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Journal Articles

Development of laser beam injection system for the Edge Thomson Scattering (ETS) in ITER

Yatsuka, Eiichi; Hatae, Takaki; Suito, Satoshi*; Ohara, Miyuki*; Hagita, Koji*; Inoue, Kazunori*; Bassan, M.*; Walsh, M.*; Itami, Kiyoshi

Journal of Instrumentation (Internet), 11(1), p.C01006_1 - C01006_12, 2016/01

 Times Cited Count:6 Percentile:31.03(Instruments & Instrumentation)

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.

JAEA Reports

Study of manufacture and test of the alcohol waste processing test equipment

*; *; *; *; *

JNC TJ9410 2001-003, 432 Pages, 2001/08

JNC-TJ9410-2001-003.pdf:80.1MB

This report describes the result of study of manufacture and test of the Alcohol Waste Processing test Equipment. The experimental fast Reactor, JOYO, stores the radioactive alcohol waste at storage tank. As this alcohol waste can not be processed with existing equipment, about 5 m$$^{3}$$ of alcohol waste is stored. And the amount of this waste increases every year. So it is necessary to process this alcohol waste by appropriate method, for example, chemical resolution. In this fiscal year, based on the study results in the last fiscal year on catalytic oxidation method, the test equipment is manufactured and conclusive test is performed. And the investigation and tests on applicability of the other sodium removal technologies is also performed. The study results obtained in this fiscal year are as follows. [(1)Conclusive Test of the alcohol waste processing] (a)As a result of 1/2 scale test, target processing performance of 1.25$$ell$$/h can be obtained for simulative alcohol waste of 80% alcohol, but processing performance for simulative alcohol waste of 20% could not satisfy the target value. (b)In case that high temperature pipes, which are under condition of 350 deg C in actual plant, are arranged, it is difficult to arrange equipment in alcohol waste tank room (A-106). [(2)Investigative and Test about Sodium removal] (a)The sodium in alcohol waste can be separated and removed from carbonate compound. (b)A sodium (carbonate compound and metals) in alcohol waste could be removed by wired-film evaporator, and it is considered to be possible that this equipment is applied to actual plant. (c)ICP (Inductively Coupled Plasma) is considered to be effective method as one of alcohol resolution processes. [(3)Basic Design of alcohol waste process equipment] In this basic design, as far evaporation-dry process, the components, process ability, properties of waste, chemical mass balance, safety for fire and explosion, and the plot plan are investigated. As a result, ...

Journal Articles

Mechanical characteristics and position control of vehicle/manipulator for ITER blanket remote maintenance

Kakudate, Satoshi; Oka, Kiyoshi; Yoshimi, Takashi*; Taguchi, Ko*; Nakahira, Masataka; Takeda, Nobukazu; Shibanuma, Kiyoshi; Obara, Kenjiro; Tada, Eisuke; Matsumoto, Yasuhiro*; et al.

Fusion Engineering and Design, 51-52(1-4), p.993 - 999, 2000/11

 Times Cited Count:9 Percentile:54.14(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

High $$gamma$$-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.]

Journal Articles

Development of 15-m-long radiation hard periscope for ITER in-vessel viewing

Obara, Kenjiro; *; Kakudate, Satoshi; Oka, Kiyoshi; Nakahira, Masataka; Morita, Yosuke; *; *; Takeda, Nobukazu; Takahashi, Hiroyuki*; et al.

Fusion Engineering and Design, 42, p.501 - 509, 1998/00

 Times Cited Count:3 Percentile:31.85(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Development of radiation hardness components for ITER remote maintenance

Obara, Kenjiro; Kakudate, Satoshi; Oka, Kiyoshi; *; Yagi, Toshiaki; Morita, Yosuke

J. Robot. Mechatron., 10(2), p.121 - 132, 1998/00

no abstracts in English

Journal Articles

Development of bore tools for blanket cooling pipe connection in ITER

*; Oka, Kiyoshi; Kakudate, Satoshi; Obara, Kenjiro; *; Tada, Eisuke; A.Tesini*; Shibanuma, Kiyoshi; R.Haange*

Proceedings of 17th IEEE/NPSS Symposium Fusion Engineering (SOFE'97), 2, p.921 - 924, 1998/00

no abstracts in English

Journal Articles

Development of radiation hard components for remote maintenance

Oka, Kiyoshi; Obara, Kenjiro; Kakudate, Satoshi; *; *; Morita, Yosuke

Purazuma, Kaku Yugo Gakkai-Shi, 73(1), p.69 - 82, 1997/01

no abstracts in English

Journal Articles

Development of radiation hard CCD camera and camera control unit

Obara, Kenjiro; Kakudate, Satoshi; Oka, Kiyoshi; Nakahira, Masataka; *; Morita, Yosuke; *; *; *; *; et al.

