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Journal Articles

An Evaluation method for plastic buckling of cantilever type pipes controlled by displacement loads, 1; Proposal of the estimation method and the criterion

Ando, Masanori; Tezuka, Taiji*; Nakamura, Toshio*; Okawa, Tomohiro*; Enuma, Yasuhiro*; Kawasaki, Nobuchika; Tsukimori, Kazuyuki

Proceedings of 2011 ASME Pressure Vessels and Piping Conference (PVP 2011) (CD-ROM), 9 Pages, 2011/07

Journal Articles

An Evaluation method for plastic buckling of cantilever type pipes controlled by displacement loads, 2; Verification of proposal method by buckling test

Ando, Masanori; Tezuka, Taiji*; Nakamura, Toshio*; Okawa, Tomohiro*; Enuma, Yasuhiro*; Kawasaki, Nobuchika; Tsukimori, Kazuyuki

Proceedings of 2011 ASME Pressure Vessels and Piping Conference (PVP 2011) (CD-ROM), 8 Pages, 2011/07

Journal Articles

Effect of heat treatments on tensile properties of F82H steel irradiated by neutrons

Wakai, Eiichi; Ando, Masami; Sawai, Tomotsugu; Tanigawa, Hiroyasu; Taguchi, Tomitsugu; Stroller, R. E.*; Yamamoto, Toshio; Kato, Yoshiaki; Takada, Fumiki

Journal of Nuclear Materials, 367-370(1), p.74 - 80, 2007/08

 Times Cited Count:9 Percentile:58.28(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Feasibility Study on Commercialization of Fast Breeder Reactor Cycle Systems Interim Report of Phase II; Technical Study Report for Reactor Plant Systems

Konomura, Mamoru; Ogawa, Takashi; Okano, Yasushi; Yamaguchi, Hiroyuki; Murakami, Tsutomu; Takaki, Naoyuki; Nishiguchi, Youhei; Sugino, Kazuteru; Naganuma, Masayuki; Hishida, Masahiko; et al.

JNC TN9400 2004-035, 2071 Pages, 2004/06

JNC-TN9400-2004-035.pdf:76.42MB

The attractive concepts for Sodium-, lead-bismuth-, helium- and water-cooled FBRs have been created through using typical plant features and employing advanced technologies. Efforts on evaluating technological prospects of feasibility have been paid for these concepts. Also, it was comfirmed if these concepts satisfy design requierments of capability and performance presumed in the feasibilty study on commertialization of Fast Breeder Reactor Systems. As results, it was concluded that the selection of sodium-cooled reactor was most rational for practical use of FBR technologies in 2015.

JAEA Reports

Test results of the reactor inlet coolant temperature control system of HTTR

Saito, Kenji; Nakagawa, Shigeaki; Hirato, Yoji; Kondo, Makoto; Sawahata, Hiroaki; Tsuchiyama, Masaru*; Ando, Toshio*; Motegi, Toshihiro; Mizushima, Toshihiko; Nakazawa, Toshio

JAERI-Tech 2004-042, 26 Pages, 2004/04

JAERI-Tech-2004-042.pdf:1.16MB

The reactor control system of HTTR is composed of the reactor power control system, the reactor inlet coolant temperature control system, the primary coolant flow rate control system and so on. The reactor control system of HTTR achieves reactor power 30MW, reactor outlet coolant temperature 850$$^{circ}$$C, reactor inlet coolant temperature 395$$^{circ}$$C under the condition that primary coolant flow rate is fixed. In the Rise-to-Power Test, the performance test of the reactor inlet coolant temperature control system was carried out in order to confirm the control capability of this control system. This report shows the test results of performance test. As a result, the control parameters, which can control the reactor inlet coolant temperature stably during the reactor operation, were successfully selected. And it was confirmed that the reactor inlet coolant temperature control system has the capability of controlling the reactor inlet coolant temperature stably against any disturbances on the basis of operational condition of HTTR.

