• 主题
高级搜索  >
历史搜索 清空历史
首页> 美国政府科技报告 >Effect of irradiation on the stress corrosion cracking behavior of Alloy X-750 and Alloy 625.
【24h】

Effect of irradiation on the stress corrosion cracking behavior of Alloy X-750 and Alloy 625.

机译：辐照对合金X-750和合金625应力腐蚀开裂行为的影响。

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

摘要

In-reactor testing of bolt-loaded precracked and as-notched compact tension specimens was performed in 360(degrees)C water to determine effect of irradiation on SCC of Condition HTH and Condition BH Alloy X-750 and age-hardened Alloy 625. Variables were stress intensity factor (K(sub I)) level, fluence, grade of HTH material, prestraining and material chemistry. Effects of irradiation on high temperature SCC and the rapid cracking that occurs during cooldown below 150(degrees)C were characterized. Significant degradation in the in-reactor SCC resistance of HTH material was observed at initial K(sub I) levels above 30 MPa(radical)m and fluences greater than 10(sup 19) n/cm(sup 2) (E > 1 MeV). A small degradation in SCC resistance of HTH material was observed at low fluences (20 ppM). Age-hardened Alloy 625 exhibited superior in-reactor SCC behavior compared to HTH material as no crack extension occurred in any of the precracked Alloy 625 specimens tested at initial K(sub I) levels up to 80 MPa(radical)m.

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