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Yokozuka, Yuta; Sunaoshi, Mizuho*; Sakai, Tatsuya; Fujikura, Toshiki; Handa, Yuichi; Muraguchi, Yoshinori; Mimura, Ryuji; Terunuma, Akihiro
JAEA-Technology 2021-037, 44 Pages, 2022/03
JAEA-Technology-2021-037.pdf:10.84MB
JAEA has dismantled equipment and instrument in the JAERI's Reprocessing Test Facility (JRTF) since 1996 as a part of its decommissioning. Starting in JFY 2007, in the annex building B which stored liquid waste generated in wet reprocessing tests, the liquid waste storage tank LV-1 installed in the LV-1 room of the first basement was dismantled with the in-situ dismantling method. The dismantling work is described in this report. Data on manpower, radiation control, and waste in the preparation work were collected, and its work efficiency was analyzed.
Yokozuka, Yuta; Sunaoshi, Mizuho*; Fujikura, Toshiki; Suzuki, Shota; Muraguchi, Yoshinori; Handa, Yuichi; Mimura, Ryuji; Terunuma, Akihiro
JAEA-Technology 2020-017, 56 Pages, 2021/01
JAEA-Technology-2020-017.pdf:7.88MB
JAEA has dismantled equipment and instrument in the JAERI's Reprocessing Test Facility (JRTF) since 1996 as a part of its decommissioning. Starting in JFY 2007, in the annex building B which stored liquid waste generated in wet reprocessing tests, the liquid waste storage tank LV-1 installed in the LV-1 room of the first basement was dismantled with the in situ dismantling method. The dismantling preparation work is described in this report. Data on manpower, radiation control, and waste in the preparation work were collected, and its work efficiency was analyzed.
Kawatsuma, Shinji; Mimura, Ryuji; Asama, Hajime*
ROBOMECH Journal (Internet), 4, p.6_1 - 6_7, 2017/02
It was cleared that portability of emergency response reconnaissance robot had been very important. So, RESQ-A robots, which had been developed by Japan Atomic Energy Research Institute (present Japan Atomic Energy Agency), had been considered from the view point of portability. After Fukushima Daiichi NPPs' accidents occurred, JAEA had modified a RESQ-A robot to JAEA-3 robot in order to meet the anticipated situation of the accidents. However, actual situation was beyond the anticipated situation, and additional modification was required. The actual confused situation was many rubble were scattered and temporary cables and hoses were constructed in the reactor buildings, so that reconnaissance robots should be conveyed by operators through limited route, should be reassembled in short time and should be able to remove cable and tiers for reduce the operators' exposure dose during maintenance. JAEA modified again JAEA-3 robot system, with cooperation of operators from Fukushima Daiichi NPPs. It was lesson learned that emergency response reconnaissance robot needed to be unitized for portability, and "Unitization Policy for emergency response reconnaissance robot" was developed.
Terunuma, Akihiro; Mimura, Ryuji; Nagashima, Hisao; Aoyagi, Yoshitaka; Hirokawa, Katsunori*; Uta, Masato; Ishimori, Yuu; Kuwabara, Jun; Okamoto, Hisato; Kimura, Yasuhisa; et al.
JAEA-Review 2016-008, 98 Pages, 2016/07
JAEA-Review-2016-008.pdf:11.73MB
Japan Atomic Energy Agency formulated the plan to achieve the medium-term target in the period of April 2010 to March 2015(hereinafter referred to as "the second medium-term plan"). JAEA determined the plan for the business operations of each year (hereinafter referred to as "the year plan"). This report is that the Sector of Decommissioning and Radioactive Waste Management has summarized the results of the decommissioning technology development and decommissioning of nuclear facilities which were carried out in the second medium-term plan.
