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Akiyama, Yoichi; Shibanuma, So; Yanagisawa, Kenichi*; Yamada, Taichi; Suzuki, Kenta; Yoshida, Moeka; Ono, Takahiro; Kawabata, Kuniaki; Watanabe, Kaho; Morimoto, Kyoichi; et al.
JAEA-Review 2023-015, 60 Pages, 2023/09
JAEA-Review-2023-015.pdf:4.78MB
Naraha Center for Remote Control Technology Development (NARREC) was established in Japan Atomic Energy Agency to promote a decommissioning work of Fukushima Daiichi Nuclear Power Station (Fukushima Daiichi NPS). NARREC consists of a Full-scale Mock-up Test Building and Research Management Building. Various test facilities are installed in these buildings for the decommissioning work of Fukushima Daiichi NPS. These test facilities are intended to be used for various users, such as companies engaged in the decommissioning work, research and development institutions, educational institutions and so on. The number of NARREC facility uses was 84 in FY2021. We participated booth exhibitions and presentations on the decommissioning related events. Moreover, we also contributed to the development of human resources by supporting the 6th Creative Robot Contest for Decommissioning. As a new project, "Narahakko Children's Classroom" was implemented for elementary school students in Naraha Town. This report summarizes the activities of NARREC in FY2021, such as the utilization of facilities and equipment of NARREC, the development of remote-control technologies for supporting the decommissioning work, arrangement of the remote-control machines for emergency response, and training for operators by using the machines.
Yamada, Taichi; Kawabata, Kuniaki; Abe, Hiroyuki*
JAEA-Technology 2021-033, 18 Pages, 2022/03
JAEA-Technology-2021-033.pdf:1.58MB
This report describes the test procedures for evaluating performances involved in robot arm maneuvering of remotely operated robot utilized for nuclear emergency responses and decommissioning. After the accident at Fukushima Daiichi Nuclear Power Station of the Tokyo Electric Power Company Holdings Inc. (FDNPS) occurred, remotely operated robots have been deployed and utilized in the response tasks. Such post-accident work experience and lessons learned are very valuable for developing the robots in the future. Therefore, we were motivated to develop the test methods for performance evaluation of the robot by referring with such experiences and lessons. In the response and the decommissioning tasks, robots with a robot arm were deployed for door opening, removal objects, decontamination and cleanup and so on. Some of these tasks were conducted in an environment with obstacles by robot arms maneuvering. This report describes test procedures for quantitatively evaluating the performances which are for maneuvering involving in robot arm to approach target objects in an environment with obstacles. A typical course layout and the demonstration of test are also illustrated for the references.
Kawabata, Kuniaki; Yamada, Taichi; Abe, Hiroyuki*
JAEA-Technology 2020-015, 37 Pages, 2020/11
JAEA-Technology-2020-015.pdf:3.81MB
This report describes the test procedures for evaluating running performances of remotely operated robot utilized for nuclear emergency responses and decommissioning. After the accident at Fukushima Daiichi Nuclear Power Station of the Tokyo Electric Power Company Holdings Inc. (FDNPS) occurred, remotely operated robots have been deployed and utilized in the response tasks. Such post-accident work experience and lessons learned are very valuable for developing the robots in the future. Therefore, we were motivated to develop the test methods for performance evaluation of the robot by referring with such experiences and lessons. Based on our examinations, in order to execute the response and decommissioning tasks, the robots are required to run through the space without enough margin and avoiding collisions, to move on stairs while avoiding tumbling or falling down and to drag a cable while avoiding problems caused by the cable entwining around objects. This report describes three test procedures for quantitatively evaluating the performances which are for running narrow passage, climbing up/down on the stairs and running with dragging the cable. Typical course layout and the demonstration of test running are also illustrated for the references.
Kawabata, Kuniaki
Japanese Journal of Applied Physics, 59(5), p.050501_1 - 050501_9, 2020/05
Times Cited Count：13 Percentile：19.78(Physics, Applied)This paper describes the decommissioning work being undertaken at the Fukushima Daiichi Nuclear Power Station of the Tokyo Electric Power Company Holdings Inc.'s (FDNPS) using remote controlled robotic systems, as well as lessons learned from past remote task executions. We also summarize the issues to be considered in promoting safe, steady, and efficient decommissioning based on past experiences. In response to these issues, we are developing test methods for performance evaluation of the robots for nuclear decommissioning, robot simulator for operator proficiency training, and information generation methods to improve the operator's status awareness. The current status of technological development is also described.
