Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
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
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
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
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
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
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/(ms), 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.
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
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
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
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.
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 for 2000 cycles. The result of these activities has convinced us to proceed to collaboration for ITER construction.
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
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.
Sawa, Kazuhiro; Ueta, Shohei; Iyoku, Tatsuo
Proceedings of International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP 2003) (CD-ROM), 10 Pages, 2003/00
This paper provides present status of research and development for the coated fuel particle (CFPs) including the advanced ZrC-CFP. Current HTGR employs so-called TRISO-CFPs with SiC layer. In safety design of the HTGR fuels, it is important to retain fission products within CFPs so that their release to primary coolant does not exceed an acceptable level. The behavior of TRISO-CFPs has been investigated through experiments and reactor operation. These data show excellent performance of the TRISO-CFPs when they are correctly fabricated. On the other hand, the crystalline material comprising the SiC layer has a tendency to decompose at high temperature. The transition temperatures of beta-SiC (as-deposited) to alpha-SiC vary from 1600 to 2200C. ZrC is one of the transition metal carbides which are characterized by the high melting point and the thermodynamic stability etc. The CFPs with CVD-ZrC coatings have been investigated including the fabrication processes and characterization techniques developments.
Yoshida, Hiroyuki; Takase, Kazuyuki; Ose, Yasuo*; Tamai, Hidesada; Akimoto, Hajime
Proceedings of International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP 2003) (CD-ROM), 8 Pages, 2003/00
no abstracts in English
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.
Okubo, Tsutomu; Iwamura, Takamichi; Takeda, Renzo*; Yamauchi, Toyoaki*; Okada, Hiroyuki*
Proceedings of International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP 2003) (CD-ROM), 8 Pages, 2003/00
A water-cooled reactor concept named Reduced-Moderation Water Reactor is under development for effective fuel utilization through plutonium multiple recycling based on the water-cooled reactor technology. The reactor aims at achievement of a high conversion ratio more than 1.0 with MOX fuel. Especially, the core performances during the Pu multiple recycling have been investigated for the advanced fuel reprocessing schemes with low decontamination factors than the current PUREX process, and are shown to achieve the conversion ratio more than 1.0 and the negative void reactivity coefficient.