Impact hammer test of ITER blanket remote handling system

Noguchi, Yuto; Maruyama, Takahito; Ueno, Kenichi; Komai, Masafumi; Takeda, Nobukazu; Kakudate, Satoshi

Fusion Engineering and Design, 109-111(Part B), p.1291 - 1295, 2016/11

https://doi.org/10.1016/j.fusengdes.2015.12.040

This paper reports the impact hammer test of the full-scale mock-up of ITER Blanket Remote Handling system (BRHS). Since the BRHS, which is composed of the articulated rail and the vehicle manipulator which travels on the rail deployed in the vacuum vessel, is subjected to the floor response spectrum with 14 G peak at 8 Hz, evaluation of dynamic response of the system is of essential importance. Recently impact hammer testing on the full-scale mock-up of the BRHS was carried out to verify the finite element method seismic analysis and to experimentally obtain the damping ratio of the system. The results showed that the mock-up has a vertical major natural mode with a natural frequency of 7.5 Hz and a damping ratio of 0.5%. While higher structural damping ratios is predicted in a high amplitude excitation such as major earthquake, it was confirmed that the experimental natural major frequencies are in agreement with the major frequencies obtained by elastic dynamic analysis.

Seismic analysis of the ITER blanket remote handling system

Noguchi, Yuto; Maruyama, Takahito; Takeda, Nobukazu; Kakudate, Satoshi

Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 9 Pages, 2015/05

This paper reports the seismic analysis of the ITER Blanket RH system (BRHS) during blanket module handling operation. Since the BRHS, which is composed of the articulated rail and the vehicle manipulator, which travels on the rail deployed in the vacuum vessel in the toroidal direction, has various configurations and the rail system has flexibility, evaluation of dynamic response of the system is of essential importance. Via parameter sensitivity study on position and posture of the vehicle manipulator, the most unfavorable configuration for each component of the BRHS has been specified by the modal and spectrum analyses with the global BRHS FE model. Then using the quasi-static equivalent loads on the individual components obtained by the global BRHS seismic analysis, the structural verifications of the structural members of the BRHS have been carried out with detailed partial FE models. The system seismic resistance of the BRHS to a safe shutdown earthquake was confirmed.

Study on system integration of robots Operated in nuclear fusion facility and nuclear power plant facilities

Oka, Kiyoshi

JAERI-Research 2004-009, 225 Pages, 2004/07

JAERI-Research-2004-009.pdf:47.47MB

In the present paper, I describe the necessary approaches and elemental technologies to solve the issues on the system integration of the typical robot systems for maintenance in the nuclear fusion facility and rescue in the accident of the nuclear power plant facilities. These robots work under the intense radiation condition and restricted space in place of human. In particular, I propose a new approach to realize the system integration of the robot for actual use from the viewpoints of not only the environmental and working conditions but also the restructure and optimization of the required elemental technologies with a well balance in the robot system. Based on the above approach, I have a contribution to realize the robot systems working under the actual conditions for maintenance in the nuclear fusion facility and rescue in the accident of the nuclear power plant facilities.

Conceptual design of cesium removal device for ITER NBI maintenance

Oka, Kiyoshi; Shibanuma, Kiyoshi

JAERI-Tech 2003-004, 57 Pages, 2003/03

JAERI-Tech-2003-004.pdf:2.36MB

Cesium is required in order to generate a stable negative ion of hydrogen in an ion source of the neutral beam injector (NBI), which is one of the plasma-heating devices for International Thermonuclear Experimental Reactor (ITER). After long time operation of NBI, the cesium deposits to the insulators supporting the electrode. Due to the deterioration of the insulation resistance, the continuous operation of the NBI will be difficult. In addition, the NBI device is activated by neutron from D-T plasma, so that a periodic removal and cleaning of the cesium on the insulators by remote handling is required. A study of the cesium removal scenario and device is therefore required considering remote handling. In this report, a cesium removal procedure and conceptual design of the cesium removal device using laser ablation technique are studied, and the feasibility of laser ablation is shown.

Development of new dosimeter using colored alumilite fading

Obara, Kenjiro

Genshiryoku eye, 48(2), p.46 - 48, 2002/02

http://ci.nii.ac.jp/naid/40005192298

no abstracts in English

Development of a control system for a heavy object handling manipulator; Application to a remote maintenance system for ITER blanket module

Yoshimi, Takashi*; Kakudate, Satoshi; Tada, Eisuke; Tsuji, Koichi*; Miyagawa, Shinichi*; Kubo, Tomomi*

Nihon Robotto Gakkai-Shi, 19(6), p.766 - 774, 2001/09

https://doi.org/10.7210/jrsj.19.766

no abstracts in English

Development of super elastic alloy seal gasket

Taguchi, Ko*; Tada, Eisuke

JAERI-Tech 99-079, p.28 - 0, 1999/11

JAERI-Tech-99-079.pdf:3.07MB

no abstracts in English

None

; *; *; ;

JNC TN8440 2000-001, 126 Pages, 1999/03

JNC-TN8440-2000-001.pdf:4.37MB

None

High -rays irradiation tests of critical components for ITER (International Thermonulear Experimental Reactor) in-vessel remote handling system

Obara, Kenjiro; Kakudate, Satoshi; Oka, Kiyoshi; *; *; Koizumi, Koichi; Shibanuma, Kiyoshi; Yagi, Toshiaki; Morita, Yosuke; ; et al.

JAERI-Tech 99-003, 312 Pages, 1999/02

[This article is unavailable to download the full text due to various reasons.]

None

; Ojima, Hisao

PNC TN8410 97-220, 33 Pages, 1997/12

PNC-TN8410-97-220.pdf:1.63MB

None