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Journal Articles

Status of R&D of high-performance monitoring system under sever accident

Tsuchiya, Kunihiko; Takeuchi, Tomoaki; Komanome, Hirohisa*; Miura, Kuniaki*; Araki, Masanori; Ishihara, Masahiro

Nihon Hozen Gakkai Dai-13-Kai Gakujutsu Koenkai Yoshishu, p.375 - 378, 2016/07

no abstracts in English

Journal Articles

Research and development of high-performance instruments for safety measure for LWRs

Takeuchi, Tomoaki; Ueno, Shunji; Komanome, Hirohisa*; Otsuka, Noriaki; Shibata, Hiroshi; Kimura, Nobuaki; Matsui, Yoshinori; Tsuchiya, Kunihiko; Araki, Masanori

Proceedings of 6th International Symposium on Material Testing Reactors (ISMTR-6) (Internet), 7 Pages, 2013/10

During the station blackout situation at the Fukushima Dai-ichi (1F) Nuclear Power Plant, conventional in-pile instrumentation systems did not work sufficiently, resulting in the progress of the severe accident. In June 2011, the Japanese government referred to "Enhancement of instrumentation to identify the status of the reactors and PCVs" as a lesson of the accident at the 1F NPP, in the report of Japanese government to the IAEA ministerial conference in accordance with such situation, we started from 2012 a research and development which corresponds to the provisions so as to monitor the NPPs situations during a severe accident. In this research and development, we have been building of technical bases of a radiation-resistant high-definition and high-sensitivity monitoring camera, a wireless transmission system, and radiation- and heat-resistant signal line. The objective and latest progress situations of the R&D including the results of the characteristic experiments will be introduced in this symposium.

Journal Articles

Recent progress in blanket materials development in the Broader Approach Activities

Nishitani, Takeo; Tanigawa, Hiroyasu; Nozawa, Takashi; Jitsukawa, Shiro; Nakamichi, Masaru; Hoshino, Tsuyoshi; Yamanishi, Toshihiko; Baluc, N.*; M$"o$slang, A.*; Lindou, R.*; et al.

Journal of Nuclear Materials, 417(1-3), p.1331 - 1335, 2011/10

 Times Cited Count:12 Percentile:71.79(Materials Science, Multidisciplinary)

As a part of the Broader Approach (BA) activities, the research and development on blanket related materials and tritium technology have been initiated toward DEMO by Japan and EU. Recently, those five R&D items have progressed substantially in Japan and EU. As a preparatory work aiming at the RAFM steel muss-production development, a 5-ton heat of RAFM steel (F82H) was procured with the Electro Slag Re-melting as a secondary melting. The result of the double notch tensile test method for the NITE-SiC$$_{f}$$/SiC specimen indicated notch insensitivity and very minor size effect on proportional limit tensile stress and fracture strength. For the fabrication technology development of beryllide neutron multiplayer pebbles, Be- Ti inter-metallic pebbles have been sintered directly from the mixed powder of Be and Ti in Japan.

Journal Articles

Structural components with high temperature environment

Araki, Masanori; Suzuki, Satoshi

Purazuma, Kaku Yugo Gakkai-Shi, 87(Suppl.), p.155 - 161, 2011/02

For the nuclear fusion reactor, issues of heat removal technologies, its thermal stresses and fatigues of the divertor component as a part of report in the core plasma physics and the engineering technologies for DEMO reactor are described in this session.

Journal Articles

Progress of IFERC project in the Broader Approach activities

Araki, Masanori; Sakamoto, Yoshiteru; Hayashi, Kimio; Nishitani, Takeo; Ouchi, Rei*

Fusion Engineering and Design, 85(10-12), p.2196 - 2202, 2010/12

 Times Cited Count:10 Percentile:60.62(Nuclear Science & Technology)

For contributing to the ITER project and promoting a possible early realization of DEMO, the IFERC project shall perform the activities on (1) DEMO Design and R&D Coordination, (2) Computational Simulation Centre, and (3) ITER Remote Experimentation Centre in the framework under the BA agreement. The DEMO design activity aims at establishing a common basis for DEMO design, including design features of DEMO, a possible common concept of DEMO, a roadmap for DEMO, and so on. Based on the common interest toward DEMO, the DEMO R&D activities have been planned and carried out for the following five areas which are relevant to blanket development: (1) SiC/SiC composites, (2) tritium technology, (3) materials engineering for DEMO blanket, (4) advanced neutron multiplier for DEMO blanket, and (5) advanced tritium breeders for DEMO blanket. In the activity of the Computational Simulation Centre, the objective is to provide and exploit a supercomputer for large scale simulation activities to analyse experimental data on fusion plasmas, prepare scenarios for ITER operation, predict the performance of the ITER facilities and contribute to the DEMO design. At the initial phase, high-level benchmark codes in the fusion research field have been selected through Special Working Group.

