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Horiguchi, Kenichi
Gijutsushi, 30(4), p.8 - 11, 2018/04
The verification activity and training of operation in the Fukushima-Daiichi Nuclear Power Station are more important than another Nuclear Power Station. At the JAEA Naraha Remote Technology Development Center, it has being carried out the development work to apply to the decommissioning work by using the full sized mock up and VR system which is built based on location surveying data of inside the reactor building. It is able to contribute to the decommissioning more reliably and efficiently.
Kawabata, Kuniaki; Mori, Fumiaki*; Shirasaki, Norihito; Tanifuji, Yuta; Hanari, Toshihide
Proceedings of 2017 IEEE/SICE International Symposium on System Integration (SII 2017), p.450 - 455, 2018/02
This paper describes the test facilities and experimental environments for supporting the decommissioning of the nuclear facilities especially Fukushima Daiichi Nuclear Power Station by remote operation. Naraha Remote Technology Development Center of Japan Atomic Energy Agency is an institution for such purpose. Mock-up staircase, robot testing pool and motion capture arena are already installed and full service and support began from April, 2016. We are also designing and developing some experimental environment for remotely operated robots for nuclear decommissioning. In this paper, we describe current status and development of test facilities of Naraha Remote Technology Development Center, Japan Atomic Energy Agency.
Onozuka, Masanori*; Alfile, J. P.*; Aubert, P.*; Dagenais, J.-F.*; Grebennikov, D.*; Ioki, Kimihiro*; Jones, L.*; Koizumi, Koichi; Krylov, V.*; Maslakowski, J.*; et al.
Fusion Engineering and Design, 55(4), p.397 - 410, 2001/09
Times Cited Count：25 Percentile：84.31(Nuclear Science & Technology)Development of welding, cutting and non-destructive testing (NDT) techniques, and development of remotized systems, have been conducted for on-site manufacturing and maintenance of the thick wall structure of the ITER vacuum vessel (VV). Conventional techniques, including TIG (tungsten inert gas) welding, plasma cutting and ultrasonic inspection, have been improved and optimized for the application to thick austenitic stainless steel plates. In addition, advanced methods have been investigated including reduced-pressure electron-beam and multi-pass NdYAG (neodymium-doped yttrium aluminum garnet) laser welding, NdYAG laser cutting, and EMAT (electro-magnetic acoustic transducer) inspection to improve cost and technical performance. Two types of remotized systems with different payloads have been investigated and one of them has been fabricated and demonstrated in field joint welding, cutting, and NDT tests on test mockups and full-scale ITER VV sector models. The progress and results of this development to date provide a high level of confidence that the manufacturing and maintenance of the ITER VV is feasible.
Morita, Yosuke; Udagawa, Akira
Genshiryoku eye, 44(5), p.40 - 45, 1998/05
no abstracts in English
Kawamura, Hiroshi
no journal, ,
no abstracts in English
Sumi, Hirotaka; Nakayama, Jiro; Kuboki, Michikatsu; Kodaka, Akira; Fujiwara, Koji
no journal, ,
no abstracts in English
Kawabata, Kuniaki; Mori, Fumiaki*; Shirasaki, Norihito; Tanifuji, Yuta; Hanari, Toshihide
no journal, ,
This paper describes the development of test fields for decommissioning works by remotely operated machines. Especially, prototypes that imitate penetrations for accessing inside of the Primary Containment Vessel were designed. Penetrations are the pipes; three types of penetration with different inner diameter are developed by referring to real size. Some elbow-type pipes are also prepared to configure various piping route. The prototypes and some peripheral facilities for testing the machines are described.
Kawabata, Kuniaki
no journal, ,
no abstracts in English
