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Journal Articles

Tensile and fatigue strength of free-standing CVD diamond

Davies, A. R.*; Field, J. E.*; Takahashi, Koji; Hada, Kazuhiko

Diamond and Related Materials, 14(1), p.6 - 10, 2005/01

 Times Cited Count:17 Percentile:38.07(Materials Science, Multidisciplinary)

A CVD diamond is finding increased application and it is important to study its fatigue properties. The present paper describes research on a batch of di-electric grade CVD material. It was obtained that tensile strength at the nucleation side and the growth were side 690$$pm$$90MPa and 280$$pm$$30MPa, respectively. Some samples survived at least 95% of their critical fracture stress for 10$$^{7}$$ cycles without fatiguing.

Journal Articles

The Toughness of free-standing CVD diamond

Davies, A. R.*; Field, J. E.*; Takahashi, Koji; Hada, Kazuhiko

Journal of Materials Science, 39(5), p.1571 - 1574, 2004/03

 Times Cited Count:6 Percentile:68.42(Materials Science, Multidisciplinary)

A four-point bend test was used to determine the fracture toughness of mechanical grade and di-electric (optical) grade chemical vapour deposited (CVD) diamond. The validity of the test was first confirmed by measuring the toughness of alumina and confirming the results with literature values. The toughnesses of both types of CVD were similar; 8.5$$pm$$1.0 and 8.3$$pm$$0.4 MPa($sqrt{m}$) respectively. This is higher than the value of 3.4$$pm$$0.5 MPa($sqrt{m}$) measured for diamond by Field and Freeman, 1981 using an indentation technique. It is suggested that this is primarily due to differences in surface roughness. There were enough samples to make a preliminary study of the effect of temperature and these data are reported.

Journal Articles

Approach for safety assurance and structural integrity of ITER

Tada, Eisuke; Hada, Kazuhiko; Maruo, Takeshi; Safety Design/Evaluation Group

Purazuma, Kaku Yugo Gakkai-Shi, 78(11), p.1145 - 1156, 2002/11

no abstracts in English

Journal Articles

Ready to construct ITER

Hada, Kazuhiko

Nippon Kikai Gakkai Doryoku Enerugi Shisutemu Bumon Nyusu Reta, (25), p.2 - 3, 2002/10

no abstracts in English

Journal Articles

Safety design concepts for ITER-tritium facility; Toward construction in Japan

Ohira, Shigeru; Tada, Eisuke; Hada, Kazuhiko; Neyatani, Yuzuru; Maruo, Takeshi; Hashimoto, Masayoshi*; Araki, Takao*; Nomoto, Kazuhiro*; Tsuru, Daigo; Ishida, Toshikatsu*; et al.

Fusion Science and Technology, 41(3), p.642 - 646, 2002/05

no abstracts in English

Journal Articles

Main features of ITER vacuum vessel and approach to code application

Nakahira, Masataka; Takeda, Nobukazu; Hada, Kazuhiko; Tada, Eisuke; Miya, Kenzo*; Asada, Yasuhide*

Proceedings of 10th International Conference on Nuclear Engineering (ICONE 10) (CD-ROM), 7 Pages, 2002/04

The special features of Vacuum Vessel (VV) of International Thermonuclear Experimental Reactor (ITER) are complicated structure and electromagnetic load. The VV is torus shaped, double-walled structure with ribs. The electromagnetic force is not uniform. Thus the rules for axisymmetric structures and loading are not effective for ITER VV. The double ミwalled structure requires one-sided welding joints with no possibility of access from the other side. Every joints between outer wall and rib and field joints are this type. The joint between outer wall and rib is special T-joint with partial penetration. To cover these special issues on ITER VV, a new code is under development. Supporting R&Ds are planned to be material tests to obtain joint efficiency and fatigue reduction factor, UT sensitivity tests, sensitivity tests on crevice corrosion and examination-free welding for application to field joints. This paper describes the special features of ITER VV from code stand point, concept of new code and R&Ds to apply the new code to ITER VV.

Journal Articles

New cryogenic steels and design approach for ITER superconducting magnet system

Nakajima, Hideo; Hamada, Kazuya; Okuno, Kiyoshi; Hada, Kazuhiko; Tada, Eisuke

Proceedings of 10th International Conference on Nuclear Engineering (ICONE 10) (CD-ROM), 8 Pages, 2002/00

The Japan Atomic Energy Research Institute (JAERI) has conducted to develop a new design code for construction and operation/maintenance of the International Thermonuclear Experimental Reactor (ITER), which will be formed as a code case of ASME B&PV Code Section III, division 4, in collaboration with the ASME international. The new design code will also include the several new techniques and materials developed for each components of ITER. This paper describes the new cryogenic steels used in the magnet system and the design approach with taking account of unique features of the ITER superconducting magnets.

