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Evaluation of a Sodium–Water Reaction Event Caused by Steam Generator Tubes Break in the Prototype Generation IV Sodium-cooled Fast Reactor

机译：蒸汽发生器管引起的钠 - 水反应事件评估原型生成IV钠冷却快堆

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Sang June Ahn; Kwi-Seok Ha; Won-Pyo Chang; Seok Hun Kang; Kwi Lim Lee; Chi-Woong Choi; Seung Won Lee; Jin Yoo; Jae-Ho Jeong; Taekyeong Jeong;
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1. Evaluation of a Sodium-Water Reaction Event Caused by Steam Generator Tubes Break in the Prototype Generation IV Sodium-cooled Fast Reactor [J] . Ahn Sang June, Ha Kwi-Seok, Chang Won-Pyo, Nuclear engineering and technology . 2016,第4期

机译：第四代钠冷快堆中蒸汽发生器管破裂引起的钠水反应事件的评估
2. Evaluation of a Sodium–Water Reaction Event Caused by Steam Generator Tubes Break in the Prototype Generation IV?Sodium-cooled Fast Reactor [J] . Sang June Ahn, Kwi-Seok Ha, Won-Pyo Chang, Nuclear engineering and technology . 2016,第4期

机译：评估IV型钠冷快堆中蒸汽发生器管破裂引起的钠水反应事件
3. Thermal Influence on Steam Generator Heat Transfer Tube During Sodium-Water Reaction Accident of Sodium-Cooled Fast Reactor [J] . Akira Yamaguchi, Takashi Takata, Hiroyuki Ohshima, Nuclear Technology . 2009,第1期

机译：钠冷快堆钠水反应过程中对蒸汽发生器传热管的热影响
4. Development of a Multiphysics Analysis System for Sodium-water Reaction Phenomena in Steam Generators of Sodium-cooled Fast Reactors [C] . Akihiro Uchibori, Akikazu Kurihara, Hiroyuki Ohshima International Conference of Computational Methods in Sciences and Engineering . 2015

机译：钠冷却快速反应器蒸汽发生器中钠水反应现象的多体分析系统的研制
5. High Temperature Creep-Fatigue Behavior of Alloy 709 Austenitic Stainless Steel in Sodium-Cooled Fast Reactors [D] . Alsmadi, Zeinab Yousef. 2020

机译：钠冷却快速反应器中合金709奥氏体不锈钢的高温蠕变行为
6. Development of CVD Silica Membranes Having High Hydrogen Permeance and Steam Durability and a Membrane Reactor for a Water Gas Shift Reaction [O] . Ryoichi Nishida, Toshiki Tago, Takashi Saitoh, 2019

机译：具有高氢渗透性和蒸汽耐久性的CVD二氧化硅膜的开发以及用于水煤气变换反应的膜反应器
7. Evaluation of a Sodium–Water Reaction Event Caused by Steam Generator Tubes Break in the Prototype Generation IV Sodium-cooled Fast Reactor [O] . Ahn Sang June, Ha Kwi-Seok, Chang Won-Pyo, 2016

机译：第四代原型钠冷快堆中蒸汽发生器管破裂引起的钠水反应事件的评估
8. PRELIMINARY DESIGN REPORT-PROTOTYPE STEAM GENERATOR. VOL. 3. EFFECTS OF SODIUM-WATER REACTION ON STEAM GENERATOR. SODIUM-HEATED STEAM GENERATOR DEVELOPMENT [R] . 1965

机译：初步设计报告 - 原型蒸汽发生器。 VOL。 3.钠 - 水反应对蒸汽发生器的影响。钠加热蒸汽发生器开发

Evaluation of a Sodium–Water Reaction Event Caused by Steam Generator Tubes Break in the Prototype Generation IV Sodium-cooled Fast Reactor

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