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Journal Articles

Investigation of water-vapor two-phase flow characteristics in a tight-lattice core by large-scale numerical simulation, 4; Large-scale analysis of water-vapor two-phase flow in rod bundles with TPFIT code using earth simulator

Yoshida, Hiroyuki; Ose, Yasuo*; Kureta, Masatoshi*; Nagayoshi, Takuji*; Takase, Kazuyuki; Akimoto, Hajime

Nippon Genshiryoku Gakkai Wabun Rombunshi, 4(2), p.106 - 114, 2005/06

no abstracts in English

Journal Articles

Current status of thermal/hydraulic feasibility project for reduced-moderation water reactor, 1; Large-scale thermal/hydraulic test

Tamai, Hidesada; Onuki, Akira; Kureta, Masatoshi*; Liu, W.; Sato, Takashi; Akimoto, Hajime

Proceedings of 2005 International Congress on Advances in Nuclear Power Plants (ICAPP '05) (CD-ROM), 8 Pages, 2005/05

no abstracts in English

Journal Articles

Investigation of water-vapor two-phase flow characteristics in a tight-lattice core by large-scale numerical simulation, 3; Analysis of liquid film falling down on inclined flat plate

Yoshida, Hiroyuki; Nagayoshi, Takuji*; Ose, Yasuo*; Takase, Kazuyuki; Akimoto, Hajime

Nippon Genshiryoku Gakkai Wabun Rombunshi, 4(1), p.25 - 31, 2005/03

no abstracts in English

Journal Articles

Numerical simulation of single bubble behavior in rod bundle with interface tracking method

Yoshida, Hiroyuki; Nagayoshi, Takuji*; Tamai, Hidesada; Takase, Kazuyuki; Akimoto, Hajime

Proceedings of 4th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-4), p.264 - 269, 2004/12

no abstracts in English

Journal Articles

Development of a large-scale numerical simulation method on water-vapor two-phase flow through light-water reactor cores

Yoshida, Hiroyuki; Ose, Yasuo*; Takase, Kazuyuki; Akimoto, Hajime

Proceedings of 4th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-4), p.270 - 276, 2004/12

no abstracts in English

Journal Articles

Numerical investigation of two-phase flow structure around fuel rods with spacers by large-scale simulations

Takase, Kazuyuki; Yoshida, Hiroyuki; Ose, Yasuo*; Kureta, Masatoshi; Tamai, Hidesada; Akimoto, Hajime

Proceedings of 5th International Conference on Multiphase Flow (ICMF 2004) (CD-ROM), 14 Pages, 2004/06

no abstracts in English

Journal Articles

Pressure drop characteristics in tight-lattice bundles for reduced-moderation water reactors

Tamai, Hidesada; Kureta, Masatoshi; Yoshida, Hiroyuki; Akimoto, Hajime

JSME International Journal, Series B, 47(2), p.293 - 298, 2004/05

no abstracts in English

Journal Articles

Direct numerical simulation on fluid flow characteristics in a tight-lattice fuel bundle

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, 2003/09

no abstracts in English

Journal Articles

Large-scale numerical simulations of two-phase flow behavior in a fuel bundle of a reduced-moderation light water reactor

Takase, Kazuyuki; Yoshida, Hiroyuki; Ose, Yasuo*; Tamai, Hidesada; Kano, Takuma; Akimoto, Hajime

Nippon Konsoryu Gakkai Nenkai Koenkai 2003 Koen Rombunshu, p.33 - 34, 2003/00

no abstracts in English

Journal Articles

Critical heat flux experiments in tight lattice core

Kureta, Masatoshi

JAERI-Conf 2002-012, p.47 - 52, 2002/12

no abstracts in English

Journal Articles

Design of small Reduced-Moderation Water Reactor (RMWR) with natural circulation cooling

Okubo, Tsutomu; Suzuki, Motoe; Iwamura, Takamichi; Takeda, Renzo*; Moriya, Kumiaki*; Kanno, Minoru*

