Quantity evaluation of gamma radiation shielding performance of concrete container which have damage

2014 Fiscal Year Final Research Report

• Project/Area Number: 25820265
• Research Category: Grant-in-Aid for Young Scientists (B)
• Allocation Type: Multi-year Fund
• Research Field: Building structures/Materials
• Research Institution: Tohoku University
• Principal Investigator: SUZUKI YUSUKE 東北大学, 災害科学国際研究所, 助教 (90635400)
• Project Period (FY): 2013-04-01 – 2015-03-31
• Keywords: 遮蔽コンクリート / 損傷度 / 表面粗さ / γ線遮蔽性能劣化

Outline of Final Research Achievements

This study evaluated the shielding performance of concrete container to store the radioactivity pollutant which occurred by a nuclear plant accident, and shielding performance deterioration of the container which have damage, through experiments and analysis. The following conclusions can be drawn from the research. (1) The simulation system which can choose the most suitable wall-thickness and density of the shielding concrete container according to radioactivity and quantity of the pollutant was constructed. (2) Relationship of the shielding concrete damage surface roughness and the gamma radiation shielding performance deteriolation were studied. In this results, the radiation transmission was decreased according to surface roughness of concrete cracking. In addition, analysis study by Monte Carlo simulation, was able to qualitatively simulate this experiment results.

Free Research Field

コンクリート工学