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JAEA Reports

In-situ dismantling of the liquid waste storage tank LV-1 in the JRTF; The Dismantling preparation work

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.

Journal Articles

Unitization for portability of emergency response surveillance robot system; Experiences and lessons learned from the deployment of the JAEA-3 emergency response robot at the Fukushima Daiichi Nuclear Power Plants

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.

JAEA Reports

Decommissioning activities and R&D of nuclear facilities in the second midterm plan

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.

Journal Articles

In-situ dismantling of the liquid waste storage tank in the decommissioning program of the JRTF

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$$^{3}$$ 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.

JAEA Reports

Improvement for the stable operation in the super compactor

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.

JAEA Reports

Evaluation of void ratio of the solidified wastes containing supercompacted wastes

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.

Oral presentation

Summary and lesson learned on nuclear disaster robots of JAEA in the accident at Fukushima Daiichi Nuclear Power Station

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 $$gamma$$-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 $$gamma$$-ray visualization equipment.

Oral presentation

Remote operation technology applied for the Fukushima Daiichi Nuclear Power Plant accident, 1; Summary on activities of remote operation technology in JAEA

Kawatsuma, Shinji; Okada, Takashi; Fukushima, Mineo; Nakai, Koji; Mimura, Ryuji; Kanayama, Fumihiko

no journal, , 

no abstracts in English

Oral presentation

Remote operation technologies applied for the Fukushima Daiichi Nuclear Power Plant accident, 3; Development of $$gamma$$ ray imaging system and reconnaissance platform

Mimura, Ryuji; Kanayama, Fumihiko; Okada, Takashi; Kawatsuma, Shinji

no journal, , 

no abstracts in English

Oral presentation

Development of dose mapping system for environment

Mimura, Ryuji

no journal, , 

no abstracts in English

Oral presentation

Treatment test of decontamination wastes using a pilot-scale pyrolysis furnace, 3; Heat-treatment test of paddy soil in Iitate-village

Osugi, Takeshi; Nakashio, Nobuyuki; Mimura, Ryuji; Nonaka, Kazuharu; Nakanishi, Yoshiki; Okoshi, Minoru; Tokizawa, Takayuki; Nakayama, Shinichi; Kimura, Takeshi*

no journal, , 

To reduce volume of wastes that consisted of plants and soil generated from decontamination works on farmland, we have produced a pilot-scale pyrolysis furnace by rotary kiln type and had some heat-treatment tests. In this reports, we shows some results of the tests on two kinds of paddy soils in Iitate-village.

Oral presentation

Development of radiation measurement technology, Emergency response for Fukushima Dai-ichi Nuclear Power Plant accident; Development of a $$gamma$$-ray visualization (Emergency response for Fukushima Dai-ichi Nuclear Power Plant accident) Summary of JR-1 (JAEA Reconnaissance 1)

Mimura, Ryuji; Okada, Takashi; Igarashi, Miyuki

no journal, , 

Introduce of radiation measurements and remote robot, about JAEA emergency response for Fukushima Dai-ichi Nuclear Power Plant accident.

Oral presentation

In-situ dismantling of the liquid waste storage tank LV-1 in JRTF, 2; Preparatory works before dismantling

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, ${it in-situ}$ 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.

Oral presentation

In-situ dismantling of the liquid waste storage tank LV-1 in JRTF, 1; An Outline of the dismantling program

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, ${it in-situ}$ 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 ${it in-situ}$ dismantling of the LV-1.

Oral presentation

In-situ dismantling of the liquid waste storage tank LV-1 in JRTF, 3; Evaluation of the radioactivity inventory of LV-1

Kubota, Shintaro; Kawagoshi, Hiroshi; Tachibana, Mitsuo; Muraguchi, Yoshinori; Mimura, Ryuji; Nakashio, Nobuyuki; Nemoto, Koichi; Shiraishi, Kunio

no journal, , 

no abstracts in English

Oral presentation

In-situ dismantling of the liquid waste storage tank LV-1 in JRTF, 5; Removal of the radioactive residue and decontamination in LV-1

Nakashio, Nobuyuki; Muraguchi, Yoshinori; Mimura, Ryuji; Nemoto, Koichi; Shiraishi, Kunio

no journal, , 

no abstracts in English

Oral presentation

In-situ dismantling of the liquid waste storage tank LV-1 in JRTF, 4; The Plan for removal of the radioactive residue from LV-1

Mimura, Ryuji; Muraguchi, Yoshinori; Nakashio, Nobuyuki; Nemoto, Koichi; Shiraishi, Kunio

no journal, , 

no abstracts in English

Oral presentation

The Radiation control for the decontamination and recovery of high concentration radioactive residue in the waste storage tank

Arakawa, Yuto; Fujii, Katsutoshi; Mimura, Ryuji; Nakashio, Nobuyuki; Onuma, Isamu; Shishido, Nobuhito; Umehara, Takashi

no journal, , 

no abstracts in English

Oral presentation

In-situ dismantling of the liquid waste storage tank LV-1 in JRTF, 6; Evaluation of the removal procedure of the radioactive residue in LV-1

Kubota, Shintaro; Tachibana, Mitsuo; Mimura, Ryuji; Nemoto, Koichi; Shiraishi, Kunio

no journal, , 

no abstracts in English

Oral presentation

In-situ dismantling of the liquid waste storage tank LV-1 in JRTF, 7; Cutting of LV-1 tank

Mimura, Ryuji; Yokozuka, Yuta; Nemoto, Koichi; Shiraishi, Kunio

no journal, , 

no abstracts in English

24 (Records 1-20 displayed on this page)