[2C06-09] TRU Waste

[2C07] Research and development of TRU waste package

(2) Evaluation of Radiolysis Hydrogen Generation from Waste Package Infill

*Hiroyuki Sakamoto¹, Kumi Negishi², Masaya Ida², Shinya Hasegawa², Naoki Fujii¹, Hitoshi Owada¹ (1. RWMC, 2. Taiheiyo Consultant)

Keywords:TRU Waste, Waste Package Infill, Hydrogen Gas Generation, G-Value, Gamma-ray Irradiation, Cement Pastes, Mortar, Concrete

For geological disposal of TRU waste, it is being considered to store the waste in a waste package container and fill the inside of the waste package with a cement-based material. In this study, we evaluated the amount of hydrogen gas generated by radioactive decomposition of cement-based materials. The amount of hydrogen gas generated from mortar and concrete was evaluated by irradiating with γ-ray of 60Co. It was confirmed that the amount of hydrogen gas generated by radioactive decomposition of the concrete that took measures against hydrogen gas generation can be reduced to 1/10 or less of that of general mortar.