Basic study on reinforced concrete containers for accommodating radioactive incineration ashes

This study aimed at developing a container for accommodating radioactive incineration ashes for the period until final disposal, and prepared specimens and reinforced concrete containers for examining the radiation shielding effects and decontamination methods. In the shielding performance test as the basic performance, specimens made from ferronickel slag, lead glass cullet, and ordinary aggregate had a gamma-ray transmittance of approximately 15% when the thickness was 15 cm. Even in a full-scale prototype container with a wall thickness of 15 mm, the effect of bending cracks was small, and the radiation dose on the outer surface was reduced to about 15% of the inside. It was also confirmed that the surface coating treatment facilitates the decontamination of radioactivity attached to the container. (A.O.)