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Journal Articles

Gallium-effect in a lead-free solder for silver-sheathed superconducting tape

Shamoto, Shinichi; Lee, M. K.*; Fujimura, Yuki; Kondo, Keietsu; Ito, Takashi; Ikeuchi, Kazuhiko*; Yasuda, Satoshi; Chang, L.-J.*

Materials Research Express (Internet), 8(7), p.076303_1 - 076303_6, 2021/07

 Times Cited Count:0 Percentile:0.00(Materials Science, Multidisciplinary)

Pb, Ga, and Ga doped lead free Sn-Ag-Cu solders are used to study the gallium effect for the low joint resistivity with silver sheathed DI BISCCO type H tapes. The results are reported.

Journal Articles

CFD analysis

Takase, Kazuyuki; Misawa, Takeharu*

Supercritical-Pressure Light Water Cooled Reactors, p.301 - 319, 2014/12

no abstracts in English

Journal Articles

Nuclear technology and potential ripple effect of superconducting magnets for fusion power plant

Nishimura, Arata*; Muroga, Takeo*; Takeuchi, Takao*; Nishitani, Takeo; Morioka, Atsuhiko

Fusion Engineering and Design, 81(8-14), p.1675 - 1681, 2006/02

 Times Cited Count:3 Percentile:23.59(Nuclear Science & Technology)

In a fusion reactor plant, a neutral beam injector (NBI) will be operated for a long time, and it will allow neutron streaming from NBI ports to outside of the plasma vacuum vessel. It requires the superconducting magnet to develop nuclear technology to produce stable magnetic field and to reduce activation of the magnet components. In this report, the back ground of the necessity and the contents of the nuclear technology of the superconducting magnets for fusion application are discussed and some typical investigation results are presented, which are the neutron irradiation effect on Nb$$_{3}$$Sn wire, the development of low activation superconducting wire, and the design concept to reduce nuclear heating and nuclear transformation by streaming. In addition, recent activities in high energy particle physics are introduced and potential ripple effect of the technology of the superconducting magnets is described briefly.

JAEA Reports

Report on the 8th Workshop on the Innovative Water Reactor for Flexible Fuel Cycle; February 10, 2005, Koku-kaikan, Minato-ku, Tokyo

Kobayashi, Noboru; Okubo, Tsutomu; Uchikawa, Sadao

JAERI-Review 2005-029, 119 Pages, 2005/09

JAERI-Review-2005-029.pdf:11.01MB

The research on Innovative Water Reactor for Flexible fuel cycle (FLWR) has been performed in JAERI for the development of future innovative reactors. The workshop on the FLWRs has been held every year since 1998 aiming at information exchange between JAERI and other organizations. The 8th workshop was held on Feb. 10, 2005 under the joint auspices of JAERI and North Kanto and Kanto-Koetsu branches of Atomic Energy Society of Japan with 75 participants. The workshop began with 3 presentations on FLWRs entitled "Framework and Status of Research and Development on FLWRs", "Long-Term Fuel Cycle Scenarios for Advanced Utilization of Plutonium from LWRs", and "Experiments on Characteristics on Hydrodynamics in Tight-Lattice Core". Then 3 lectures followed: "Development of Evaluation Method for Accuracy in Predicting Neutronics Characteristics of Tight-Lattice Core" by Osaka University, "Development of Cost-Reduced Low-Moderation Spectrum Boiling Water Reactor" by Toshiba Corporation and "Design and Analysis on Super-Critical Water Cooled Power Reactors" by Tokyo University.

Journal Articles

Development of a heat-resistant neutron shielding resin for the national centralized tokamak

Morioka, Atsuhiko; Sakurai, Shinji; Okuno, Koichi*; Tamai, Hiroshi

Purazuma, Kaku Yugo Gakkai-Shi, 81(9), p.645 - 646, 2005/09

A 300 $$^{circ}$$C heat-resistant neutron shielding material is newly developed, which consists of phenol-based resin with 5 weight-% boron. The neutron shielding performance of the developed resin, examined by the $$^{252}$$Cf neutron source, is almost the same as that of the polyethylene. The resin is applicable to the port section of vacuum vessel of the DD plasma device to suppress the streaming neutrons and to reduce the nuclear heating of the superconducting coils.

