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Journal Articles

Development of numerical simulation method for small particles behavior in two-phase flow by combining interface and Lagrangian particle tracking methods

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

Proceedings of 11th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-11) (Internet), 6 Pages, 2018/11

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

Excitation energy dependence of fragment-mass distributions from fission of $$^{180,190}$$Hg formed in fusion reactions of $$^{36}$$Ar + $$^{144,154}$$Sm

Nishio, Katsuhisa; Andreyev, A. N.*; Chapman, R.*; Derkx, X.*; D$"u$llmann, C. E.*; Ghys, L.*; He${ss}$berger, F. P.*; Hirose, Kentaro; Ikezoe, Hiroshi*; Khuyagbaatar, J.*; et al.

Physics Letters B, 748, p.89 - 94, 2015/09

 Times Cited Count:17 Percentile:18.12(Astronomy & Astrophysics)

Journal Articles

Numerical prediction on heat transfer-characteristics of supercritical pressure water in a heated pipe based on three dimensional two-fluid model

Ose, Yasuo*; Yoshimori, Hajime*; Misawa, Takeharu; Yoshida, Hiroyuki; Takase, Kazuyuki

Nippon Kikai Gakkai Dai-26-Kai Keisan Rikigaku Koenkai Rombunshu (CD-ROM), p.701_1 - 701_2, 2013/11

no abstracts in English

Journal Articles

A Large-scale three-dimensional simulation on thermal-hydraulics in a fuel bundle for SCWR

Misawa, Takeharu; Takase, Kazuyuki; Yoshida, Hiroyuki; Ose, Yasuo*; Oka, Yoshiaki*

Proceedings of Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo (SNA & MC 2013) (CD-ROM), 2 Pages, 2013/10

Journal Articles

In-beam fissio study at JAEA for heavy element synthesis

Nishio, Katsuhisa; Ikezoe, Hiroshi; Hofmann, S.*; Ackermann, D.*; Aritomo, Yoshihiro*; Comas, V. F.*; D$"u$llmann, Ch. E.*; Heinz, S.*; Heredia, J. A.*; He${ss}$berger, F. P.*; et al.

AIP Conference Proceedings 1524, p.68 - 72, 2013/04

 Times Cited Count:0 Percentile:100

Journal Articles

Evidence for hindrance in fusion between sulfur and lead nuclei

Khuyagbaatar, J.*; Nishio, Katsuhisa; Hofmann, S.*; Ackermann, D.*; Block, M.*; Heinz, S.*; He${ss}$berger, F. P.*; Hirose, Kentaro; Ikezoe, Hiroshi; Kindler, B.*; et al.

Physical Review C, 86(6), p.064602_1 - 064602_6, 2012/12

 Times Cited Count:15 Percentile:31.1(Physics, Nuclear)

Journal Articles

Fusion probabilities in the reactions $$^{40,48}$$Ca + $$^{238}$$U at energies around the Coulomb barrier

Nishio, Katsuhisa; Mitsuoka, Shinichi; Nishinaka, Ichiro; Makii, Hiroyuki; Wakabayashi, Yasuo*; Ikezoe, Hiroshi; Hirose, Kentaro*; Otsuki, Tsutomu*; Aritomo, Yoshihiro*; Hofmann, S.*

Physical Review C, 86(3), p.034608_1 - 034608_6, 2012/09

 Times Cited Count:56 Percentile:5.33(Physics, Nuclear)

Journal Articles

Investigation of fission properties and evaporation residue measurement in the reactions using $$^{238}$$U target nucleus

Nishio, Katsuhisa; Ikezoe, Hiroshi; Hofmann, S.*; Ackermann, D.*; Antalic, S.*; Aritomo, Yoshihiro; Comas, V. F.*; D$"u$llmann, Ch. E.*; Gorshkov, A.*; Graeger, R.*; et al.

