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Sonobe, Hitoshi
JAEA-Review 2008-001, 37 Pages, 2008/03
JAEA-Review-2008-001.pdf:3.17MB
In the Japan Atomic Energy Agency, it has been conducted aggressively since the previous organization, and the achieved results has been reflected to the documents related to the decision of a basic idea of the safety regulation for disposal of the high-level radioactive waste etc. The Power Reactor and Nuclear Fuel Development Corporation and Japan Nuclear Cycle Development Institute, predecessors of the Japan Atomic Energy Agency, have developed the geological disposal technology of the high-level radioactive waste to contribute the implementation of disposal and the safety regulation. This report presents outline of the safety research conducted up to now: the policy, the plan of the safety research on the high-level radioactive waste disposal, the summary of results, and future studies required.
Yamada, Fumitaka; Sonobe, Hitoshi; Igarashi, Hiroshi
JAEA-Review 2007-061, 67 Pages, 2008/02
JAEA-Review-2007-061.pdf:8.39MB
In JAEA, various systems associated with the collaboration with industries and universities are enacted. These systems have been operated considering the needs of JAEA's program, industry and academia, resultantly contributed, for example, to basic research and the project development. Activities under these systems contain personal exchanges, the publication of the accomplishments and utilization of those, in R&D concerning geological disposal technology of HLW. These activities have progressed in PNC and JNC, through JAEA. The accomplishments from these systems have contributed to the advancement of the national program on the geological disposal of HLW. In this report, the progress of the R&D under these systems was investigated from the beginning of their operation. The contribution to the R&D on geological disposal technology of HLW was also studied. On the basis of these studies, the future utilization of the systems of the collaboration was also discussed.
Umeki, Hiroyuki; Osawa, Hideaki; Sonobe, Hitoshi; Miyamoto, Yoichi
Dai-5-Kai Anzen Kenkyu Seika Hokokukai Koenrokushu; Hoshasei Haikibutsu No Chiso Shobun Ni Tsuite, p.5 - 29, 2006/03
no abstracts in English
Kato, Tomoko; Fujishima, Atsushi; Ueno, Kenichi; ; Notoya, Shin; Sonobe, Hitoshi
JNC TN8450 2001-003, 205 Pages, 2001/01
JNC-TN8450-2001-003.pdf:77.1MB
We have compiled and refined the information materials to explain ENTRY (Engineering Scale Test and Research Facility) and QUALITY (Quantitative Assessment Radionuclide Migration Experimental Facility). These include information materials to show activities for research and development of radioactive waste disposal in Tokai Works such as panels of experimental equipments. This work was carried out by a working group in Waste Isolation Research Division, Waste Management and Fuel Cycle Research Center; Tokai Works in 1998
2000. We have developed database for above information materials including typical experimental equipments of ENTRY and QUALITY. In the future, it can be easily refind in case of reconstruction of the experimental equipments. This report presents the database including the experimental equipments and several pamphlet.
Ashida, Takashi; Sonobe, Hitoshi; Yamada, Kazuo
PNC TN8600 91-003, 38 Pages, 1991/06
no abstracts in English
Ishiguro, Katsuhiko; Kawamura, Kazuhiro; Sonobe, Hitoshi; Nodaka, Masayuki*; Arai, Takashi; Yusa, Yasuhisa; Tsunoda, Naomi
PNC TN8410 87-071, 37 Pages, 1987/08
Experimental studies have been carried out in order to evaluate durability of engineered barriers in geological disposal system. These are as follows; (1) Leaching behavior of waste borosilicate glass. Leaching experiments of simulated waste glass were carried out for more than one year in both scale of laboratory and of engineering. The leachability was suppressed under the condition of high SA/V (the surface area of glass/leachant volume). Saturation of leachant with silicon reduces leaching rates of the other elements. (2) Corrosion behavior of candidate overpack materials. Corrosion behavior of carbon steel and titanium was studied in synthetic groundwater with or without bentonite. No localized corrosion was observed in both the materials. Corrosion rate of carbon steel depends on bentonite/water ratio. Crevice corrosion resistance of titanium and its alloy was also studied. (3) Permeability of compacted bentonite as buffer material. Hydraulic conductivity of saturated compacted bentonite decreases and the swelling pressure increases with the increase of density. Influence of cracks on permeability was also studied, and significant effect was not observed. Infiltration of water into dry compacted bentonite was also studied to evaluate permeability of buffer material at the initial stage of disposal.