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Journal Articles

Japan Atomic Energy Agency; Contribution to the decommissioning of the Fukushima Daiichi Nuclear Power Station and the reconstruction of Fukushima Prefecture at the Naraha center for Remote Control technology development

Morimoto, Kyoichi; Ono, Takahiro; Kakutani, Satomi; Yoshida, Moeka; Suzuki, Soichiro

Journal of Robotics and Mechatronics, 36(1), p.125 - 133, 2024/02

The Naraha Center for Remote Control Technology Development was established for the purpose of developing and verifying remote control equipment for promoting the decommissioning of the Fukushima Daiichi Nuclear Power Station and the external use of this center was started in 2016. The mission of this center is to contribute to the decommissioning of the Fukushima Daiichi Nuclear Power Station and for the reconstruction of Fukushima Prefecture. In this review, we describe the equipment related to the full-scale mock-up test, the component test for a remote-control device and the virtual reality system in this center. In addition, the case examples for usage of these equipment are introduced.

JAEA Reports

Annual report for FY2016 on the activities of Naraha Center for Remote Control Technology Development (April 1, 2016 - March 31, 2017)

Naraha Center for Remote Control Technology Development, Fukushima Research Insitute

JAEA-Review 2018-014, 52 Pages, 2018/12

JAEA-Review-2018-014.pdf:5.62MB

The Naraha Remote Technology Development Center (Naraha Center) consists of a mock-up test building and a research management building, and various test facilities necessary for the decommissioning work after the accident of TEPCO Fukushima Daiichi Nuclear Power Station are installed. Using these test facilities, a wide range of users, such as companies engaged in decommissioning work, research and development institutions, educational institutions, etc., can efficiently develop robots through characterization and performance evaluation of remote-controlled robots. Furthermore, it is possible to make various uses such as exhibitions that many companies have met together, experts' meetings on decommissioning. This report summarizes the activities of the Naraha Center such as development of remote control technologies, maintenance and training of remote control equipment for emergency response, use of component test areas, and so on in FY2016.

JAEA Reports

Plan of vibration tests for estimation of seismic performance of ITER tokamak

Takeda, Nobukazu; Nakahira, Masataka

JAERI-Tech 2004-073, 59 Pages, 2005/01

JAERI-Tech-2004-073.pdf:11.36MB

The ITER toamak is composed of major components such as superconducting magnet and vacuum vessel whose operation temperatures are changed from room temperature to 4 K and room temperature to 200$$^{circ}$$C, respectively. The gravity support of the tokamak is flexible in order to accept the thermal deformation caused by temperature change. This structural feature causes the complex behaviors of the tokamak during seismic events. Therefore, the mechanical characteristics of the flexible support have to be investigated in detail. The present report describes the global plan of the series of vibration tests to estimate the seismic performance of the ITER tokamak. Although it is ideal that the vibration tests are carried out using a full-scale model, scale models are planned due to the limitation of the test facilities. The test results can be estimated by a scaling law. When the scaling law cannot be applied to some performances, the test is performed using a full-scale model. In addition, the other tests such as vacuum vessel and small-scaled models of the support structure are also planned.

JAEA Reports

Performance test results of mock-up model test facility with a full-scale reaction tube for HTTR hydrogen production system (Contract research)

Inagaki, Yoshiyuki; Hayashi, Koji; Kato, Michio; Fujisaki, Katsuo; Aita, Hideki; Takeda, Tetsuaki; Nishihara, Tetsuo; Inaba, Yoshitomo; Ohashi, Hirofumi; Katanishi, Shoji; et al.

JAERI-Tech 2003-034, 129 Pages, 2003/05

JAERI-Tech-2003-034.pdf:7.62MB

no abstracts in English

JAEA Reports

Fabrication of the full scale separable first wall of ITER shielding blanket

Kosaku, Yasuo; Kuroda, Toshimasa*; Hatano, Toshihisa; Enoeda, Mikio; Miki, Nobuharu*; Akiba, Masato

JAERI-Tech 2002-078, 58 Pages, 2002/10

JAERI-Tech-2002-078.pdf:19.38MB

Shielding blanket for ITER-FEAT applies the unique first wall structure which is separable from the shield block for the purpose of radio-active waste reduction in the maintenance work and cost reduction in fabrication process. Also, it is required to have various types of slots in both of the first wall and the shield block, to reduce the eddy current for reduction of electro-magnetic force in disruption events. This report summarizes the achievement of such R&Ds as, slit grooving techniques for Be/DSCu/SS first wall panel and SS shield block, demonstration of Be armor joining to the real scal first wall panel, and demonstration of full scale first wall panel.

