Low-level Radioactive Waste (LLW) generated at nuclear facilities in Japan will be disposed by either of the following methods; “sub-surface disposal”, “pit disposal”, and“trench disposal”. The “pit disposal” is disposal of the waste packages in near surface disposal facilities provided with engineered barriers. The solid waste such as steel are stored in drums, and then solidified as a mixture using cement-based fillers. There is concern that the volume expansion due to the change of the metal into the corrosion product will affect the barrier function. Estimation of volume ratio before and after corrosion of metal is required.
In the present study, the composition of the precipitate synthesized from the iron sulfate aqueous solution was evaluated and the volume ratio before and after the corrosion was estimated from the density of the product.

Low-level Radioactive Waste, corrosion, metal, volume expansion7th International Workshop on Long-term Prediction of Corrosion Damage in Nuclear Waste Systems (LTC 2019)