Proc. of 1997 RADECS Conf. Data Workshop (RADECS 97), 0, p.69 - 74, 1997/00

no abstracts in English

JAEA Reports

Development of radiation-hard ultrasonic inspection probes for ITER vacuum vessel

Koizumi, Koichi; Nakahira, Masataka; Oka, Kiyoshi; Obara, Kenjiro; *; Morita, Yosuke; Tada, Eisuke

JAERI-Tech 96-041, 66 Pages, 1996/10

JAERI-Tech-96-041.pdf:2.6MB

no abstracts in English

JAEA Reports

Development of remote bore tools for pipe welding/cutting by YAG laser

Oka, Kiyoshi; Nakahira, Masataka; Kakudate, Satoshi; Tada, Eisuke; Obara, Kenjiro; *; *

JAERI-Tech 96-035, 47 Pages, 1996/07

JAERI-Tech-96-035.pdf:3.17MB

no abstracts in English

JAEA Reports

Irradiation tests of critical components for remote handling system in gamma radiation environment

Obara, Kenjiro; Kakudate, Satoshi; Oka, Kiyoshi; Furuya, Kazuyuki; *; Tada, Eisuke; Shibanuma, Kiyoshi; Koizumi, Koichi; Okawa, Yoshinao; Morita, Yosuke; et al.

JAERI-Tech 96-011, 111 Pages, 1996/03

JAERI-Tech-96-011.pdf:5.9MB

no abstracts in English

JAEA Reports

Conceptual design studies of in-vessel viewing equipment for ITER

Obara, Kenjiro; Oka, Kiyoshi; *; *; Tada, Eisuke; Shibanuma, Kiyoshi

JAERI-Tech 96-010, 29 Pages, 1996/03

JAERI-Tech-96-010.pdf:1.15MB

no abstracts in English

Journal Articles

Mockup test of rail-mounted vehicle type maintenance system for fusion experimental reactor

Kakudate, Satoshi; Tada, Eisuke; Oka, Kiyoshi; *; *; ; Obara, Kenjiro; *; Shibanuma, Kiyoshi; Seki, Masahiro

Fusion Technology 1994, Vol.2, 0, p.1411 - 1414, 1995/00

no abstracts in English

JAEA Reports

Critical element development of standard components for pipe welding/cutting by CO$$_{2}$$ laser

Oka, Kiyoshi; Kakudate, Satoshi; Nakahira, Masataka; Tada, Eisuke; Obara, Kenjiro; *; *; *; Shibanuma, Kiyoshi; Seki, Masahiro

JAERI-Tech 94-033, 20 Pages, 1994/11

JAERI-Tech-94-033.pdf:1.25MB

no abstracts in English

JAEA Reports

Critical element study on autonomous position control of articulated-arm type manipulator

Oka, Kiyoshi; Kakudate, Satoshi; Nakahira, Masataka; Tada, Eisuke; Obara, Kenjiro; *; *; *; Shibanuma, Kiyoshi; Seki, Masahiro

JAERI-Tech 94-022, 20 Pages, 1994/10

JAERI-Tech-94-022.pdf:0.87MB

no abstracts in English

JAEA Reports

Critical element development of double seal door for tritium containment

*; Kakudate, Satoshi; Oka, Kiyoshi; Nakahira, Masataka; *; Obara, Kenjiro; Tada, Eisuke; Shibanuma, Kiyoshi; Seki, Masahiro

JAERI-Tech 94-012, 17 Pages, 1994/08

JAERI-Tech-94-012.pdf:1.14MB

no abstracts in English

JAEA Reports

Irradiation tests of critical components for remote handling in gamma radiation environment

Obara, Kenjiro; Kakudate, Satoshi; Oka, Kiyoshi; Furuya, Kazuyuki; *; Tada, Eisuke; Shibanuma, Kiyoshi; Okawa, Yoshinao; Morita, Yosuke; Yokoo, Noriko*; et al.

JAERI-Tech 94-003, 73 Pages, 1994/08

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

JAEA Reports

Critical element development of standard pipe connector for remote handling

*; Kakudate, Satoshi; *; Oka, Kiyoshi; Nakahira, Masataka; Obara, Kenjiro; Tada, Eisuke; Shibanuma, Kiyoshi; Seki, Masahiro

JAERI-Tech 94-002, 19 Pages, 1994/08

JAERI-Tech-94-002.pdf:1.17MB

no abstracts in English

21 (Records 1-20 displayed on this page)