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Journal Articles

R&D program on thermochemical water-splitting iodine-sulfur process at JAERI

Kubo, Shinji; Nakajima, Hayato; Higashi, Shunichi*; Masaki, Tomoo*; Kasahara, Seiji; Nomura, Mikihiro; Ishiyama, Shintaro; Onuki, Kaoru; Shimizu, Saburo

Proceedings of International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP 2003) (CD-ROM), p.1072_1 - 1072_7, 2003/09

Studies on thermochemical water-splitting process of iodine-sulfur family (IS process) are being carried out at Japan Atomic Energy Research Institute (JAERI). IS process is composed of three chemical reactions and works like a chemical engine to produce hydrogen and oxygen from water. HTGR that can supply high temperature of ca. 1000$$^{circ}$$C will be the most suitable energy supplier to drive IS process. JAERI demonstrated the feasibility of continuous hydrogen production by combing the fundamental reactions and separations of IS process in laboratory. At present, hydrogen production test is continuing using a scaled-up glass apparatus. Corrosion-resistant materials for constructing a large-scale plant and process improvements by introducing advanced separation techniques such as membrane separation are under study, as well. Future R&D items are discussed based on these present activities.

Journal Articles

Performance of safety system of passive safety small reactor for distributed energy supply system

Ishida, Toshihisa; Yonomoto, Taisuke; Sawada, Kenichi; Nakajima, Nobuya

Proceedings of International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP 2003) (CD-ROM), p.1081_1 - 1081_10, 2003/09

no abstracts in English

Journal Articles

Present status and future plan of HTTR project

Iyoku, Tatsuo; Nakazawa, Toshio; Kawasaki, Kozo; Hayashi, Hideyuki; Fujikawa, Seigo

Proceedings of International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP 2003) (CD-ROM), p.1094_1 - 1094_8, 2003/09

no abstracts in English

Journal Articles

Research and development programs on helium gas compressor and magnetic bearing suspended rotor for the Gas Turbine High Temperature Reactor (GTHTR300)

Takada, Shoji; Takizuka, Takakazu; Kunitomi, Kazuhiko; Yan, X.; Kosugiyama, Shinichi; Minatsuki, Isao*; Itaka, Hidehiko*; Matsumoto, Iwao*

Proceedings of International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP 2003) (CD-ROM), p.1069_1 - 1069_7, 2003/09

no abstracts in English

Journal Articles

In-vessel type control rod drive mechanism for integral-type reactors; Development and their application

Ishida, Toshihisa; Imayoshi, Sho*; Kanagawa, Takashi*

Proceedings of International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP 2003) (CD-ROM), p.1232_1 - 1232_9, 2003/09

no abstracts in English

Journal Articles

Safety demonstration tests using High Temperature Engineering Test Reactor (HTTR)

Tachibana, Yukio; Nakagawa, Shigeaki; Iyoku, Tatsuo

Proceedings of International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP 2003) (CD-ROM), 8 Pages, 2003/09

no abstracts in English

Journal Articles

Research and development program on HTTR hydrogen production system

Inagaki, Yoshiyuki; Nishihara, Tetsuo; Takeda, Tetsuaki; Hayashi, Koji; Inaba, Yoshitomo; Ohashi, Hirofumi

Proceedings of International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP 2003) (CD-ROM), p.1062_1 - 1062_6, 2003/09

JAERI has been promoting R&D on the HTTR Hydrogen Production System (HTTR-H2) with a view to establishing and demonstrating the technology to couple a hydrogen production system with a High Temperature Gas-cooled Reactor. The coupling technology consists of control and safety-related ones. The control technology aims at preventing thermal mismatch between reactor and hydrogen production systems. A simulation test with a mockup model of the HTTR-H2 has been carried out to develop this technology. The safety-related technology includes countermeasures against explosion of combustible gas and tritium permeation from helium gas to process gas, and assurance of pressure boundary between the primary and secondary helium gases and that between the secondary and process gases. As for this technology, design study and components tests are underway.

Journal Articles

Overview of large-scale technology R&D's for ITER; Engineering challenges

Seki, Masahiro; Akiba, Masato; Okuno, Kiyoshi; Shibanuma, Kiyoshi

Proceedings of International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP 2003) (CD-ROM), p.1191_1 - 1191_6, 2003/09

Variety of technology R&D's have been performed to confirm the technical feasibility of ITER construction. Special efforts have been made to demonstrate fabricability and performance of ITER critical components such as superconducting magnets, the vacuum vessel, blanket modules, divertor cassettes, and remote handling system. The central solenoid (CS) model coil has successfully achieved 13 T at a current of 46 kA with a stored energy of 640 MJ. Pulsed operations with a ramp-up rate of 0.6 T/s and ramp-down rate of 1.2 T/s were also successfully performed. The full-scale sector model of the vacuum vessel, which has a D-shape of 15m high and 9m wide, was fabricated within an allowable deformation. The divertor components were developed to survive a heat flux of 20 MW/m$$^{2}$$ for 2000 cycles. The result of these activities has convinced us to proceed to collaboration for ITER construction.