Journal Articles

Study on decay heat removal of compact ITER

Tsuru, Daigo; Neyatani, Yuzuru; Araki, Takao*; Nomoto, Kazuhiro*; Ohira, Shigeru; Maruo, Takeshi; Hashimoto, Masayoshi*; Hada, Kazuhiko; Tada, Eisuke

Fusion Engineering and Design, 58-59, p.985 - 989, 2001/11

 Times Cited Count:3 Percentile:69.85

no abstracts in English

Journal Articles

Safety activities in JAERI related to ITER

Ohira, Shigeru; Tada, Eisuke; Hada, Kazuhiko; Neyatani, Yuzuru; Maruo, Takeshi; Hashimoto, Masayoshi*; Araki, Takao*; Nomoto, Kazuhiro*; Tsuru, Daigo; Ishida, Toshikatsu*; et al.

Fusion Engineering and Design, 54(3-4), p.515 - 522, 2001/04

 Times Cited Count:3 Percentile:69.85

no abstracts in English

JAEA Reports

Study on commercial HTGR hydrogen production system

Nishihara, Tetsuo; Hada, Kazuhiko; Nishimura, Kuniyuki*

JAERI-Tech 2000-046, 54 Pages, 2000/07

JAERI-Tech-2000-046.pdf:2.72MB

no abstracts in English

Journal Articles

Thermal stress ratcheting analysis of time-hardening structure

Hada, Kazuhiko

Nippon Kikai Gakkai Rombunshu, A, 65(636), p.108 - 115, 1999/08

no abstracts in English

Journal Articles

Evaluation tritium transportation to the product hydrogen in the HTGR hydrogen production system

Nishihara, Tetsuo; Hada, Kazuhiko

Nippon Genshiryoku Gakkai-Shi, 41(5), p.571 - 578, 1999/05

 Times Cited Count:4 Percentile:61.54(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Out-of-pile demonstration test program of hydrogen production system coupling with HTTR

Inagaki, Yoshiyuki; Takeda, Tetsuaki; Nishihara, Tetsuo; Hada, Kazuhiko; Hayashi, Koji

Nippon Genshiryoku Gakkai-Shi, 41(3), p.250 - 257, 1999/00

 Times Cited Count:10 Percentile:35.5(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Research and development of hydrogen production systems with HTGR in Japan

Miyamoto, Yoshiaki; Shiozawa, Shusaku; Ogawa, Masuro; Akino, Norio; Hada, Kazuhiko; Inagaki, Yoshiyuki; Shimizu, Saburo; Onuki, Kaoru

Proc. of 9th Canadian Hydrogen Conf., p.205 - 213, 1999/00

no abstracts in English

Journal Articles

Development program on hydrogen production at JAERI

Miyamoto, Yoshiaki; Shiozawa, Shusaku; Ogawa, Masuro; Hada, Kazuhiko

Proc. of the Int. Conf. on Future Nuclear Systems (GLOBAL'99)(CD-ROM), 7 Pages, 1999/00

no abstracts in English

Journal Articles

Out-of-pile demonstration test of hydrogen production system coupling with HTTR

Inagaki, Yoshiyuki; Nishihara, Tetsuo; Takeda, Tetsuaki; Hada, Kazuhiko; Hayashi, Koji

Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7) (CD-ROM), 10 Pages, 1999/00

no abstracts in English

Journal Articles

Overview of HTGR heat utilization system development at JAERI

Miyamoto, Yoshiaki; Shiozawa, Shusaku; Ogawa, Masuro; Akino, Norio; Shimizu, Saburo; Hada, Kazuhiko; Inagaki, Yoshiyuki; Onuki, Kaoru; Takeda, Tetsuaki; Nishihara, Tetsuo

IAEA-TECDOC-1056, p.191 - 200, 1998/11

no abstracts in English

Journal Articles

Developments of nuclear heat utilization systems for high-temperature gas-cooled reactor in JAERI

Miyamoto, Yoshiaki; Shiozawa, Shusaku; Akino, Norio; Ogawa, Masuro; Hada, Kazuhiko; Shiina, Yasuaki; Shimizu, Saburo; Inagaki, Yoshiyuki; Onuki, Kaoru; Fumizawa, Motoo; et al.

Proc. of 9th Annual U. S.Hydrogen Meeting, p.367 - 369, 1998/00

no abstracts in English

JAEA Reports

Outline of operation and control system and analytical investigation of transient behavior of an out-of-pile hydrogen production system for HTTR heat utilization system

Inagaki, Yoshiyuki; Hada, Kazuhiko; Nishihara, Tetsuo; Takeda, Tetsuaki; Hino, Ryutaro;

JAERI-Tech 97-050, 125 Pages, 1997/10

JAERI-Tech-97-050.pdf:2.96MB

no abstracts in English

JAEA Reports

Proposal of safety design methodologies for an HTGR-hydrogen production system; Mainly on countermeasures against fire and explosion

Nishihara, Tetsuo; Hada, Kazuhiko; Shiozawa, Shusaku

JAERI-Research 97-022, 110 Pages, 1997/03

JAERI-Research-97-022.pdf:4.1MB

no abstracts in English

44 (Records 1-20 displayed on this page)