Journal Articles

Novel pressure phase diagram of heavy fermion superconductor CePt$$_{3}$$Si investigated by ac calorimetry

Tateiwa, Naoyuki; Haga, Yoshinori; Matsuda, Tatsuma; Ikeda, Shugo; Yasuda, Takashi*; Takeuchi, Tetsuya*; Settai, Rikio*; Onuki, Yoshichika

Journal of the Physical Society of Japan, 74(7), p.1903 - 1906, 2005/07

 Times Cited Count:73 Percentile:88.91(Physics, Multidisciplinary)

The pressure dependences of the antiferromagnetic and superconducting transition temperatures have been investigated by ac heat capacity measurement under high pressures for the heavy-fermion superconductor CePt$$_3$$Si without inversion symmetry in the tetragonal structure. The N$'e$el temperature $$T_{rm N}$$ = 2.2 K decreases with increasing pressure and becomes zero at the critical pressure $$P_{rm AF}$$ $$simeq$$ 0.6 GPa. On the other hand, the superconducting phase exists in a wider pressure region from ambient pressure to about 1.5 GPa. The pressure phase diagram of CePt$$_3$$Si is thus very unique and has never been reported before for other heavy fermion superconductors.

JAEA Reports

Research and development plan of fusion technologies in JAERI toward DEMO reactors

Department of Fusion Engineering Research

JAERI-Review 2005-011, 139 Pages, 2005/03

JAERI-Review-2005-011.pdf:11.95MB

no abstracts in English

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.

JAEA Reports

Summary of the 6th Workshop on the Reduced-Moderation Water Reactor; March 6, 2003, JAERI, Tokai

Nabeshima, Kunihiko; Nakatsuka, Toru; Ishikawa, Nobuyuki; Uchikawa, Sadao

JAERI-Conf 2003-020, 240 Pages, 2003/11

JAERI-Conf-2003-020.pdf:27.66MB

The research on Reduced-Moderation Water Reactors (RMWRs) has been performed in JAERI for the development of future innovative reactors. The workshop on the RMWRs has been held every year since 1998 aimed at information exchange between JAERI and other organizations such as universities, laboratories, utilities and vendors. The workshop began with five lectures on status of research and development on RMWRs in JAERI entitled "Status and Future Program of Research and Development on Reduced-Moderation Water Reactors", "Design of Small Reduced-Moderation Water Reactors", "Critical Experiments for Reduced-Moderation Water Reactors", "Critical Heat Flux Experiments in Tight Lattice Core" and "Development of High Performance Cladding". Then two lectures followed: "Status of Phase II of Feasibility Studies on Commercialized Fast Breeder Reactor System" by JNC and "Present Status of Study on Super-critical water Cooled Power Reactor" by Toshiba Corporation.

Journal Articles

Development of supercritical pressure water cooled solid breeder blanket in JAERI

Akiba, Masato; Ishitsuka, Etsuo; Enoeda, Mikio; Nishitani, Takeo; Konishi, Satoshi

Purazuma, Kaku Yugo Gakkai-Shi, 79(9), p.929 - 934, 2003/09

no abstracts in English

Journal Articles

Thermal-hydraulic design of J-PARC cold moderators

Aso, Tomokazu; Sato, Hiroshi; Kaminaga, Masanori; Hino, Ryutaro; Monde, Masanori*

Proceedings of ICANS-XVI, Volume 2, p.935 - 944, 2003/07

no abstracts in English

Journal Articles

Thermal conductivity of superplastically deformed 3Y-TZP

Wan, C.*; Motohashi, Yoshinobu*; Shibata, Taiju; Baba, Shinichi; Ishihara, Masahiro; Hoshiya, Taiji

Materials Transactions, 43(10), p.2473 - 2479, 2002/10

 Times Cited Count:14 Percentile:62.05(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Experimental investigation on the effect of superplastic deformation on the specific heat of a zirconia-based ceramic