Mimura, Ryuji; Muraguchi, Yoshinori; Nakashio, Nobuyuki; Nemoto, Koichi; Shiraishi, Kunio
Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 5 Pages, 2015/05
The JAERI's Reprocessing Test Facility (JRTF) was the first engineering-scale reprocessing facility constructed in Japan. The JRTF was operated from 1968 to 1969 to reprocess spent fuels from the Japan Research Reactor No.3 (JRR-3). As a result of the operation (total 3 runs) by PUREX process, 200 g of highly purified plutonium (Pu) were extracted. In this operation, about 70 m
of liquid waste was generated and part of this waste, which including Pu, with relatively high radioactivity, was stored in six large tanks. After shutdown of the facility, the JRTF decommissioning program was started in 1990 to develop decommissioning technologies and to obtain experiences and data on dismantling of fuel cycle facilities. Liquid waste in the tanks was treated from 1982 to 1998. Dismantling of tanks started in 2002. The tanks were installed in narrow concrete cells and inside of the cell was high dose area. Dismantling method for the tank is important factor to decide manpower and time for dismantlement. In this paper, in-situ dismantling of the liquid waste storage tank and its preparation work are discussed.
Sudo, Tomoyuki; Mimura, Ryuji; Ishihara, Keisuke; Satomi, Shinichi; Myodo, Masato; Momma, Toshiyuki; Kozawa, Kazushige
JAEA-Technology 2011-015, 24 Pages, 2011/06
JAEA-Technology-2011-015.pdf:2.28MB
The super compactor in the Advanced Volume Reduction Facilities (AVRF) treats metal wastes mainly generated from research reactors in the Nuclear Science Research Institute of JAEA. Those wastes are compacted from one third to one fourth with maximum 2,000-ton force. In the trial operation using simulated wastes, some technical problems were found to be improve for the stable operation. One problem is the motion mechanism for carrying wastes before and after compaction. The other problem is the mechanism for treating the irregular supercompacted products. In this report, we describe the detail and the result of improvement on those problems for the stable operation in the super compactor.
Sudo, Tomoyuki; Nakashio, Nobuyuki; Osugi, Takeshi; Mimura, Ryuji; Ishihara, Keisuke; Satomi, Shinichi; Myodo, Masato; Momma, Toshiyuki; Kozawa, Kazushige
JAEA-Technology 2010-041, 38 Pages, 2011/01
JAEA-Technology-2010-041.pdf:4.73MB
The super compactor in the AVRF treats compactible metal wastes mainly generated from research reactors in the Nuclear Science Research Institute of JAEA. Those wastes are compacted with the maximum about 2,000-ton force. The supercompacted wastes are packed into the container and then immobilized with cementitious materials. The solidified wastes (containing supercompacted wastes) become an object for near surface disposal with artificial barrier. For disposal, the solidified wastes must be satisfied the technical criteria. One of the important indicators is the void ratio in the solidified wastes. In this report, we manufactured the supercompacted wastes with the ordinary treatment method for actual wastes treated in the AVRF and immobilized with a mortar grout. The void ratio of the solidified wastes were evaluated in consideration for concrete vault disposal. As a result, We confirmed the integrity of the solidified wastes from a point of view of void ratio.