Journal Articles

Present status of integrated performance achieved in tokamak experiments and critical issues towards DEMO reactor

Sakamoto, Yoshiteru; Tobita, Kenji; Araki, Masanori

Journal of Plasma and Fusion Research SERIES, Vol.9, p.375 - 380, 2010/08

Recent tokamak experiments have achieved high fusion performances. Moreover, the ITER as the next step device will demonstrate the fusion burning with Q = 10, which provides the physics basis of burning plasma, including the behavior of energetic particle and the effect of self-heating towards DEMO reactors. The DEMO reactor requires not only the fusion performance but also the integrated performance. This paper summarizes the present status of the integrated performance achieved in the experiments to clarify the critical issues towards the DEMO reactor.

Journal Articles

International Fusion Energy Research Centre

Araki, Masanori; Hayashi, Kimio; Tobita, Kenji; Nishitani, Takeo; Tanigawa, Hiroyasu; Nozawa, Takashi; Yamanishi, Toshihiko; Nakamichi, Masaru; Hoshino, Tsuyoshi; Ozeki, Takahisa; et al.

Purazuma, Kaku Yugo Gakkai-Shi, 86(4), p.231 - 239, 2010/04

The Broader Approach Activities, which support the ITER Project and implement activities to aim early realization of fusion energy, is an EU-Japan collaborative project to carry out various kinds of researches and developments during the period of the ITER construction phase. In this special topic, achievements and prospects of the projects on the International Fusion Energy Research Centre (IFERC) is described.

Journal Articles

Fusion materials development program in the Broader Approach activities

Nishitani, Takeo; Tanigawa, Hiroyasu; Jitsukawa, Shiro; Nozawa, Takashi; Hayashi, Kimio; Yamanishi, Toshihiko; Tsuchiya, Kunihiko; M$"o$slang, A.*; Baluc, N.*; Pizzuto, A.*; et al.

Journal of Nuclear Materials, 386-388, p.405 - 410, 2009/04

 Times Cited Count:31 Percentile:89.62(Materials Science, Multidisciplinary)

The establishment of the breeding blanket technology is one of the most important engineering issues on the DEMO development. For the DEMO blanket, developments of the structural materials and functional materials such as tritium breeder and neutron multiplier. Which should be used under the savior circumstance such as high neutron fluence, high temperature and strong magnetic field, are urgent issues. In the Broader Approach activities initiated by EU and Japan, developments of reduced activation ferritic martensitic steels as a DEMO blanket structural material, SiC/SiC composites, advanced tritium breeders and neutron multiplier for DEMO blankets, are planed as common interest issues of EU and Japan. This paper describes the overview of the development program.

Journal Articles

Current status and evolution of nuclear fusion development; Aiming at the achievement of the nuclear fusion energy

Araki, Masanori; Kamada, Yutaka; Mori, Masahiro; Nishitani, Takeo

Denki Hyoron, 92(10), p.38 - 44, 2007/10

A general view of the current status and evolution of nuclear fusion research and development in JAEA is reviewed. Concretely, the outline is shown about the fruitful results of research that are obtaining mainly on an experimental device JT-60 concisely, and the international thermonuclear experimental reactor ITER project (design and technical R&D activities, and details for construction) as well as a Broader Approach Activities for aiming at the achievement of a DEMO reactor and of a nuclear fusion energy.

Journal Articles

Multi-physics and multi-scale simulation for core disruptive accidents in fast breeder reactors

Koshizuka, Seiichi*; Liu, J.*; Morita, Koji*; Arima, Tatsumi*; Tobita, Yoshiharu; Yamano, Hidemasa; Ito, Takahiro*; Shirakawa, Noriyuki*; Hosoda, Seigo*; Araki, Kazuhiro*; et al.

Proceedings of 5th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-5), p.472 - 479, 2006/11

A 5-year research project started in FY2005 in the framework of Innovative Nuclear Research and Development Program funded by the Ministry of Education, Culture, Sports, Science and Technology in Japan. A computer code, named COMPASS (Computer Code with Moving Particle Semi-implicit for Reactor Safety Analysis), is being developed using the Moving Particle Semi-implicit (MPS) method for various complex phenomena of severe accidents in fast breeder reactors. Both MOX and metal fuels are considered. Eutectic reactions between the metal fuel and the cladding material are being investigated by molecular dynamics and molecular orbital methods. The molten metal flow with solidification was analyzed by MPS. The elastic analysis of a hexagonal wrapper tube was analyzed by the MPS method as well. The results were compared with an experiment and an calculation using an commercial code. Eutectic reactions were calculated by molecular dynamics and compared with the references. We found that the combination of the above numerical methods was useful for multi-physics and multi-scale phenomena of core disruptive accidents in fast breeder reactors.

