transition temperature TT_(41J) estimated with results of subsize specimens after the recovery annealing was confirmed by the testing of standard Charpy-V-notch specimens. The evaluated TT_(4IJ) shows a better accordance with the irradiation fluence along the wall thickness than the master curve reference temperature T_o. The evaluated T_0from the trepan of base metal ring 0.3.1 varies through the thickness of the RPV wall. The K_(Jc) values generally follow the course of the MC, although the scatter is large. The re-embrittlement during two campaign operations can be assumed to be low for the weld and base metal.
机译：对退役核电站（NPPs）的反应堆压力容器（RPV）材料的研究提供了独特的机会来检查真实条件下的辐射行为。从RPV墙获取的材料样本可进行全面的材料表征。本文描述了从格赖夫斯瓦尔德NPP退役的WWER-440第一代RPV中获取的铁环的研究。这些RPV代表不同的物质条件，例如辐照（I）；辐照并恢复退火（IA）；然后进行辐照，恢复退火，然后再辐照（IAI）。该工作程序的重点是通过RPV壁对RPV钢（基础金属和焊缝金属）进行表征。测试的关键部分旨在根据美国材料试验协会（ASTM）测试标准EJ921-08确定参考温度T_o，以确定RPV钢在不同厚度位置的断裂韧性。第一步，研究了从RPV Greifswald单元1截取的，位于X线对接多层埋入式焊缝中的节环和从都位于带线区域的贱金属环0.3.1中截取的节环。单元1代表IAI条件。结果表明，ASTM El 921中采用的主曲线（MC）方法适用于所研究的原始WWER-440焊接金属。评估的T_o随焊缝厚度的变化而变化。在代表均匀的细晶粒铁素体组织的焊缝根部区域中测量出最低的T_o值。在焊接根部T_o之外显示出波状行为。在内壁表面未测量到焊缝的最高T_o。这对于评估在亚尺寸夏比（Charpy）试样上测量的韧性至脆性温度非常重要，该试样由从内部RPV壁上取下的焊接金属紧密样品制成。我们的发现暗示这些样本不代表最保守的情况。尽管如此，通过标准Charpy-V缺口试样的测试证实了用恢复退火后的小尺寸试样的结果估算的Charpy-V转变温度TT_（41J）。所评估的TT_（4IJ）与沿主壁参考温度T_o的沿壁厚的辐照通量相比具有更好的一致性。从母材金属环0.3.1的截面积得出的T_0随RPV壁的厚度而变化。尽管分散很大，但K_（Jc）值通常遵循MC的过程。对于焊缝和母材，可以假定在两次运动期间的重新包埋率较低。

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