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A Study on Corrosion Behaviors of Ferritic/Martensitic Steels in Liquid Sodium Condition for Sodium-cooled Fast Reactor Application

机译：钠冷却快堆中液态钠条件下铁素体/马氏体钢的腐蚀行为研究

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Department of Nuclear Engineering

机译：核工程系

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Shin Sang Hun;
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年度 2015
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原文格式 PDF
正文语种 en
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2. On-line Corrosion Monitoring Analysis of Ferritic-Martensitic Steels in High Temperature Liquid Sodium Environment: UCFR Application [J] . Sang Hun Shin, Jeong Hyun Lee, Ji Hyun Kim Transactions of the American nuclear society . 2013,第novapta1期

机译：高温液态钠环境中铁素体-马氏体钢的在线腐蚀监测分析：UCFR应用
3. Inelastic Cyclic Deformation Behaviors of Type 316H Stainless Steel for Reactor Pressure Vessel of Sodium-Cooled Fast Reactor at Elevated Temperatures [J] . Yoon Ji-Hyun, Kim Young-Chun, Hong Seokmin, Journal of Korean Institute of Metal and Materials . 2015,第10期

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A Study on Corrosion Behaviors of Ferritic/Martensitic Steels in Liquid Sodium Condition for Sodium-cooled Fast Reactor Application

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