JAEA Reports

Study for characteristic of dynamic analysis models for tokamak complex of International Thermonuclear Experimental Reactor (ITER)

Nakakura, Kensuke*; Yagenji, Akira*; Shoji, Teruaki*; Araki, Masanori; Neyatani, Yuzuru; Tanaka, Eiichi*; Shima, Hiroaki*

JAERI-Tech 2005-058, 61 Pages, 2005/09

JAERI-Tech-2005-058.pdf:4.49MB

The design of International Thermonuclear Experimental Reactor (ITER) had been done during the period of Engineering Design Activities (EDA) and its final deign report was published on July 2001. After that the further design studies have been performed as activities in the CTA and ITA periods. As for Tokamak complex, Japan Atomic Energy Research Institute (JAERI) performed preliminary study for both static and dynamic analyses with a few types of analysis models based on the Technical Guidelines for Aseismic Design of Nuclear Power Plants etc during EDA. In comparison with reactor building for nuclear fission power plant, its outside is not so different from reactor building's one. However, its structural characteristics inside building are apparently different from reactor building's one, because the bio shield of Tokamak complex has a lot of large penetration of ports. Therefore, characteristic of dynamic analysis models for Tokamak complex needs to be evaluated in order to perform the detailed design of Tokamak complex in account for site-dependent conditions. This report describes results of characteristic evaluation with representative analytical models for Tokamak complex, which are modeled with Finite Element Method and Lumped mass, and it is confirmed that adopted evaluation method of the bio shield wall and floor's stiffnesses around the bio shield wall for Lumped mass model is adequate.

JAEA Reports

Study for reducing radioactive solid waste at ITER decommissioning period

Sato, Shinichi*; Araki, Masanori; Omori, Junji*; Oono, Isamu*; Sato, Satoshi; Yamauchi, Michinori*; Nishitani, Takeo

JAERI-Tech 2002-083, 126 Pages, 2002/10

JAERI-Tech-2002-083.pdf:4.07MB

It is one of the foremost goals for ITER to demonstrate the attractiveness with regard to safety and environmental potential. This implies that the radioactive materials and waste at decommissioning phase should carefully be treated with prescribed regulations. As possible activities during the Coordinated Technical Activity (CTA), Japanese Participant Team (JA-PT) has proposed a study for searching the possibility of more reduction in the activated level by taking account of minimum material changes while keeping original design concept and structure. Based on it, reassessment of the activation level and the amount of activation volumes will give us positive aspects for public acceptance.

JAEA Reports

Alternatives of ITER vacuum vessel support system

Omori, Junji*; Kitamura, Kazunori*; Araki, Masanori; Oono, Isamu*; Shoji, Teruaki

JAERI-Tech 2002-053, 86 Pages, 2002/07

JAERI-Tech-2002-053.pdf:3.81MB

no abstracts in English

Journal Articles

The Summary report on engineering design activities in the International Thermonuclear Experimental Reactor (ITER) project

Mori, Masahiro; Shoji, Teruaki; Araki, Masanori; Saito, Keiji*; Senda, Ikuo; Omori, Junji*; Sato, Shinichi*; Inoue, Takashi; Ono, Isamu*; Kataoka, Takahiro*; et al.

Nihon Genshiryoku Gakkai-Shi, 44(1), p.16 - 89, 2002/01

no abstracts in English

Journal Articles

ITER engineering design

Shimomura, Yasuo; Tsunematsu, Toshihide; Yamamoto, Shin; Maruyama, So; Mizoguchi, Tadanori*; Takahashi, Yoshikazu; Yoshida, Kiyoshi; Kitamura, Kazunori*; Ioki, Kimihiro*; Inoue, Takashi; et al.

Purazuma, Kaku Yugo Gakkai-Shi, 78(Suppl.), 224 Pages, 2002/01

no abstracts in English

Journal Articles

Conceptual tokamak design at high neutron fluence

Araki, Masanori; Sato, Shinichi*; Senda, Ikuo; Omori, Junji*; Shoji, Teruaki

Fusion Engineering and Design, 58-59, p.887 - 892, 2001/11

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Critical heat flux test on saw-toothed fin duct under one-sided heating conditions

Ezato, Koichiro; Suzuki, Satoshi; Sato, Kazuyoshi; Taniguchi, Masaki; Hanada, Masaya; Araki, Masanori; Akiba, Masato

Fusion Engineering and Design, 56-57, p.291 - 295, 2001/10

 Times Cited Count:7 Percentile:50.11(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Ultrasonic non-destractive testing on CFC monoblock divertor mock-up

Ezato, Koichiro; Taniguchi, Masaki; Sato, Kazuyoshi; Araki, Masanori; Akiba, Masato

Physica Scripta, T91, p.110 - 112, 2001/07

 Times Cited Count:2 Percentile:21.24(Physics, Multidisciplinary)

no abstracts in English

Journal Articles

Design analysis on the magnetic field control system in compact ITER

Senda, Ikuo; Shoji, Teruaki; Araki, Masanori; ITER Japan Home Team; ITER Joint Central Team

International Journal of Applied Electromagnetics and Mechanics, 13(1-4), p.349 - 357, 2001/00

no abstracts in English

JAEA Reports

Assessment of buckling for vacuum vessel and back plate of RC-ITER (IAM-v2)

Omori, Junji*; Araki, Masanori

JAERI-Tech 2000-006, p.15 - 0, 2000/02

JAERI-Tech-2000-006.pdf:0.66MB

no abstracts in English

135 (Records 1-20 displayed on this page)