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核反应堆用奥氏体不锈钢的研究进展

Research progress on austenitic stainless steel for nuclear reactors

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【作者】 王勇陈翠杨洋李维娟庞启航

【Author】 WANG Yong;CHEN Cui;YANG Yang;LI Weijuan;PANG Qihang;School of Materials and Metallurgy,University of Science and Technology Liaoning;Ansteel Iron and Steel Research Institute;

【通讯作者】 李维娟;

【机构】 辽宁科技大学材料与冶金学院鞍钢集团钢铁研究院

【摘要】 核反应堆作为核电站的核心已历经四代更替,核反应堆用钢的安全性和经济性备受行业瞩目。本文综述核反应堆用钢的性能要求和主要类别;重点分析合金化设计中的几类重要元素、成型工艺中的轧制和锻造、热处理工艺中的固溶处理和稳定化处理对核反应堆用奥氏体不锈钢性能的影响;最后对当前核反应堆用钢的发展趋势进行了展望,旨在为核反应堆用钢的设计和开发奠定理论基础。

【Abstract】 As the core of nuclear power plants,nuclear reactors have undergone four generations of replacements,and the safety and economic efficiency of the steel used in nuclear reactors have always attracted industry attention. This paper reviews the performance requirements and main categories of steel used in nuclear reactors;it focuses on analyzing the impact of several important elements in alloy design,rolling and forging in forming processes,and solution treatment and stabilization treatment in heat treatment processes on the performance of austenitic stainless steel used in nuclear reactors. Finally,an outlook on the current development trends of steel used in nuclear reactors was provided,aiming to lay a theoretical foundation for the design and development of steel for nuclear reactors.

  • 【文献出处】 辽宁科技大学学报 ,Journal of University of Science and Technology Liaoning , 编辑部邮箱 ,2024年05期
  • 【分类号】TL34;TM623;TG142.71
  • 【下载频次】14
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