Journal Articles

Evaluation of hydrogen production system with High Temperature Gas-cooled Reactor

Ogawa, Masuro; Shiozawa, Shusaku

Proceedings of International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP 2003) (CD-ROM), p.1055_1 - 1055_8, 2003/09

no abstracts in English

Journal Articles

Subchannel analysis of CHF experiments for tight-lattice core

Nakatsuka, Toru; Tamai, Hidesada; Kureta, Masatoshi; Okubo, Tsutomu; Akimoto, Hajime; Iwamura, Takamichi

Proceedings of International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP 2003) (CD-ROM), 6 Pages, 2003/09

It is important to evaluate thermal margin of the tight lattice core in the Reduced-Moderation Water reactor (RMWR). In the present study, to assess the applicability of subchannel analysis for tight lattice cores, tight lattice CHF experiments were analyzed with COBRA-TF code. For the axial uniform heated rod bundle, the code gives good prediction of critical power for mass velocity of around 500kg/(m$$^{2}$$s), while the code underestimates it for lower mass velocity and overestimates for higher mass velocity. The predicted BT position was outer channels and differed from the measured position. For the axially double-humped heated bundle, the code gives good prediction for mass velocity of around 200kg/(m$$^{2}$$s), and overestimates for higher mass velocity. It turned out that the two-phase multiplier of friction loss have a large influences on the flow distribution among the subchannels. To improve the calculation accuracy, it is required to predict precisely the flow distribution including the prediction of pressure distribution in a tight lattice bundle.

Journal Articles

Overview of ITER project; Objective, history, status of development, structure and its future

Matsuda, Shinzaburo

Proceedings of International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP 2003) (CD-ROM), p.1188_1 - 1188_9, 2003/09

no abstracts in English

Journal Articles

Development of 3D Seismic Isolation Techology for Advanced Nuclear Power Plant Application

Moro, Satoshi; Ito, Kei; Kitamura, Seiji

Proceedings of International Conference on Advanced Nuclear Power (GENES4/ANP2003) (CD-ROM), P. 1110, 2003/00

None

Journal Articles

Twenty-four-year experience of industrial-scale plutonium utilization in the Fugen Nuclear Power Station

Iijima, Takashi; ;

Proceedings of International Conference on Advanced Nuclear Power (GENES4/ANP2003) (CD-ROM), 0 Pages, 2003/00

None

Journal Articles

ATR-MOX Fuel Design and Development

Maeda, Seiichiro; Abe, Tomoyuki; Nakazawa, Hiroaki

Proceedings of International Conference on Advanced Nuclear Power (GENES4/ANP2003) (CD-ROM), 8 Pages, 2003/00

None

Journal Articles

R&D issues in Structural Design Standard for commercialized Fast Rreactor Components

Shibamoto, Hiroshi; Tanaka, Yoshihiko; kasahara, Naoto; Ito, Kei; Inoue, Kazuhiko

Proceedings of International Conference on Advanced Nuclear Power (GENES4/ANP2003) (CD-ROM), P. 120, 2003/00

None

Journal Articles

Development of distributed plant monitoring and diagnosis system at MONJU

Okusa, Ryoichi; Tamayama, Kiyoshi;

Proceedings of International Conference on Advanced Nuclear Power (GENES4/ANP2003) (CD-ROM), 0 Pages, 2003/00

None

Journal Articles

Conceptual Design of a Medium Scale Lead-Bismuth Cooled Fast Reactor

Enuma, Yasuhiro; ; Soman, Yoshindo; Konomura, Mamoru

Proceedings of International Conference on Advanced Nuclear Power (GENES4/ANP2003) (CD-ROM), P. 1085, 2003/00

None

Journal Articles

Evaluation Methodology and Prospective Introduction Scenarios of FR Cycle Systems

; Kato, Atsushi; Sato, Kazujiro

Proceedings of International Conference on Advanced Nuclear Power (GENES4/ANP2003) (CD-ROM), 0 Pages, 2003/00

None

Journal Articles

MA/LLFP transmutation experiment options in the future MONJU CORE

Kitano, Akihiro; Nishi, Hiroshi; Ishibashi, Junichi

Proceedings of International Conference on Advanced Nuclear Power (GENES4/ANP2003) (CD-ROM), 0 Pages, 2003/00

None

Journal Articles

The Current status of R&D for accelerator-driven system at JAERI

Sasa, Toshinobu; Oigawa, Hiroyuki; Tsujimoto, Kazufumi; Nishihara, Kenji; Umeno, Makoto*; Takano, Hideki*

Proceedings of International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP 2003) (CD-ROM), 8 Pages, 2003/00

Japan Atomic Energy Research Institute (JAERI) performs research and development for accelerator-driven transmutation systems to improve the environmental impact and increase a capacity of waste disposal plant. The system consists of a superconducting proton LINAC, Pb-Bi eutectic spallation target and Pb-Bi cooled subcritical core. Thermal output of the system is 800MW by injection of the proton beam with the power of 20 to 30MW and then, about 250kg of minor actinides can be transmuted annually. To study and evaluate the feasibility of ADS by a physical and an engineering viewpoint, the Transmutation Experimental Facility is proposed under a framework of J-PARC project. In the presentation, the R&D activities by the contract between the Ministry of Education, Culture, Sports, Science and Technology will be presented.

29 (Records 1-20 displayed on this page)