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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.

Journal Articles

Development of fabrication technology of ITER shielding blanket

Enoeda, Mikio

Koon Gakkai-Shi, 30(5), p.256 - 262, 2004/09

Fabrication technologies for ITER in-vessel components, especially the shielding blanket with the separable first wall panel has been developed. Hot Isostatic Pressing (HIP) has been applied to the bonding of Cu-alloy/stainless steel and beryllium/Cu-alloy. First wall mock-ups fabricated by using HIP were tested under high heat fluxes and showed sufficient heat removal and thermal fatigue performance. Water jet and electrical discharge machining have been applied to manufacture slots into the first wall panel and the shield block. With these technologies, a first wall panel prototype and a shielding block 1/2 mock-up were successfully fabricated.

Journal Articles

Neutronic and thermal estimation of blanket in-pile mockup with Li$$_{2}$$TiO$$_{3}$$ pebbles

Nagao, Yoshiharu; Nakamichi, Masaru; Tsuchiya, Kunihiko; Kawamura, Hiroshi

Fusion Engineering and Design, 58-59, p.673 - 678, 2001/11

 Times Cited Count:0 Percentile:0.00(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Quick installation/removal technology for first wall tile

; ; Seki, Yasushi; Fujisawa, Noboru; ;

JAERI-M 89-084, 69 Pages, 1989/07

JAERI-M-89-084.pdf:1.35MB

no abstracts in English

JAEA Reports

Core Hydrodynamic Tests and Determination of Core Flow of JRR-3 to Be Renewed ata 20MWt

Sudo, Yukio; ; ;

JAERI-M 84-119, 108 Pages, 1984/06

JAERI-M-84-119.pdf:2.16MB

no abstracts in English

JAEA Reports

Critical Assembly Experiment on FCA Assembly VI-2

Iijima, Tsutomu; ; ; ; ; ; ; ; ; M.Cho*

JAERI-M 7888, 50 Pages, 1978/10

JAERI-M-7888.pdf:1.1MB

no abstracts in English

JAEA Reports

Critical Experiment on FCA Assembly V-2

Iijima, Tsutomu; ; ; ; ; ; ; ; ; ; et al.

JAERI-M 7887, 48 Pages, 1978/10

JAERI-M-7887.pdf:1.44MB

no abstracts in English

JAEA Reports

Critical Experiment on FCA Assembly V-1

; ; ; ; ; ;

JAERI-M 7882, 47 Pages, 1978/10

JAERI-M-7882.pdf:1.46MB

no abstracts in English

JAEA Reports

Experimental Results on the 「Linear Heat Rating Capsule」(72F-12J)

Mizuho, Mitsuru; ; ; ;

JAERI-M 7705, 77 Pages, 1978/06

JAERI-M-7705.pdf:1.85MB

no abstracts in English

Journal Articles

Mockup experiments for the irregular shield of the first nuclear ship of Japan

; ; H.YAMAKI*; Y.TOYODA*; Y.NAKANO*; T.FUSE*; T.MIURA*

Nucl.Eng.Des., 7(2), p.152 - 158, 1968/00

 Times Cited Count:1

no abstracts in English

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