Search


Information
ICMST-Tohoku 2018
Oct. 23 - 26, 2018
Sendai, Japan
ICMST-Shenzhen 2016
Nov 1 - 4, 2016
Shenzhen, China
(EXIT THIS PAGE)
ICMST-Kobe 2014
Nov 2(Sun) - 5(Wed), 2014
Kobe, Japan
Nuclear Regulation Authority Outline of the New Safety Standards for Light Water Reactors for Electric Power Generation
For Public Comment
Outline of New Safety Standard (Design Basis)
For Public Comment
New Safety Standards (SA) Outline (Draft)
For Public Comment
Outline of New Safety Standard(Earthquake and Tsunami)(DRAFT)
Issues
 

Vol.10 No.2(Aug)
Vol.10 No.1(May)
Vol.9 No.4(Feb)
Vol.9 No.3(Nov)
< Other Issues

 

Occasional Topics
OTjapan Measures for Tsunami Striking Nuclear Power Station in Japan
Special Article: The Great Tohoku Earthquake (1)
OTjapan The Tragedy of “To Be” Principle in the Japanese Nuclear Industry
EJAMOT_CN3_Figure1_The_outside_view_of_CEFR OTChinaPlanning and Consideration on SFR R&D Activities in China
< All Occasional Topics

Featured Articles
EJAM7-3NT72 A New Mechanical Condition-based Maintenance Technology Using Instrumented Indentation Technique
EJAM7-3NT73 Survey robots for Fukushima Daiichi Nuclear Power Plant

JSM
Contacts
(EJAM): ejam@jsm.or.jp
(JSM): secretariat@jsm.or.jp
HP: http://www.jsm.or.jp
(in English)

 

Vol.4 No.4 previous AA-SP8(49-50-51-52-53-54-55-56-57-58)-NT 53 -54-55

Academic Articles
Regular Paper Vol.5No.1 (2013) p.1 - p.16
 

Theoretical Investigation of Oxidation Mechanism of Fuel Cladding in Light-Water Reactor

 
Yasunori YAMAMOTO1,*, Kazunori MORISHITA2,, Hirotomo IWAKIRI3, and Yasunori KANETA4,
 
1 Graduate School of Energy Science, Kyoto University, Uji, Kyoto, 611-0011, Japan
2 Institute of Advanced Energy, Kyoto University, Uji, Kyoto 611-0011, Japan
3Faculty of Education, University of the Ryukyus, Nakagami-gun, Okinawa 903-0213, Japan
4Akita National College of Technology, Akita, 011-0923, Japan
 
Abstract
Aging management is one of the main issues to keep the safety of currently operating light-water reactors. In many cases plant aging is caused by material’s degradation due to energetic particle irradiation, high temperature, high pressure, etc. In order to keep the safety of light-water reactors, material’s degradation is accurately inspected, and then, based on the results thus obtained the appropriate plant design and timely maintenance should be made. To do so, we should develop the methodology to predict the behavior of materials under severe environments. In the present study, the theoretical and computational investigation was done to understand the mechanism of oxidation process of fuel cladding, which is one of the main degradation processes. Our calculation results have indicated that a difference between the oxidation rates of Zr at normal operating temperature and high temperature may be explained by the stress effect on the diffusion process of an oxygen atom in the oxide film.
 
Keywords
Fuel cladding, Oxidation, First principle calculation, Zirconium, Zirconia, Stress
 
Full Paper: PDF EJAM Vol.5No.1 pp.1-6 "Theoretical Investigation of Oxidation Mechanism of Fuel Cladding in Light-Water Reactor"
Article Information
Article history:
Received 13 November 2012
Accepted 14 March 2013