• 主题
高级搜索  >
历史搜索 清空历史
首页> 外文会议>ASME Pressure Vessels and Piping conference >UTILIZATION OF SPT TECHNIQUES FOR EVALUATION OF CHANGES IN THE PROPERTIES OF THE WER-440 REACTOR PRESSURE VESSEL STEELS AFTER THEIR IRRADIATION IN THE RESEARCH AND POWER REACTORS
【24h】

UTILIZATION OF SPT TECHNIQUES FOR EVALUATION OF CHANGES IN THE PROPERTIES OF THE WER-440 REACTOR PRESSURE VESSEL STEELS AFTER THEIR IRRADIATION IN THE RESEARCH AND POWER REACTORS

机译：在研究和功率反应堆中辐照后使用SPT技术评估Wer-440反应堆压力容器钢的性能变化

获取原文
页面导航
  • 摘要
  • 著录项
  • 相似文献
  • 相关主题

摘要

The paper describes the testing procedures and the basic results of the evaluation of the Small Punch Test (SPT) specimens after their irradiation in the Halden reactor in Norway. The SPT technique was used for estimation of basic mechanical properties as ultimate tensile strength and yield stress of the tested materials as well as the Fracture Appearance Transition Temperature (FATT). The main aim of the work was to compare the SPT results obtained from the surveillance specimen programs implemented in the Slovak power reactors with the SPT results from the specimens irradiated in the research reactor in Halden. For the project there were chosen 3 types of steels used for construction of the reactor WER 440/213 type in Bohunice NPPs in the Slovak Republic. The experimental materials were two bainitic steels - base metal and weld metal of the reactor pressure vessel wall and austenitic cladding of the reactor wall. Two sets of SPT specimens together with mini-tensile specimens prepared from the experimental materials were irradiated in the Halden reactor. The samples were irradiated at 275°C to two fluence values which are equivalent to approximately of 4 and 6 campaigns in the power reactor. Obtained results are compared to up-to-date SPT results from the surveillance specimen program applied at Bohunice NPP in the Slovak Republic.
机译：本文介绍了在挪威的Halden反应堆中辐照后的小打孔试验（SPT）样品的测试程序和评估的基本结果。 SPT技术用于评估基本机械性能，如被测材料的极限拉伸强度和屈服应力，以及断裂外观转变温度（FATT）。这项工作的主要目的是比较从斯洛伐克动力堆中实施的监测标本计划获得的SPT结果与在哈尔登的研究堆中辐照的标本得到的SPT结果。在该项目中，选择了3种类型的钢，用于在斯洛伐克共和国的Bohunice核电厂建造WER 440/213型反应堆。实验材料是两种贝氏体钢-反应堆压力容器壁的贱金属和焊缝金属以及反应堆壁的奥氏体熔覆层。在Halden反应器中辐照两组SPT标本以及由实验材料制备的微拉伸标本。样品在275°C照射到两个能量密度值，这大约相当于动力反应堆中的4和6个运动。将获得的结果与斯洛伐克共和国Bohunice NPP实施的监测标本计划的最新SPT结果进行比较。

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