RAdio-nuclides Migration DAtasets (RAMDA) on Cement, Bentonite and Rock for TRU Waste Repository in Japan

Mihara, Morihiro  ; Sasaki, Ryoichi

In Japan, some of low-level radioactive wastes (LLW) containing nuclides with long half-lives, such as transuranium (TRU) nuclides, fission products (e.g. iodine- 129) and activation products (e.g. carbon-14), will be generated by the operation and decommissioning of domestic and overseas reprocessing plants for spent nuclear fuel and a domestic MOX fuel fabrication plant. Such wastes are termed "TRU waste". The high activity wastes of them are panned to dispose under deep under-ground in future. The Federation of Electric Power Companies(FEPC) and the Japan Nuclear Cycle Development Institute (JNC) have been caring out the performance assessment (PA) for TRU waste disposal system. In this report, radio-nuclides migration datasets (RAMDA) of cement, bentonite and rocks for the PA are described. RAMDA contains the following dataset: (1)Radio-nuclides solubility (2)Effective diffusion coefficient of radio-nuclide (3)Sorption of radio-nuclide. For the establishment of RAMDA, the long-term evolution of the engineered barriers, such as cement mortar and compacted bentonite, was considered.