JAEA Reports

Development of fabrication technology for ITER vacuum vessel

Nakahira, Masataka; Shibanuma, Kiyoshi; Kajiura, Soji*; Shibui, Masanao*; Koizumi, Koichi; Takeda, Nobukazu; Kakudate, Satoshi; Taguchi, Ko*; Oka, Kiyoshi; Obara, Kenjiro; et al.

JAERI-Tech 2002-029, 27 Pages, 2002/03

JAERI-Tech-2002-029.pdf:2.04MB

The ITER vacuum vessel (VV) R&D has progressed with the international collaborative efforts by the Japan, Russia and US Parties during the Engineering Design Activities (EDA). Fabrication and testing of a full-scale VV sector model and a port extension have yielded critical information on the fabrication and assembly technologies of the vacuum vessel, magnitude of welding distortions, dimensional accuracy and achievable tolerances during sector fabrication and field assembly. In particular, the dimensional tolerances of $$pm$$3 mm for VV sector fabrication and $$pm$$10 mm for VV sector field assembly have been achieved and satisfied the requirements of $$pm$$5 mm and $$pm$$20 mm, respectively. Also, the basic feasibility of the remote welding robot has been demonstrated. This report presents detailed fabrication and assembly technologies such as welding technology applicable to the thick wall without large distortion, field joint welding technology between sectors and remote welding technology through the VV R&D project.

Journal Articles

Fabrication and assembly of full-scale sector models for ITER vacuum vessel

Koizumi, Koichi; Nakahira, Masataka; Oka, Kiyoshi; *; Takahashi, Hiroyuki*; Tada, Eisuke; Ioki, Kimihiro*; Johnson, G.*; Onozuka, Masanori*; Y.Utin*; et al.

Fusion Technology, 34(3), p.586 - 590, 1998/11

no abstracts in English

Journal Articles

Fabrication of full-scale sector model for ITER vacuum vessel

Koizumi, Koichi; Nakahira, Masataka; *; Takahashi, Hiroyuki*; Tada, Eisuke; Ioki, Kimihiro*; Johnson, G.*; Onozuka, Masanori*; Y.Utin*; Sonnazzaro, G.*; et al.

Proceedings of 17th IEEE/NPSS Symposium Fusion Engineering (SOFE'97), 2, p.933 - 936, 1998/00

no abstracts in English

JAEA Reports

JAEA Reports

Full-Scale MarkII CRT Program Data Report No.12 (TEST 1205)

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JAERI-M 9405, 121 Pages, 1981/03

JAERI-M-9405.pdf:3.02MB

no abstracts in English

JAEA Reports

Full-scale MarkII CRT Program Data Report No.11 (TEST 1204)

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JAERI-M 9404, 121 Pages, 1981/03

JAERI-M-9404.pdf:2.99MB

no abstracts in English

JAEA Reports

Full-Scale Mark II CRT Program Data Report No.10 (TEST 1203)

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JAERI-M 9403, 122 Pages, 1981/03

JAERI-M-9403.pdf:2.78MB

no abstracts in English

JAEA Reports

Full-Scale Mark-II CRT Program Data Report,No.9; TEST1202

; ; ; ;

JAERI-M 8961, 121 Pages, 1980/07

JAERI-M-8961.pdf:2.67MB

no abstracts in English

JAEA Reports

Full-Scale Mark-II CRT Program Data Report,No.8; TEST 1201

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JAERI-M 8887, 132 Pages, 1980/06

JAERI-M-8887.pdf:3.8MB

no abstracts in English

JAEA Reports

Full-Scale MKII Containment Response Test Facility Description

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JAERI-M 8780, 134 Pages, 1980/03

JAERI-M-8780.pdf:4.05MB

no abstracts in English

JAEA Reports

Full-Scale Mark-II CRT Program Data Report No.7; Test 3102

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JAERI-M 8765, 123 Pages, 1980/03

JAERI-M-8765.pdf:2.69MB

no abstracts in English

JAEA Reports

Full-Scale Mark-II CRT Program Data Report No.5; Test 2101

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JAERI-M 8764, 118 Pages, 1980/03

JAERI-M-8764.pdf:2.66MB

no abstracts in English

JAEA Reports

Full-Scale Mark-II CRT Program Data Report No.4; Test 1101

; ; ;

JAERI-M 8763, 116 Pages, 1980/03

JAERI-M-8763.pdf:2.52MB

no abstracts in English

JAEA Reports

Full-Scale Mark-II CRT Program Data Report No.3; Test 0004

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JAERI-M 8762, 108 Pages, 1980/03

JAERI-M-8762.pdf:2.44MB

no abstracts in English

24 (Records 1-20 displayed on this page)