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Evaluation Methods for Corrosion Damage of Components in Cooling Systems of Nuclear Power Plants by Coupling Analysis of Corrosion and Flow Dynamics (II): Evaluation of Corrosive Conditions in PWR Secondary Cooling System

机译：通过腐蚀和流动动力学耦合分析（II）耦合分析：PWR二次冷却系统中腐蚀条件的腐蚀损伤腐蚀损伤的评价方法

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Shunsuke UCHIDA; Masanori NAITOH; Yasushi UEHARA; Hidetoshi OKADA; Naoki HIRANUMA; Wataru SUGINO; Seiichi KOSHIZUKA;
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1. Evaluation Methods For Corrosion Damage Of Componentsin Cooling Systems Of Nuclear Power Plantsrnby Coupling Analysis Of Corrosion And Flow Dynamics (ii):rnevaluation Of Corrosive Conditions In Pwr Secondary Cooling System [J] . Shunsuke UCHIDA, Masanori NAITOH, Yasushi UEHARA, Journal of nuclear science and technology . 2008,第12期

机译：腐蚀与流动动力学耦合分析的核电厂冷却系统部件腐蚀损伤评估方法（ii）：Pwr二次冷却系统腐蚀条件的重新评估
2. Evaluation Methods for Corrosion Damage of Components in Cooling Systems of Nuclear Power Plants by Coupling Analysis of Corrosion and Flow Dynamics (IV) Comparison of Wall Thinning Rates Calculated with the Coupled Model of Static Electrochemical Analysis and Dynamic Double Oxide Layer Analysis and Their Values Measured at a PWR Plant [J] . Shunsuke UCHIDA, Masanori NAITOH, Yasushi UEHARA, Journal of nuclear science and technology . 2010,第2期

机译：腐蚀与流动动力学耦合分析评价核电厂冷却系统各部件的腐蚀损伤（IV）静态电化学分析与动态双氧化物层分析耦合模型计算壁厚率的比较及其在压水堆厂
3. Evaluation Methods for Corrosion Damage of Components in Cooling Systems of Nuclear Power Plants by Coupling Analysis of Corrosion and Flow Dynamics (V) Flow-Accelerated Corrosion under Single- and Two-phase Flow Conditions [J] . Hidetoshi OKADA, Shunsuke UCHIDA, Masanori NAITOH, Journal of nuclear science and technology . 2011,第1期

机译：单相和两相流动条件下腐蚀与流动动力学（V）流动加速腐蚀耦合分析的核电厂冷却系统部件腐蚀损伤评估方法
4. Evaluation of Flow Accelerated Corrosion of PWR Secondary Piping by Coupling Analysis of Corrosion and Flow Dynamics [C] . S. Uchida, M. Naitoh, Y. Uehara, Corrosion conference and expo 2009 . 2009

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5. Corrosion control in thermoelectric power plant cooling systems using impaired waters as alternative sources. [D] . Hsieh, Ming-Kai. 2009

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7. Evaluation Methods for Corrosion Damage of Components in Cooling Systems of Nuclear Power Plants by Coupling Analysis of Corrosion and Flow Dynamics (III) [O] . Shunsuke UCHIDA, Masanori NAITOH, Yasushi UEHARA, 2009

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8. ARMY GAS-COOLED REACTOR SYSTEMS PROGRAM PECAN II A Cycle Analysis Code for Gas Turbine, Nuclear or Conventional Power Plants, Modified for Problems Involving Intercooled Compressors (IBM 704 Computer) [R] . S. Luchter, P. J. Du Bois 1962

机译：aRmY气体冷却反应堆系统计划pECaN II燃气轮机，核电站或常规电厂的循环分析代码，针对涉及中间冷却压缩机的问题进行了修改（IBm 704计算机）

Evaluation Methods for Corrosion Damage of Components in Cooling Systems of Nuclear Power Plants by Coupling Analysis of Corrosion and Flow Dynamics (II): Evaluation of Corrosive Conditions in PWR Secondary Cooling System

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