Wan, C.*; Shibata, Taiju; Baba, Shinichi; Ishihara, Masahiro; Hoshiya, Taiji; Motohashi, Yoshinobu*

Netsu Bussei, 16(2), p.58 - 63, 2002/06

no abstracts in English

JAEA Reports

Development of the fabrication technology for the superconducting coils in the ITER magnet system and its achievements

Hamada, Kazuya; Nakajima, Hideo; Okuno, Kiyoshi; Endo, Sakaru*; Kikuchi, Kenichi*; Kubo, Yoshio*; Aoki, Nobuo*; Yamada, Yuichi*; Osaki, Osamu*; Sasaki, Takashi*; et al.

JAERI-Tech 2002-027, 23 Pages, 2002/03

JAERI-Tech-2002-027.pdf:2.94MB

The Engineering Design Activities (EDA) for the International Thermonuclear Experimental Reactor (ITER) was performed under the collaboration of Japan, EU, Russia and the US. The EDA was successfully completed in July 2001, in which the development of fabrication technology for advanced components, such as superconducting coils, was conducted. The ITER magnet system consists of Toroidal Field coils, a Central Solenoid (CS), Poloidal Field coils and Correction coils. The construction of these coils requires advanced technologies that fairly exceeded those available at the start of the EDA. Therefore, CS Model Coil and TF Model Coil projects were implemented. To fabricate the CS Model Coil, the fabrication technologies for high performance strand, large cable, winding, heat treatment, joint and insulation are indispensable. This report describes the above detailed fabrication technologies successfully developed in the CS Model Coil Project.

Journal Articles

Effects of superplastic deformation on thermal and mechanical properties of 3Y-TZP ceramics (Review)

Ishihara, Masahiro; Shibata, Taiju; Baba, Shinichi; Hoshiya, Taiji; Wan, C.*; Motohashi, Yoshinobu*

Proceedings of OECD/NEA 2nd Information Exchange Meeting on Basic Studies in the Field of High-temperature Engineering, p.113 - 124, 2001/00

no abstracts in English

Journal Articles

Benchmark experiment on bulk shield of SS316/water with simulated superconducting magnet

Konno, Chikara; Maekawa, Fujio; Oyama, Yukio; Wada, Masayuki*; Ikeda, Yujiro; Maekawa, Hiroshi; Kasugai, Yoshimi; M.Z.Youssef*; A.Kumar*; M.A.Abdou*

Fusion Engineering and Design, 42, p.267 - 273, 1998/00

 Times Cited Count:2 Percentile:24.18(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Thermal characteristics of microencapsulated phase-change materials

E.Choi*; Akino, Norio

Proc. of 11th Int. Heat Transfer Conf. (Heat Transfer 1998), 7, p.121 - 126, 1998/00

no abstracts in English

Journal Articles

A Safety analysis of the ITER superconducting magnet system in case of loss of vacuum in the ITER cryostat

Kato, Takashi; ; ; Matsui, Kunihiro; ; Tsuji, Hiroshi; N.Michel*; Yoshida, Kiyoshi; Shimamoto, Susumi

Fusion Technology, 30(3), p.1253 - 1257, 1996/12

no abstracts in English

JAEA Reports

Evaluation of inductive heating energy of sub-size improved DPC-U conductor by calorimetric method

; Koizumi, Norikiyo; Wakabayashi, Hiroshi*; Miura, Yushi; ; Matsui, Kunihiro; Takahashi, Yoshikazu; Tsuji, Hiroshi

JAERI-Research 96-042, 14 Pages, 1996/08

JAERI-Research-96-042.pdf:0.88MB

no abstracts in English

Journal Articles

Thermohydraulic experiments on a water jet into vacuum during ingress of coolant event in a fusion experimental reactor

Ogawa, Masuro; Kunugi, Tomoaki

Fusion Engineering and Design, 29, p.233 - 237, 1995/00

 Times Cited Count:11 Percentile:71.31(Nuclear Science & Technology)

no abstracts in English

34 (Records 1-20 displayed on this page)