发明名称 Radioactive waste solidification method
摘要 A radioactive waste (zeolite to which Cs-137 was adsorbed) in a waste tank and a glass raw material (soda lime glass) in a glass raw material tank are supplied into a solidifying vessel. Graphite in a graphite tank is also supplied into the solidifying vessel. The solidifying vessel is filled with a mixture of the radioactive waste, glass raw material, and graphite and is then disposed in an adiabatic vessel. The radioactive waste and glass raw material in the adiabatic vessel are heated by thermal energy generated due to radiation emitted from Cs-137. The heat is transferred to the peripheral portion of the solidifying vessel through the graphite, raising the temperature of the peripheral portion. The glass raw material is melted and enters clearances among the radioactive waste, producing a vitrified radioactive waste. This radioactive waste solidification method can shorten a time taken to produce a vitrified radioactive waste.
申请公布号 US9336914(B2) 申请公布日期 2016.05.10
申请号 US201514799997 申请日期 2015.07.15
申请人 Hitachi-GE Nuclear Energy, Ltd. 发明人 Itou Tsuyoshi;Noshita Kenji;Asano Takashi
分类号 G21F9/16;G21F9/30 主分类号 G21F9/16
代理机构 Crowell & Moring LLP 代理人 Crowell & Moring LLP
主权项 1. A radioactive waste solidification method comprising steps of: supplying a radioactive waste including a radioactive nuclide, a glass raw material, and graphite into a first vessel; disposing the first vessel in which the radioactive waste, the glass raw material, and the graphite exist, in an adiabatic area in a second vessel; heating the radioactive waste and the glass raw material existing in the first vessel disposed in an adiabatic area in the second vessel by heat generated by radiation emitted from the radioactive nuclide and melting the glass raw material in the first vessel; and producing a vitrified radioactive waste by the melt of the heated glass raw materials.
地址 Hitachi-shi JP