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核电用奥氏体不锈钢的辐照模拟研究 被引量:5

IRRADIATION SIMULATING RESEARCH ON AUSTENITIC STAINLESS STEELS IN NUCLEAR POWER PLANT
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摘要 叙述了核电用奥氏体不锈钢辐照模拟研究中 ,不同辐照粒子的辐照参数对合金元素偏析的影响 ,并就离子辐照模拟后的辐照肿胀、微结构变化和相关理论计算展开讨论。 This paper compares the effect of irradiation parameters on segregation in austenitic stainless steels with different kinds of particles in irradiation simulating research. The swelling, microstructure evolution and theoretical calculation after ion irradiation are also discussed.
出处 《腐蚀与防护》 CAS 2001年第5期196-201,共6页 Corrosion & Protection
基金 国家基础研究专项经费!(G19990 6 0 5 ) 科研院所社会公益研究专项资金 上海市自然科学基金项目资助
关键词 辐照模拟 奥氏体不锈钢 核电站 辐照肿胀 微结构 Irradiation simulating Austenitic stainless steel Nuclear power plant
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参考文献12

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同被引文献47

  • 1白新德,王社管,马春来,何敬皓,陈鹤鸣,范毓殿.离子轰击模拟中子辐照在核材料研究中的应用[J].原子能科学技术,1996,30(5):469-474. 被引量:7
  • 2段远刚,许斌,唐传宝.围板连接螺栓的辐照促进应力腐蚀裂纹研究[J].核动力工程,2007,28(2):62-65. 被引量:14
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