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Project Promotion Department; Radioactive Wastes Disposal Center
JAEA-Review 2023-037, 162 Pages, 2024/02
JAEA-Review-2023-037.pdf:2.66MB
For near surface disposal of radioactive wastes generated from research, industrial and medical facilities, Japan Atomic Energy Agency has discussed methods for corresponding to the technical standards on confirmation related to waste disposal, etc. From FY2022, we have established Waste Standards Committee and interim Waste Acceptance Criteria, Waste Package Confirmation Procedure, etc. have been considered. In FY2022, Waste Package Confirmation Procedures of solidified liquid waste and cement filled waste and related standards were discussed. In addition, issues of preparation of Waste Package Confirmation Procedure and rational treatment method for decommissioning wastes were considered. This annual report summarizes the results of discussion in FY2022.
Sakai, Akihiro
Dekomisshoningu Giho, (64), p.24 - 33, 2023/05
Japan Atomic Energy Agency (JAEA) has proceeded with the project of near surface disposal of radioactive waste generated from research facilities, etc. as the implementing body. On the other hand, Nuclear Regulation Authority (NRA) has established the safety regulations and standards for the operation of the disposal facilities. This report outlines the disposal project of JAEA and the development of the regulations and standards for the disposal by NRA.
Sakai, Akihiro
Dai-33-Kai Genshiryoku Shisetsu Dekomisshoningu Gijutsu Koza Tekisuto, p.31 - 63, 2023/02
The Japan Atomic Energy Agency (JAEA) is promoting the project for concrete-vault disposal and landfill-type disposal of radioactive waste generated from research facilities, etc. This report introduces current status of technical development for JAEA's disposal project as following items; (1) kinds of research facilities and characteristics of radioactivity inventory of the waste, (2) the structures of the disposal facilities which JAEA conceptually designed, (3) development of waste acceptance criteria for major radioactive waste for the JAEA disposal facilities, (4) the concept of the criteria for disposal of uranium bearing waste, that has been established in 2021.
Sakai, Akihiro; Hasegawa, Makoto; Sakamoto, Yoshiaki; Nakatani, Takayoshi
Proceedings of International Conference on the Safety of Radioactive Waste Management (Internet), p.98_1 - 98_4, 2016/11
The radioactivity of uranium-bearing waste contaminated by refined uranium increases with the production of its progeny on a long-term timescale. Therefore, the long-term safety concept of the near surface disposal of uranium-bearing waste is very important. The Japan Atomic Energy Agency (JAEA) examines disposal safety by controlling the average uranium radioactivity concentration in each section of disposal facility and performing safety assessment for very conservative assumptions.
Okoshi, Minoru; Yoshimori, Michiro; Abe, Masayoshi
Planning and Operation of Low Level Waste Disposal Facilities IAEA-SM-341/70, 0(0), p.416 - 425, 1997/00
no abstracts in English
Abe, Masayoshi; Okoshi, Minoru; Yoshimori, Michiro
Dekomisshoningu Giho, 0(15), p.50 - 58, 1996/12
no abstracts in English
Okoshi, Minoru; Yoshimori, Michiro
Proc. of 3rd Japan-Russia Joint Symp. on Radiation Safety, 0, p.75 - 85, 1995/00
no abstracts in English
Takahashi, Tomoyuki; ; Kimura, Hideo; Matsuzuru, Hideo
JAERI-M 91-216, 31 Pages, 1992/01
no abstracts in English
Tsuji, Tomoyuki
no journal, ,
Japan Atomic Energy Agency (JAEA), who conducted the demonstration test on a safe dismantling of Japan Power Demonstration Reactor (JPDR) in Nuclear Science Research Institute, has been performing the safe demonstration test of near-surface disposal of very low level (VLL) concrete waste arising from JPDR dismantling. Approximately 1,700 tons of VLL concrete wastes were placed in a simple disposal facility, of which dimensions are 45 m
16 m and 3.5 m in depth without any engineered barrier, and covered with soil of 2.5 m thickness. The safe demonstration test of near-surface disposal of VLL concrete waste consists of a operation stage (FY 1995-1996) and a management stage (FY 1996-2024). In the operation stage, radiation dose around the disposal facility was measured, and radioactivity concentrations in groundwater and soil were analyzed. After we proceeded the management stage of disposal, radiation monitoring was continued additionally for 3 years in the management stage. An inspection such as no outflow, crack and subsidence of the covered soil is conducted at once a week. The radiation monitoring data is planned to storage properly by management department until the finishing of management stage, and an inspection data is stored in accordance with the Act on the Regulation of Nuclear Source Material, Nuclear Fuel Material and Reactors.
Sakai, Akihiro
no journal, ,
Japan Atomic Energy Agency (JAEA) is promoting the project for near surface disposal of low-level radioactive waste generated from research facilities, etc. Since a function to reduce infiltration water into the cover soil is needed at trench facilities for very low-level waste, we are calculating the infiltration water through the cover soil which is installed in various composition and parameters of the impermeable sheet, low permeable soil layer and drainage layer by using the HELP code developed by EPA and a calculation code by two-dimensional finite element method. This report outlines these studies that have been conducted on the impermeable function of the trenching facilities.
