Refine your search:     
Report No.
 - 
Search Results: Records 1-14 displayed on this page of 14
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

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.

Journal Articles

Nuclear heat supply fluctuation test by non-nuclear heating using HTTR

Takada, Shoji; Sekita, Kenji; Nemoto, Takahiro; Honda, Yuki; Tochio, Daisuke; Inaba, Yoshitomo; Sato, Hiroyuki; Nakagawa, Shigeaki; Sawa, Kazuhiro

Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 7 Pages, 2015/05

To investigate the safety design criteria of heat utilization system for the HTGRs, it is necessary to evaluate the effect of fluctuation of thermal load on the reactor. The nuclear heat supply fluctuation test by non-nuclear heating was carried out to simulate the nuclear heat supply test which is carried out in the nuclear powered operation. The test data is used to verify the numerical code to calculate the temperature of core bottom structure to carry out the safety evaluation of abnormal events in the heat utilization system. In the test, the helium gas temperature was heated up to 120$$^{circ}$$C. A sufficiently high temperature disturbance was imposed on the reactor inlet temperature. It was found that the response of temperatures of metallic components such as side shielding blocks was faster than those of graphite blocks in the core bottom structure, which was significantly affected by the heat capacities of components, the level of imposed disturbance and heat transfer performance.

Journal Articles

Application of infrared thermography to nondestructive evaluation of nuclear structures and components

Ishii, Toshimitsu; Ooka, Norikazu; Naka, Michihiro; Kanaya, Kunio; Saito, Junichi; Okamoto, Yoshizo*

Proceedings of 6th Far-East Conference on Nondestructive Testing (FENDT '02), p.273 - 278, 2002/00

no abstracts in English

Journal Articles

Acceptance test of graphite components in nuclear reactor

Ishihara, Masahiro; Hanawa, Satoshi; Iyoku, Tatsuo; Shiozawa, Shusaku

Tanso, 2001(196), p.39 - 48, 2001/02

no abstracts in English

Journal Articles

Development of B$$_{4}$$C-carbon fiber composite ceramics as plasma facing materials in nuclear fusion reactor, 3; Heat resistance evaluation by electron beam irradiation and by in situ plasma discharge in JT-60

Jimbo, Ryutaro*; Saido, Masahiro; Nakamura, Kazuyuki; Akiba, Masato; ; Dairaku, Masayuki; *; *; *; *

Journal of the Ceramic Society of Japan, International Edition, 105, p.1179 - 1187, 1997/00

no abstracts in English

Journal Articles

Recent R&D activities on plasma facing components at JAERI

Sato, Kazuyoshi; ; Araki, Masanori; Nakamura, Kazuyuki; Watanabe, Kazuhiro; ; Dairaku, Masayuki; Okumura, Yoshikazu; Ohara, Yoshihiro; Akiba, Masato

16th IEEE/NPSS Symp. on Fusion Engineering (SOFE '95), 1, p.220 - 223, 1995/00

no abstracts in English

Journal Articles

Study on structural integrity of graphite components for surface flaw; Applicability of the eddy current testing as acceptance test for graphite components

Ishihara, Masahiro; Iyoku, Tatsuo; *

JCOSSAR95 Rombunshu, 0, p.199 - 206, 1995/00

no abstracts in English

Journal Articles

Evaluation of aseismic integrity in the HTTR core-bottom structure,IV; Structural integrity of connecting elements between graphite components

Ishihara, Masahiro; Iyoku, Tatsuo; Futakawa, Masatoshi

Nucl. Eng. Des., 154, p.83 - 95, 1995/00

 Times Cited Count:6 Percentile:54.86(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

An Inspection standard of graphite for the High Temperature Engineering Test Reactor

Toyota, Junji; Iyoku, Tatsuo; Ishihara, Masahiro; Takikawa, Noboru; Shiozawa, Shusaku

JAERI-M 91-102, 61 Pages, 1991/07

JAERI-M-91-102.pdf:1.49MB

no abstracts in English

Journal Articles

Thermal shock tests on various materials of plasma facing components for FER/ITER

Seki, Masahiro; Akiba, Masato; Araki, Masanori; ; Dairaku, Masayuki; *; Fukaya, Kiyoshi; Ogawa, Masuro; Ise, Hideo*

Fusion Engineering and Design, 15, p.59 - 74, 1991/00

 Times Cited Count:17 Percentile:84.03(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Construction of in-core structure test section in HENDEL, (II); Testing devices and their performance test

; ; ; ; ; ; *;

Nihon Genshiryoku Gakkai-Shi, 30(5), p.427 - 433, 1988/05

 Times Cited Count:1 Percentile:19.68(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Construction of in-core structure test section in HENDEL, (I); Outline of test section and simulated core bottom structure

; ; ; ; Nekoya, Shinichi; ; *;

Nihon Genshiryoku Gakkai-Shi, 30(4), p.333 - 342, 1988/04

 Times Cited Count:1 Percentile:29.57(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Evaluation test of stability for high temperature strain gages

; ; ; *

Kyowa Giho, 309, p.2195 - 2197, 1983/00

no abstracts in English

14 (Records 1-14 displayed on this page)
  • 1