Proceedings of International Conference on the New Frontiers of Nuclear Technology; Reactor Physics, Safety and High-Performance Computing (PHYSOR 2002) (CD-ROM), 10 Pages, 2002/10

A small scale around 300 MWe reduced-moderation water reactor (RMWR) concept has been developed. For the core, a BWR type core concept with the tight-lattice fuel rod arrangement and the high void fraction is adopted to attain a high conversion ratio over 1.0. The negative void reactivity coefficients are also required, and the very flat short core concept is adopted to make the natural circulation cooling (NC) possible. The core burn-up of 60 GWd/t and the operation cycle of 24 months are also attained. For the system, simplification of the system with the passive safety features is a basic approach to overcome the scale demerit as well as the NC. For example, the HPCF system is replaced with the passive accumulator system resulting in the expensive emergency DGs reduction. The cost evaluation for concerned NSSS components gives about 20% reduction. Since MOX fuels in the RMWR contains Pu around 30 wt% and is irradiated to a high burn-up, the fuel safety evaluation has been performed and the acceptable results have been obtained from the thermal feasibility point of view.

Journal Articles

Critical heat flux experiment for Reduced-Moderation Water Reactor (RMWR)

Kureta, Masatoshi; Akimoto, Hajime; Yamamoto, Kazuhiko*; Okada, Hiroyuki*

Proceedings of International Congress on Advanced Nuclear Power Plants (ICAPP) (CD-ROM), 7 Pages, 2002/00

no abstracts in English

Journal Articles

Core and system design of Reduced-Moderation Water Reactor with passive safety features

Iwamura, Takamichi; Okubo, Tsutomu; Yonomoto, Taisuke; Takeda, Renzo*; Moriya, Kumiaki*; Kanno, Minoru*

Proceedings of International Congress on Advanced Nuclear Power Plants (ICAPP) (CD-ROM), 8 Pages, 2002/00

Research and developments of reduced-moderation water reactor (RMWR) have been performed. The RMWR can attain the favorable characteristics such as high burn-up, long operation cycle, multiple recycling of plutonium and effective utilization of uranium resources, based on the matured LWR technologies. MOX fuel assemblies in the tight-lattice fuel rod arrangement are used to reduce the moderation of neutron, and hence, to increase the conversion ratio. The conceptual design has been accomplished for the small 330MWe RMWR core with the discharge burn-up of 60GWd/t and the operation cycle of 24 months, under the natural circulation cooling of the core. A breeding ratio of 1.01 and the negative void reactivity coefficient are simultaneously realized in the design. In the plant system design, the passive safety features are intended to be utilized mainly to improve the economy. At present, a hybrid one under the combination of the passive and the active components, and a fully passive one are proposed. The former has been evaluated to reduce the cost for the reactor components.

Journal Articles

Conceptual designing of reduced-moderation water reactor (RMWR)

Okubo, Tsutomu; Iwamura, Takamichi; Akimoto, Hajime; Araya, Fumimasa; Onuki, Akira; Yamamoto, Kazuhiko*

Dai-7-Kai Doryoku Enerugi Gijutsu Shimpojiumu Koen Rombunshu (00-11), p.250 - 253, 2000/11

no abstracts in English

JAEA Reports

Study on reduced-moderation water reactor (RMWR) core design; Joint research report, FY1998-1999 (Joint research)

Research Group for Advanced Reactor System; Research Group for Reactor Physics; Research Group for Thermal and Fluid Engineering

JAERI-Research 2000-035, 316 Pages, 2000/09

JAERI-Research-2000-035.pdf:19.81MB

no abstracts in English

Journal Articles

Research and Development of future type LWR in Japan Atomic Energy Research Institute

Iwamura, Takamichi

Genshiryoku eye, 46(1), p.19 - 23, 2000/00

no abstracts in English

JAEA Reports

Safety analyses of a high conversion LWR with BWR type tight lattice core

Okubo, Tsutomu; Tomiai, Ichio*; Osugi, Toshitaka

JAERI-M 93-015, 72 Pages, 1993/02

JAERI-M-93-015.pdf:1.64MB

no abstracts in English

17 (Records 1-17 displayed on this page)
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