Kawabata, Kuniaki
Nihon Robotto Gakkai-Shi, 36(7), p.460 - 463, 2018/09
no abstracts in English
Kawatsuma, Shinji
Dekomisshoningu Giho, (54), p.24 - 33, 2016/09
It has passed more than five years than Tokyo Electric Power Company's Fukushima Daiichi NPPs accidents occurred by huge tsunamis caused by the earthquake in Pacific Ocean Coast of North East District on March 11, 2011. It is very hard for workers to enter and stay for long time to work for decommissioning, because the radiation dose rate in the reactor buildings is too high to extremely high caused by radioactive materials released. Then the Naraha Remote Development Center has been constructed and taken into full operation in April 2016, which center would accelerate the development of remote technologies conducting decommissioning on the behalf of workers. The center is developing robot simulator system and robot performance testing method which could support developing remote operating equipment and devices. Also the center is preparing and operating remote equipment and devices for nuclear emergency response.
Yasuda, Ryo; Matsubayashi, Masahito; Nakata, Masahito; Harada, Katsuya; Amano, Hidetoshi; Ando, Hitoshi*; Sasajima, Fumio; Nishi, Masahiro; Horiguchi, Yoji
JAERI-Tech 2002-001, 23 Pages, 2002/02
JAERI-Tech-2002-001.pdf:3.79MB
Advanced neutron radiography techniques such as neutron imaging plate (NIP) and Computed Tomography (CT) methods have been investigated the practicality for Post Irradiation Examination (PIE). In this work, an unirradiated fuel rod was examined by NIP and CT methods in order to collect the fundamental data for applying these techniques to PIE.The fuel rod is composed of seven-enriched UO2 pellet and two-natural UO2 pellet that are loaded into a Zircaloy tube. There are somewhat difference in the size and shape among those UO2 pellets. A transmitted and cross-sectional images were obtained by NIP and CT methods, respectively.In the NIP image, the difference in the size, shape, and enrichment among the UO2 pellets is obviously recognized. In the case of CT method, the images clearly show the detailed shape of the cross section in the pellets, in addition, the difference in the enrichment between the natural and enriched pellets is recognized.
Ishii, Toshimitsu; Hoshiya, Taiji; Ooka, Norikazu; Inagaki, Terumi*; Nakatani, Takahiko*
Nihon Hihakai Kensa Kyokai Heisei-12-Nendo Shuki Taikai Koken Gaiyoshu, p.105 - 108, 2000/11
no abstracts in English
; Okamoto, Yoshizo*
Hihakai Kensa, 48(10), p.642 - 652, 1999/10
no abstracts in English
Okamoto, Yoshizo*; *;
Hikari Araiansu, 9(9), p.55 - 60, 1998/09
no abstracts in English
; Kaetsu, Isao*; Kusama, Yasuo; Seguchi, Tadao
Hoshasen Kagaku No Rekishi To Mirai; 30-Nen No Ayumi, p.306 - 325, 1990/11
no abstracts in English
; ; ; ; ; Yoshida, Kenzo
EIM-83-116, p.9 - 16, 1983/00
no abstracts in English
Yagi, Toshiaki; Seguchi, Tadao; Yoshida, Kenzo
EIM-83-120, p.45 - 53, 1983/00
no abstracts in English
Kuriyama, Isamu
JAERI-M 9412, 40 Pages, 1981/03
no abstracts in English
Kuriyama, Isamu
Nihon Genshiryoku Gakkai-Shi, 20(1), p.21 - 29, 1978/01
Times Cited Count：0no abstracts in English
;
Keikinzoku Yosetsu, (99), p.123 - 129, 1970/00
no abstracts in English
; ; ; *; *
Nihon Genshiryoku Gakkai-Shi, 12(11), p.642 - 648, 1970/00
no abstracts in English
-containing iron phosphate glassFujisawa, Masaharu*; Takebe, Hiromichi*; Kobayashi, Hidekazu; Amamoto, Ippei
no journal, ,
High level radioactive waste contains a relatively large amount of MoO. Mo is known to be a difficult element to incorporate in nuclear waste glass such as borosilicate glasses. On the other hand, phosphate glasses is able to contain MoO over a wide and continuous compositional range. In this study, the effect of MoO addition on properties of iron phosphate glass is studied. The glass transition temperature was evaluated. The immersion tests were performed according to MCC-2 test method due to evaluate the water durability. The additional effects of MoO are discussed in terms of glass structure.
