Refine your search:     
Report No.
 - 
Search Results: Records 1-6 displayed on this page of 6
  • 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

Activation, Radiation shielding materials

Sukegawa, Atsuhiko; Iida, Hiromasa*; Itoga, Toshio*; Okumura, Keisuke; Kai, Tetsuya; Konno, Chikara; Nakashima, Hiroshi; Nakamura, Takashi*; Ban, Shuichi*; Yashima, Hiroshi*; et al.

Hoshasen Shahei Handobukku; Kisohen, p.299 - 356, 2015/03

no abstracts in English

JAEA Reports

Investigation and design of the dismantling process of irradiation capsules containing tritium, 2; Detailed design and trial fabrication of capsule dismantling apparatus and investigation of glove box facility

Hayashi, Kimio; Nakagawa, Tetsuya; Onose, Shoji; Ishida, Takuya; Nakamichi, Masaru; Katsuyama, Kozo; Iwamatsu, Shigemi; Hasegawa, Teiji; Kodaka, Hideo; Takatsu, Hideyuki; et al.

JAEA-Technology 2009-007, 168 Pages, 2009/03

JAEA-Technology-2009-007.pdf:31.88MB

In-pile functional tests of breeding blankets have been planned by Japan Atomic Energy Agency (JAEA), using a test blanket module (TBM) which will be loaded in the International Thermonuclear Experimental Reactor (ITER). In preparation for the in-pile functional tests, JAEA has been being performed irradiation experiments of lithium titanate (Li$$_{2}$$TiO$$_{3}$$), which is the first candidate of solid breeder materials for the blanket of the demonstration reactor (DEMO) under designing in Japan. The present report describes (1) results of a detailed design and trial fabrication tests of a dismantling apparatus for irradiation capsules which were used in irradiation experiments by the Japan Materials Testing Reactor (JMTR) of JAEA, and (2) results of a preliminary investigation of a glove box facility for post-irradiation examinations (PIEs). In the detailed design of the dismantling apparatus, datailed specifications and the installation methods were examined, based on results of a conceptual design and basic design. In the trial fabrication, cutting tests were curried out by making a mockup of a cutting component. Furthermore, a preliminary investigation of a glove box facility was carried out in order to secure a facility for PIE work after the capsule dismantling, which revealed a technical feasibility.

Journal Articles

R&D of seismic emergency information transmission system

Ebisawa, Katsumi; Kuno, Tetsuya; Shibata, Katsuyuki; Oi, Masahiro*; Horiuchi, Shigeki*; Abe, Ichiro*; Tsuzuki, Kazuhisa*

Nihon Genshiryoku Gakkai Wabun Rombunshi, 1(2), p.177 - 190, 2002/06

no abstracts in English

Journal Articles

Development of seismic emergency information system adaptable to disaster management spatial information system

Ebisawa, Katsumi; Kuno, Tetsuya; Shibata, Katsuyuki; Abe, Ichiro*; Kakumoto, Shigeru*; Kameda, Hiroyuki*

Chiiki Anzen Gakkai Kogaishu, 10, p.133 - 136, 2000/11

no abstracts in English

Journal Articles

Development of methodology for evaluating ground motion parameters and information system under seismic emergency

Shibata, Katsuyuki; Ebisawa, Katsumi; Abe, Ichiro*; Kuno, Tetsuya; Hori, S.*; Oi, Masahiro*

Proceedings of 12th World Conference in Earthquake Engineering (CD-ROM), 8 Pages, 2000/01

no abstracts in English

Journal Articles

R&D on seismic emergency information system

Ebisawa, Katsumi; Kuno, Tetsuya; Shibata, Katsuyuki; Oi, Masahiro*; Horiuchi, Shigeki*; Abe, Ichiro*; Tsuzuki, Kazuhisa*

Riarutaimu Jishin Joho Dentatsu Shisutemu; Kongo No Snkangaku Renkei No Tameni, P. 18, 2000/00

no abstracts in English

6 (Records 1-6 displayed on this page)
  • 1