...
首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >General corrosion and stress corrosion cracking of Alloy 600 in light water reactor primary coolants
【24h】

General corrosion and stress corrosion cracking of Alloy 600 in light water reactor primary coolants

机译:辐射反应器初级冷却剂合金600的一般腐蚀和应力腐蚀裂纹

获取原文
获取原文并翻译 | 示例
           

摘要

The general corrosion and stress corrosion cracking behaviors of the nickel-base Alloy 600 in the primary high temperature aqueous coolants of light water cooled and moderated nuclear power reactors are reviewed. The compatible welding Alloys 182 and 82 as well as the high strength, precipitation hardened analogue, Alloy X-750, are also included. The emphasis is on what is known of the underlying science of these degradation phenomena rather than on the associated engineering consequences and remedies. (C) 2019 Published by Elsevier B.V.
机译:综述了镍基合金600在初级高温核电力反应器中镍基合金600的一般腐蚀和应力腐蚀开裂行为。 还包括相容的焊接合金182和82以及高强度,沉淀硬化模拟,合金X-750。 重点是这些降解现象的潜在科学所闻名的基础知识,而不是在相关的工程后果和补救措施。 (c)2019年由elestvier b.v发布。

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