E202 Development of Numerical Evaluation Methods for Multi-physics Phenomena under Tube Failure Accident in Steam Generator of Sodium-cooled Fast Reactor

2013 ◽  
Vol 2013.18 (0) ◽  
pp. 381-384
Author(s):  
Akihiro UCHIBORI ◽  
Shin KIKUCHI ◽  
Akikazu KURIHARA ◽  
Hirotsugu HAMADA ◽  
Hiroyuki OHSHIMA
Keyword(s):  
Steam Generator ◽  
Fast Reactor ◽  
Numerical Evaluation ◽  
Evaluation Methods ◽  
Tube Failure

scholarly journals 310 Safety Evaluation Experiment on Water-leak Accident in Steam Generator of Sodium-cooled Fast Reactor

2011 ◽  
Vol 2011.19 (0) ◽  
pp. 65-66
Author(s):  
Akikazu KURIHARA ◽  
Kazuhito SHIMOYAMA ◽  
Hirotsugu HAMADA ◽  
Hiroyuki OSHIMA
Keyword(s):  
Steam Generator ◽  
Fast Reactor ◽  
Safety Evaluation ◽  
Water Leak

High cycle fatigue behavior and numerical evaluation of Alloy 690TT steam generator tube

2020 ◽  
Vol 137 ◽  
pp. 105662 ◽  
Author(s):  
Zhenhua Li ◽  
Xinyu Wang ◽  
Junping Wang ◽  
Yonghao Lu ◽  
Tetsuo Shoji
Keyword(s):  
Steam Generator ◽  
Numerical Evaluation ◽  
High Cycle Fatigue ◽  
Fatigue Behavior ◽  
Cycle Fatigue ◽  
Steam Generator Tube
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