JAEA Reports

Investigation of automatic shutdown of HTTR on May 21st, 2003

Hirato, Yoji; Saito, Kenji; Kondo, Makoto; Sawahata, Hiroaki; Motegi, Toshihiro; Tsuchiyama, Masaru*; Ando, Toshio*; Mizushima, Toshihiko; Nakazawa, Toshio

JAERI-Tech 2004-037, 33 Pages, 2004/04

JAERI-Tech-2004-037.pdf:4.08MB

HTTR (High Temperature Engineering Test Reactor) was operated from May 6th, 2003 to June 18th, 2003 to obtain operation data in parallel loaded operation mode and in safety demonstration tests. Operated with the reactor power at 60% of the rated power on May 21st, HTTR was automatically scrammed by a signalof "Primary coolant flow rate of the Primary Pressurized Water Cooler (PPWC): Low". The cause of the shutdown was the primary gas circulator (A) automatically stopped. The primary coolant flow rate of the PPWC decresed and reached the scram set value due to the gas circulator stop. As a result of investigation, it became clear that the cause of the gas circulator stop was malfunction of an auxiliary relay which monitored electric power of a circuit breaker in power line of the gas circulator. The cause of malfunction was deterioration of the relay under high temperature condition because the relay was installed beside an electric part which was heated up by electricity.

Journal Articles

Development and test results of a 60kA HTS current lead for fusion application

Isono, Takaaki; Hamada, Kazuya; Kawano, Katsumi; Abe, Kanako*; Nunoya, Yoshihiko; Sugimoto, Makoto; Ando, Toshinari*; Okuno, Kiyoshi; Bono, Takaaki*; Tomioka, Akira*; et al.

Teion Kogaku, 39(3), p.122 - 129, 2004/03

JAERI has been developing a large-capacity high-temperature superconductor (HTS) current lead for fusion application, and succeeded in fabricating and testing a 60kA HTS current lead satisfying ITER requirements. Targets of performance are 1/10 heat leak and 1/3 electric power consumption of cryogenic system compared with a conventional lead. To achieve the target, selection of sheath material of HTS, optimizing the Cu part, reduction of joule heat at joint between HTS and Cu parts, improve of heat transfer between HTS and stainless steel tube. Developed 60kA HTS current lead satisfied the design condition and almost achieved the targets. Adoption of the HTS current lead can reduce 13% electric power consumption of cryogenic system for ITER.

Journal Articles

Test results of 60-kA HTS current lead for fusion application

Isono, Takaaki; Kawano, Katsumi; Hamada, Kazuya; Matsui, Kunihiro; Nunoya, Yoshihiko; Hara, Eiji*; Kato, Takashi; Ando, Toshinari*; Okuno, Kiyoshi; Bono, Takaaki*; et al.

Physica C, 392-396(Part2), p.1219 - 1224, 2003/10

A 60-kA high-temperature-superconductor (HTS) current lead has been fabricated and tested for aiming at the application to a fusion magnet system, providing a low heat leak current lead. The design of HTS current leads is optimized not only to reduce the heat leak but also to perform safe operation even in fault conditions. The HTS current lead consists of a forced flow cooled copper part and a conduction cooled HTS part. The HTS part is composed of 288 Ag-10at.%Au sheathed Bi-2223 tapes and they are cylindrically arrayed on a stainless steel tube. The diameter and the length of the HTS part are 146 mm and 300 mm, respectively. Operation of a 60 kA current, which is the world record, was successfully achieved at coolant of 20 K, 3.2 g/s for the copper part, and a low heat leak of 5.5 W at 4.2 K was demonstrated. This result shows that the electric power of a refrigerator to cool the current lead can be reduced by 1/3 of that in a conventional current lead. In conclusion, technology of a large HTS current lead for fusion application is established.

