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Sakasegawa, Hideo
ENEKAN, 20, p.20 - 23, 2022/07
no abstracts in English
Asakura, Kazuki; Shimomura, Yusuke; Donomae, Yasushi; Abe, Kazuyuki; Kitamura, Ryoichi; Miyakoshi, Hiroyuki; Takamatsu, Misao; Sakamoto, Naoki; Isozaki, Ryosuke; Onishi, Takashi; et al.
JAEA-Review 2021-020, 42 Pages, 2021/10
The disposal of radioactive waste from the research facility need to calculate from the radioactivity concentration that based on variously nuclear fuels and materials. In Japan Atomic Energy Agency Oarai Research and Development Institute, the study on considering disposal is being advanced among the facilities which generate radioactive waste as well as the facilities which process radioactive waste. This report summarizes a study result in FY2020 about the evaluation method to determine the radioactivity concentration in radioactive waste on Oarai Research and Development Institute.
Nakagawa, Akinori; Oyokawa, Atsushi; Murakami, Masashi; Yoshida, Yukihiko; Sasaki, Toshiki; Okada, Shota; Nakata, Hisakazu; Sugaya, Toshikatsu; Sakai, Akihiro; Sakamoto, Yoshiaki
JAEA-Technology 2021-006, 186 Pages, 2021/06
Radioactive wastes generated from R&D activities have been stored in Japan Atomic Energy Agency. In order to reduce the risk of taking long time to process legacy wastes, countermeasures for acceleration of waste processing and disposal were studied. Work analysis of waste processing showed bottleneck processes, such as evaluation of radioactivity concentration, segregation of hazardous and combustibles materials. Concerning evaluation of radioactivity concentration, a radiological characterization method using a scaling factor and a nondestructive gamma-ray measurement should be developed. The number of radionuclides that are to be selected for the safety assessment of the trench type disposal facility can decrease using artificial barriers. Hazardous materials, will be identified using records and nondestructive inspection. The waste identified as hazardous will be unpacked and segregated. Preliminary calculations of waste acceptance criteria of hazardous material concentrations were conducted based on environmental standards in groundwater. The total volume of the combustibles will be evaluated using nondestructive inspection. The waste that does not comply with the waste acceptance criteria should be mixed with low combustible material waste such as dismantling concrete waste in order to satisfy the waste acceptance criteria on a disposal facility average. It was estimated that segregation throughput of compressed waste should be increased about 5 times more than conventional method by applying the countermeasures. Further study and technology development will be conducted to realize the plan.
Asakura, Kazuki; Shimomura, Yusuke; Donomae, Yasushi; Abe, Kazuyuki; Kitamura, Ryoichi
JAEA-Review 2020-015, 66 Pages, 2020/09
The disposal of radioactive waste from the research facility need to calculated from the radioactivity concentration that based on variously nuclear fuels and materials. In Japan Atomic Energy Oarai Research and Development Institute, the study on considering disposal is being advanced among the facilities which generate radioactive waste as well as the facilities which process radioactive waste. This report summarizes a study result in FY2019 about the evaluation method to determine the radioactivity concentration in radioactive waste on Oarai Research and Development Institute.
Sato, Kazuhiko; Yagi, Naoto; Nakagiri, Toshio
Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 6 Pages, 2019/05
no abstracts in English
Ishihara, Keisuke; Yokota, Akira; Kanazawa, Shingo; Iketani, Shotaro; Sudo, Tomoyuki; Myodo, Masato; Irie, Hirobumi; Kato, Mitsugu; Iseda, Hirokatsu; Kishimoto, Katsumi; et al.
JAEA-Technology 2016-024, 108 Pages, 2016/12
Radioactive isotope, nuclear fuel material and radiation generators are utilized in research institutes, universities, hospitals, private enterprises, etc. As a result, various low-level radioactive wastes (hereinafter referred to as non-nuclear radioactive wastes) are produced. Disposal site for non-nuclear radioactive wastes have not been settled yet and those wastes are stored in storage facilities of each operator for a long period. The Advanced Volume Reduction Facilities (AVRF) are built to produce waste packages so that they satisfy requirements for shallow underground disposal. In the AVRF, low-level beta-gamma solid radioactive wastes produced in the Nuclear Science Research Institute are mainly treated. To produce waste packages meeting requirements for disposal safely and efficiently, it is necessary to cut large radioactive wastes into pieces of suitable size and segregate those depending on their types of material. This report summarizes activities of pretreatment to dispose of non-nuclear radioactive wastes in the AVRF.
Wada, Ryutaro*; Yoshinaka, Kazuyuki
Gijutsushi, 28(11), p.4 - 7, 2016/11
It is one of the important subjects for decommissioning to establish the safe and effective waste management. Research and Development programs on the waste management for Fukushima-Daiichi as it differs from normal practices are conducted by IRID. We show the outline of the lecture presented by Mr.Miyamoto, Deputy Director of IRID.
Hagiwara, Shigeru*; Sakamoto, Yoshiaki; Takebe, Shinichi; Ogawa, Hiromichi; Nakayama, Shinichi
JAERI-Review 2002-038, 107 Pages, 2002/12
For the disposal of radioactive waste arising from radioactive utilization facilities and nuclear facilities, it is necessary to establish the disposal system in proportion to half-lives of radionuclides and radioactivity concentration in the waste. It is important to grasp the features of the earth scientific phenomena and geological structure of our country for the disposal system of radioactive waste. Then, for the porpose of the survey of the geological characteristics around the Japanese Islands whole neiborhood, the earth scientific phenomena at present, geological structure and geotectonic history were summarized on the basis of the existing literatures.
5th NUCEF Seminar Working Group
JAERI-Conf 2001-015, 92 Pages, 2001/12
no abstracts in English
4th NUCEF Seminar Working Group
JAERI-Conf 2000-012, 52 Pages, 2000/07
no abstracts in English
Maekawa, Hiroshi; Mukaiyama, Takehiko; Yamane, Tsuyoshi; *; *; Suzuki, Atsuyuki*; Takeda, Renzo*; *; Kawashima, Masatoshi*; *; et al.
Nihon Genshiryoku Gakkai-Shi, 40(12), p.963 - 965, 1998/12
no abstracts in English
Onuki, Toshihiko; Muraoka, Susumu; Bamba, Tsunetaka
JAERI-Review 98-014, 112 Pages, 1998/10
no abstracts in English
Sakamoto, Yoshiaki
Isotope News, (532), p.10 - 12, 1998/09
no abstracts in English
JAERI-Conf 98-010, 47 Pages, 1998/06
no abstracts in English
JAERI-Conf 97-002, 28 Pages, 1997/02
no abstracts in English
Tsujino, Takeshi
Genshiryoku Shisutemu Nyusu, 6(3), p.15 - 20, 1995/12
no abstracts in English
; ; ; ; ; *; ; ; ; Araki, Kunio; et al.
JAERI-M 8485, 74 Pages, 1979/10
no abstracts in English
;
JAERI-M 7138, 46 Pages, 1977/06
no abstracts in English
Nenryo Kyokai-Shi, 54(577), p.306 - 313, 1975/00
no abstracts in English