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Journal Articles

Experimental research on pool scrubbing of particles of radioactive materials

Akiba, Miyuki*; Hotta, Akitoshi*; Abe, Yutaka*; Sun, Haomin

Nippon Genshiryoku Gakkai Wabun Rombunshi, 19(1), p.1 - 15, 2020/02

Tests at three different scales were conducted in order to understand the mechanisms of pool scrubbing. In the small-scale separate effect test, high resolution two-phase flow measurement techniques such as a high-speed camera, wire mesh sensor and PIV were applied to capture the behaviors of a single bubble and two-phase flow structures. In the large-scale integral effect test, the dependence of the aerosol removal efficiency on submergence and pool temperature was measured under constant pressure and depressurized conditions. To clarify relationships between individual phenomena and combined phenomena observed in two tests, the mid-scale integral effect test was undertaken.

Journal Articles

Validation of three-dimensional finite-volume-particle method for simulation of liquid-liquid mixing flow behavior

Kato, Masatsugu*; Funakoshi, Kanji*; Liu, X.*; Matsumoto, Tatsuya*; Liu, W.*; Morita, Koji*; Kamiyama, Kenji

Proceedings of 11th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-11) (Internet), 7 Pages, 2018/11

Journal Articles

Estimation of porosity and void fraction profiles in a packed bed of spheres using X-ray radiography

Ito, Daisuke*; Ito, Kei*; Saito, Yasushi*; Aoyagi, Mitsuhiro; Matsuba, Kenichi; Kamiyama, Kenji

Nuclear Engineering and Design, 334, p.90 - 95, 2018/08

 Times Cited Count:2 Percentile:53.66(Nuclear Science & Technology)

Two-phase flow through porous media must be well understood to develop a severe accident analysis code not only for light water reactor but also sodium-cooled fast reactor. When a core disruptive accident occurs in sodium-cooled fast reactor, the fuel inside the core become melted and interacts with the coolant. As a result, gas-liquid two-phase flow will be formed in the debris bed, which may have porous nature depending on the cooling process. In such condition, the local porosity and its distribution are very important to characterize two-phase flow field in the porous media. In this study, X-ray radiography was applied to measure the local porosity in the packed bed of spheres. The radial profiles were estimated from the chordal profiles measured by the X-ray method and compared with the previous porosity model. In addition, the void fraction radial profiles were also obtained in air-water two-phase flow.

Journal Articles

Development of numerical simulation method for capturing behavior of aerosol particles on gas-liquid interface based on interface tracking method

Yoshida, Hiroyuki; Uesawa, Shinichiro; Horiguchi, Naoki; Miyahara, Naoya; Ose, Yasuo*

Dai-23-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu (USB Flash Drive), 5 Pages, 2018/06

no abstracts in English

Journal Articles

Study on water-vapor two-phase flow behavior in venturi tube

Uesawa, Shinichiro; Horiguchi, Naoki; Shibata, Mitsuhiko; Yoshida, Hiroyuki

Nippon Kikai Gakkai Rombunshu (Internet), 84(859), p.17-00392_1 - 17-00392_10, 2018/03

no abstracts in English

Journal Articles

Study on water-vapor two-phase flow behavior in venturi tube

Uesawa, Shinichiro; Horiguchi, Naoki; Shibata, Mitsuhiko; Yoshida, Hiroyuki

Dai-22-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu (USB Flash Drive), 6 Pages, 2017/06

no abstracts in English

Journal Articles

Predicted three-dimensional bubbly and liquid film flow behavior in narrow fuel channels

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

Proceedings of International Conference on Jets, Wakes and Separated Flows (ICJWSF 2005), p.137 - 144, 2005/11

no abstracts in English

Journal Articles

Research for thermal-hydraulic performance in a tight-lattice fuel assembly, 2; Two-phase flow analysis in a fuel assembly with a large-scale simulation

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

Nippon Konsoryu Gakkai Nenkai Koenkai 2005 Koen Rombunshu, p.231 - 232, 2005/08

no abstracts in English

Journal Articles

Large-scale simulations of two-phase flow dynamics in fuel channels of nuclear reactor cores

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

Dai-24-Kai Nippon Shimyureshon Gakkai Taikai Happyo Rombunshu, p.161 - 164, 2005/07

no abstracts in English

Journal Articles

Numerical visualization on a Large-scale bubbly flow in a vertical small duct

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

Kashika Joho Gakkai-Shi, 25(Suppl.1), p.435 - 436, 2005/07

no abstracts in English

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

Present status of thermal design of nuclear reactors using large-scale simulations

Takase, Kazuyuki

Nippon Kikai Gakkai Ryutai Kogaku Bumon Nyuzu Reta Nagare (Internet), 6 Pages, 2005/04

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

Investigation of water-vapor two-phase flow characteristics in a tight-lattice core by large-scale numerical simulation, 2; Experimental analysis of 2-channel fluid mixing tests

Nagayoshi, Takuji*; Yoshida, Hiroyuki; Onuki, Akira; Akimoto, Hajime

Nippon Genshiryoku Gakkai Wabun Rombunshi, 4(1), p.16 - 24, 2005/03

A detailed gas-liquid two-phase flow analysis code based on an advanced interface-tracking method has been developed. It is expected that the developed code would be able to simulate two-phase cross flow behavior within tight-lattice fuel bundles without relying on any empirical correlations. In order to verify the applicability of the code to simulate two-phase cross flow behavior in such situations, numerical analyses of 2-channel model tests were conducted to compare the air slug deformation and separation behavior caused by cross flow through a narrow interconnection between channels. Although the code underestimated the ascending velocity of the slug, the calculated slug deformation and separation behavior were shown to be quite similar to those observed by a high-speed video camera. Moreover the minimum differential pressure between the subchannels through the interconnection, causing channel-to-channel air transfer to occur could be predicted to within 20Pa. However, further studies of modeling and implementation related to the interface-channel wall interaction, such as a contact angle of a gas-liquid interface at the channel wall, are required for prediction improvements. Nevertheless, the qualitative capability of the developed code to simulate two-phase cross flow phenomena was demonstrated.

Journal Articles

Large-scale simulations on bubbly flow dynamics in a fuel channel with the earth simulator

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

Hai Pafomansu Komputingu To Keisan Kagaku Shimpojium (HPCS 2005) Rombunshu, P. 16, 2005/01

no abstracts in English

Journal Articles

Three-dimensional numerical predictions on two-phase flow behavior in advanced light water reactors

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

Dai-18-Kai Suchi Ryutai Rikigaku Shimpojiumu Koen Yoshishu (CD-ROM), 6 Pages, 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

Predicted thermal-hydraulic characteristics of liquid film flow on a ribbed surface

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

Proceedings of 1st International Forum on Heat Transfer (IFHT 2004), p.207 - 208, 2004/11

no abstracts in English

Journal Articles

A Large-scale numerical simulation on bubbly flow configurations in a vertical small duct

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

Proceedings of 1st International Forum on Heat Transfer (IFHT 2004), p.199 - 200, 2004/11

no abstracts in English

Journal Articles

Development of a best estimate analysis method on two-phase flow thermal-hydraulics for reduced-moderation water reactors

Takase, Kazuyuki; Tamai, Hidesada; Yoshida, Hiroyuki; Akimoto, Hajime

Proceedings of International Meeting on Updates in Best EstimateMethods in Nuclear Installations Safety Analysis (BE-2004) (CD-ROM), p.151 - 152, 2004/11

no abstracts in English

133 (Records 1-20 displayed on this page)