Journal Articles

None

Ando, Masanori; Aoto, Kazumi; Nakagiri, Toshio

Nihon Genshiryoku Gakkai-Shi, 45(9), 568 Pages, 2003/00

None

Journal Articles

Design of a 60-kA HTS current lead for fusion magnets and its R&D

Ando, Toshinari; Isono, Takaaki; Hamada, Kazuya; Nishijima, Gen; Tsuji, Hiroshi; Tomioka, Akira*; Bono, Takaaki*; Yasukawa, Yukio*; Konno, Masayuki*; Uede, Toshio*

IEEE Transactions on Applied Superconductivity, 11(1), p.2535 - 2538, 2001/03

 Times Cited Count:6 Percentile:42.24(Engineering, Electrical & Electronic)

no abstracts in English

JAEA Reports

Physics design of advanced steady-state tokamak reactor A-SSTR 2

Nishio, Satoshi; Ushigusa, Kenkichi; Ueda, Shuzo; Polevoi, A.*; Kurita, Genichi; Tobita, Kenji; Kurihara, Ryoichi; Hu, G.; Okada, Hidetoshi*; Murakami, Yoshiki*; et al.

JAERI-Research 2000-029, 105 Pages, 2000/10

JAERI-Research-2000-029.pdf:4.19MB

no abstracts in English

Journal Articles

Particle confinement characteristics and helium ash exhaust experiments in JT-60 tokamak

Nakamura, Hiroo; Tsuji, Shunji; Shimizu, Katsuhiro; Hirayama, Toshio; Hosogane, Nobuyuki; Yoshida, Hidetoshi; Tobita, Kenji; Koide, Yoshihiko; Nishitani, Takeo; Nagashima, Keisuke; et al.

Kaku Yugo Kenkyu, 65(SPECIAL ISSUE), p.261 - 285, 1991/03

no abstracts in English

Journal Articles

H-mode experiments with outer and lower divertors in JT-60

Nakamura, Hiroo; Tsuji, Shunji; ; Ozeki, Takahisa; Ishida, Shinichi; Azumi, Masafumi; Akiba, Masato; Ando, Toshiro; Fujii, Tsuneyuki; Fukuda, Takeshi; et al.

Nuclear Fusion, 30(2), p.235 - 250, 1990/02

 Times Cited Count:16 Percentile:53.26(Physics, Fluids & Plasmas)

no abstracts in English

JAEA Reports

Results of the H-mode experiments with outer and lower divertors

Nakamura, Hiroo; Tsuji, Shunji; ; Ozeki, Takahisa; Ishida, Shinichi; Azumi, Masafumi; Akiba, Masato; Ando, Toshiro; Fujii, Tsuneyuki; Fukuda, Takeshi; et al.

JAERI-M 89-106, 52 Pages, 1989/08

JAERI-M-89-106.pdf:1.27MB

no abstracts in English

Journal Articles

Second harmonic ICRF heating experiments in JT-60

Fujii, Tsuneyuki; Kimura, Haruyuki; Saigusa, Mikio; Akiba, Masato; Ando, Toshiro; ; Aoyagi, Tetsuo; ; Azumi, Masafumi; Fukuda, Takeshi; et al.

Plasma Physics and Controlled Nuclear Fusion Research 1988, Vol.1, p.605 - 610, 1989/00

no abstracts in English

Journal Articles

Experimental investigation of pressure rise of quenching cable-in-conduit superconductor

Ando, Toshinari; Nishi, Masataka; *; Oshikiri, Masayuki*; Tada, Eisuke; T.Painter*; Shimamoto, Susumi; Uede, Toshio*; *

Proc. of the 12th Cryogenic Engineering Conf., p.908 - 912, 1988/00

no abstracts in English

Oral presentation

Fracture toughness test of small size specimens of F82H steel irradiated by neutrons

Wakai, Eiichi; Ando, Masami; Matsukawa, Shingo*; Yamamoto, Toshio; Takada, Fumiki

no journal, , 

no abstracts in English

17 (Records 1-17 displayed on this page)
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