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Sakauchi, Hitoshi; Kikuchi, Yuki; Imaizumi, Haruki; Fukui, Yasutaka
Dekomisshoningu Giho, (57), p.34 - 42, 2018/03
OWTF (Oarai Waste Reduction Treatment Facility) is constructed for volume reduction processing and stabilization treatment of radioactive solid waste, which generate from hot facilities in Oarai Research and Development Center of Japan Atomic Energy Agency, using in-can type high frequency induction heating by remote control. In this report, we describe the outline of OWTF under construction and treatment technologies, in which incinerating and melting.
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
JAEA-Technology-2016-024.pdf:29.74MB
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.
Sakauchi, Hitoshi; Sato, Isamu*; Donomae, Yasushi; Kitamura, Ryoichi
JAEA-Technology 2015-059, 352 Pages, 2016/03
JAEA-Technology-2015-059.pdf:51.53MB
OWTF (Oarai Waste Reduction Treatment Facility) is constructed for volume reduction processing and stabilization treatment of 
solid waste, which was generated from hot facilities in Oarai Research and Develop Center of Japan Atomic Energy Agency, using in-can type high frequency induction heating by remote control. This report describes corroborative tests, in which incinerating and melting performance for OWTF is confirmed with a full-scale testing furnace. We have been carrying out the tests of incinerating and melting treatment with some kinds of simulated wastes, such as enclosure form of radioactive wastes, material and articles.
Nakashio, Nobuyuki; Nakashima, Mikio
Dekomisshoningu Giho, (26), p.45 - 55, 2002/11
Melting treatment of low-level radioactive wastes (LLW) is considered to be a promising technology for the preparation of a stable solid that will be disposed of in near surface repositories. This is because of large reduction of waste volume and production of a stable homogeneous solidified product. In the Japan Atomic Energy Research Institute (JAERI), the construction of the Waste Volume Reduction Facilities (WVRF) has been in progress since 1999. In advance of operation of the WVRF, we have been conducting melting tests of non-metallic solid wastes with the aim of establishing the optimum melting condition for preparation of a stable solid that is suitable for disposal. We have reviewed a part of the melting test conducted in our program.
Hirabayashi, Takakuni; Kameo, Yutaka; Nakashio, Nobuyuki
Proceedings of International Symposium on Technologies for the Management of Radioactive Waste from Nuclear Power Plants and Back End Nuclear Fuel Cycle Activities (CD-ROM), 10 Pages, 1999/00
no abstracts in English
Hirabayashi, Takakuni
Energy Hum., 45, p.14 - 18, 1998/06
no abstracts in English
Hirabayashi, Takakuni;
Kikai No Kenkyu, 48(5), p.18 - 24, 1996/00
no abstracts in English
; Kobayashi, Hiroaki; Masaki, Toshio; ; Kawamura, Kazuhiro; Yoneya, Masayuki;
PNC TN8440 94-028, 173 Pages, 1994/06
None
Fujiki, Kazuo;
EUR-15691, 0, p.133 - 146, 1994/00
no abstracts in English
Yahata, Taneaki
Genshiryoku Kogyo, 39(6), p.21 - 27, 1993/00
no abstracts in English
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solid Waste treatment facilities Conceptual design study; Seki, Sadao*;
PNC TJ9409 91-001, 164 Pages, 1991/02
This report describes the result of conceptual design study concerned with "High Radioactive - Solid Waste Treatment Facilities, "which will be planed for the purpose of volume reduction and stabilization of High Radioactive - solid wastes generated and stocked in the O-arai Engineering Center of PNC. In this conceptual design study the basic process of the facilities, which are sufficient to treat each waste and develop technologies, are clarified. This report consist with: (1)Clarification of waste to be treated. (2)Study on the treatment technology and process. (3)Conceptual design of facilities and equipment. (4)Estimation of construction cost and schedule.
; ; ;
Journal of Nuclear Science and Technology, 17(11), p.865 - 868, 1980/00
Times Cited Count：14 Percentile：88.54(Nuclear Science & Technology)no abstracts in English
猿田 晃一; 直江 崇; 勅使河原 誠; 二川 正敏; 梁 輝
Erkan Nejdet*
JP, 2021-188317 Patent licensing information
【課題】加工により発生するヒュームの大気中への拡散防止およご前記ヒュームを回収可能な加工装置を提供すること。 【解決手段】 加工対象物10の局所部16を溶融するために、前記局所部16を加熱する加熱ヘッド122を備えた加熱装置120と、前記局所部16と前記加熱ヘッド122とを繋ぐ加熱エリア20の外側にミストカバー層40を形成するミスト層形成装置140と、液体からミスト41を生成して前記ミスト層形成装置140に供給するミスト生成装置130と、前記加熱ヘッド122により加熱されて溶融する前記局所部16を前記加工対象物10の加工場所12に沿って移動させる加工位置移動機構30と、を備え、前記ミスト層形成装置140から噴霧された前記ミスト41により、前記加熱エリア20の外周を覆う前記ミストカバー層40を形成した、ことを特徴とする加工装置。
Kato, Mitsugu
no journal, ,
no abstracts in English
