ICMST-Tohoku 2018
Oct. 23 - 26, 2018
Sendai, Japan
ICMST-Shenzhen 2016
Nov 1 - 4, 2016
Shenzhen, China
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)

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

(in English)


Vol.9 No.3previous AASP18(143-144-145-146-147) NT86-87

Academic Articles
Regular Paper Vol.9 No.3 (2017) p.164 - p.167

Study on Material Properties of Concrete Structures Exposed to Extremely High Temperature due to Severe Accident

Yuma Sato1, Do Thi-Mai-Dung1, Masahide Suzuki1

1 Nagaoka University of Technology, 1603-1 Kamitomioka-cho, Nagaoka, Niigata 940-2188, Japan

In March 2011, the Fukushima Nuclear Power Plant suffered a severe accident because of the tsunami waves when the Great East Japan Earthquake occurred and because of this accident the containment vessel was exposed to high temperatures. However, studies related to concrete with extremely high temperature exposure are very few. For this reason, the aim of this study is to understand the structural soundness of the concrete structures exposed to high temperature by conducting heating experiments of concrete specimens which were made to reproduce the concrete structure of the Nuclear Plant. From the test results, cracks were observed at the specimen surface and they grew with the increase of temperature. Additionally, it was observed that concrete crack volume grew to temperatures around 800°C, but this growth saturated more than this temperature to 1000°C. It was observed that the amount of water content inside concrete decreased with temperature. Moreover, the chemical composition change of concrete was accompanied with the water content decrease. Results on other material properties are also to be presented.
severe accident, containment vessel, concrete, high temperature, crack
Full Paper: PDF
Article Information
Article history:
Received 12 October 2016
Accepted 29 May 2017