三村 竜二; 川妻 伸二; 岡田 尚
斉藤 義彦*
JP, 2012-114348 Patent licensing information Patent publication (In Japanese)
【課題】地表付近の線量率と、人体に影響を及ぼす高さ付近での線量率を同時に測定できると共に、測定地点が変更されても実質的に同一の高さにおける空間の線量率を測定することができる装置及び方法を提供すること。 【解決手段】機器支持ロッド、機器支持ロッドを把持するためのグリップ、機器支持ロッドの一端部に取り付けられたGPS受信機、グリップに関してGPS受信機と反対側の位置において、機器支持ロッドに取り付けられた、第1放射線検出器、第1放射線検出器と一定の間隔を隔てて、機器支持ロッドの一端部と反対側の他端部に取り付けられた、第2放射線検出器、第1及び/又は第2放射線検出器の測定値信号を切替えてその場で表示できると共に、それらの同時測定値信号と測定時のGPS受信機からの位置信号とを外部に送信するための装置であって、グリップよりもGPS受信機側に取り付けられた通信制御装置を備えている。
三村 竜二; 川妻 伸二; 岡田 尚
斉藤 義彦*
JP, 2012-114349 Patent licensing information Patent publication (In Japanese)
【課題】立木や建物の側壁など、垂直面におけるγ線の線量率マップを精確に作成するための装置を提供すること。 【解決手段】伸縮可能なロッドの先端にガイガーミューラ管を取り付け、高所におけるγ線の線量率を測定すると共に、その位置を把握するために、そのGM管と実質的に同位置のロッド上に赤外線発光部を設け、かつロッドの位置から離れた個所に赤外線カメラと可視光カメラを設置して、両者のカメラで撮像された映像を画像処理することで、赤外線発光部の位置とその位置での線量率を、可視光カメラで捉えた測定対象物上に重ねて表示するようにしている。この操作を順次位置を変えながら繰り返すことにより、例えば、建物側壁面などの線量率の分布を建物側壁の可視光写真上に表示する。
Yokozuka, Yuta; Mimura, Ryuji; Fujikura, Toshiki; Muraguchi, Yoshinori; Nemoto, Koichi; Shida, Shigeo
no journal, ,
no abstracts in English
Muraguchi, Yoshinori; Mimura, Ryuji; Nakashio, Nobuyuki; Nemoto, Koichi; Shiraishi, Kunio; Tachibana, Mitsuo
no journal, ,
For the purpose of the development of technology for dismantling and decontamination at the high dose area, 
dismantling method is applied for the liquid waste storage tank (LV-1) which is in the concrete cell at the JRTF. This report describes about the outline of preparatory works before dismantling and the data obtained from its works.
Nakashio, Nobuyuki; Mimura, Ryuji; Muraguchi, Yoshinori; Nemoto, Koichi; Shiraishi, Kunio; Tachibana, Mitsuo; Kubota, Shintaro; Kawagoshi, Hiroshi
no journal, ,
For the purpose of the development of technology for dismantling and decontamination at the high dose area, dismantling method is applied for the liquid waste storage tank (LV-1) which is in the concrete cell at the JRTF. This report describes the outline of the program for dismantling of the LV-1.
Nakashio, Nobuyuki; Muraguchi, Yoshinori; Mimura, Ryuji; Nemoto, Koichi; Shiraishi, Kunio
no journal, ,
no abstracts in English
Arakawa, Yuto; Fujii, Katsutoshi; Mimura, Ryuji; Nakashio, Nobuyuki; Onuma, Isamu; Shishido, Nobuhito; Umehara, Takashi
no journal, ,
no abstracts in English
Mimura, Ryuji; Yokozuka, Yuta; Nemoto, Koichi; Shiraishi, Kunio
no journal, ,
no abstracts in English
Kawatsuma, Shinji; Okada, Takashi; Fukushima, Mineo; Nakai, Koji; Mimura, Ryuji; Kanayama, Fumihiko
no journal, ,
no abstracts in English
Yokozuka, Yuta; Mimura, Ryuji; Fujikura, Toshiki; Nemoto, Koichi; Shida, Shigeo
no journal, ,
no abstracts in English
ray imaging system and reconnaissance platformMimura, Ryuji; Kanayama, Fumihiko; Okada, Takashi; Kawatsuma, Shinji
no journal, ,
no abstracts in English
Mimura, Ryuji; Muraguchi, Yoshinori; Nakashio, Nobuyuki; Nemoto, Koichi; Shiraishi, Kunio
no journal, ,
no abstracts in English
Okada, Takashi; Kawatsuma, Shinji; Fukushima, Mineo; Igarashi, Miyuki; Nakai, Koji; Mimura, Ryuji; Kanayama, Fumihiko
no journal, ,
Due to Tohoku Pacific Ocean earthquake and tsunami in 11 March in 2011, Tokyo Electric Power Co. Fukushima Daiichi Nuclear Power Station lost all power and has occurred accidents for failure of core cooling function. In Japan Atomic Energy Agency it was remodeled the nuclear disaster robot, was developed -ray visualization equipment and has been supporting the accident recovery. This paper is described the lessons learned from the supporting with the nuclear disaster robots and the -ray visualization equipment.