EPJ Web of Conferences, 17, p.09005_1 - 09005_4, 2011/10

 Times Cited Count:1 Percentile:50.35

Journal Articles

Nematic-to-smectic transition of magnetic texture in conical state

Takeda, Masayasu; Endo, Yasuo; Kakurai, Kazuhisa; Onose, Yoshinori*; Suzuki, Junichi; Tokura, Yoshinori*

Journal of the Physical Society of Japan, 78(9), p.093704_1 - 093704_4, 2009/09

 Times Cited Count:14 Percentile:33.98(Physics, Multidisciplinary)

The complex phase transition of the magnetic long-range order in Fe$$_{0.7}$$Co$$_{0.3}$$Si has been investigated by small-angle neutron scattering (SANS) measurement at low temperatures under an external magnetic field. A variety of scattering patterns, such as ring, crescent-shaped, and diffusive spots, were observed by changing temperature and applying a magnetic field. The results could be interpreted by an analogy of the phase transition of the liquid crystal when the net magnetization is regarded as the director of the liquid crystal.

Journal Articles

Numerical investigation of cross flow phenomena in a tight-lattice rod bundle using advanced interface tracking method

Zhang, W.; Yoshida, Hiroyuki; Ose, Yasuo*; Onuki, Akira; Akimoto, Hajime; Hotta, Akitoshi*; Fujimura, Ken*

Journal of Power and Energy Systems (Internet), 2(2), p.456 - 466, 2008/00

Journal Articles

Large-scale simulations on thermal-hydraulics in fuel bundles of advanced nuclear reactors

Takase, Kazuyuki; Yoshida, Hiroyuki; Ose, Yasuo*; Kano, Takuma; Merzari, E.*; Ninokata, Hisashi*

Annual Report of the Earth Simulator Center April 2006 - March 2007, p.223 - 228, 2007/09

no abstracts in English

Journal Articles

Statistical evaluation of cross flow in a tight-lattice rod bundle

Zhang, W.; Yoshida, Hiroyuki; Ose, Yasuo*; Onuki, Akira; Akimoto, Hajime

Nippon Kikai Gakkai 2007-Nendo Nenji Taikai Koen Rombunshu, Vol.3, p.145 - 146, 2007/09

In relation to the thermal-hydraulic design of FLWR, this study presents a statistical evaluation of numerical simulation results obtained by a detailed two-phase flow simulation code (named TPFIT). In order to clarify mechanisms of cross flow in such tight lattice rod bundles, the TPFIT was used to simulate water-steam two-phase flow in two modeled subchannels. Attention was focused on instantaneous fluctuation characteristics of cross flow. With the calculation of correlation coefficients between the differential pressure and gas/liquid mixing coefficients, the time scales of cross flow were evaluated, and the effects of mixing section length, flow pattern and gap spacing on correlation coefficients were investigated. The difference in mechanism between gas and liquid cross flows was pointed out.

Journal Articles

Study on cross flow phenomena in a tight-lattice rod bundle by statistical method

Zhang, W.; Yoshida, Hiroyuki; Ose, Yasuo*; Onuki, Akira; Akimoto, Hajime; Hotta, Akitoshi*; Fujimura, Ken*

Dai-12-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu, p.85 - 88, 2007/06

As a candidate for next generation reactor, the innovative FLexible-fuel-cycle Water Reactor (FLWR) adopts a remarkably tight triangular lattice arrangement with about 1 mm gap spacing between adjacent fuel rods. In relation to its design, this study presents a statistical evaluation of numerical simulation results of a detailed two-phase flow simulation code (named TPFIT). In order to make clear mechanisms of cross flow in such tight lattice rod bundles, the TPFIT is used to simulate cross flow between two modeled subchannels. Attention was focused on instantaneous fluctuation characteristics of differential pressure between two subchannels and gas/liquid mixing coefficients. With the calculation of correlation coefficients between the differential pressure and gas/liquid mixing coefficients, the time scales of cross flow, e.g. lag times were evaluated, and the effects of mixing section length, flow pattern and gap spacing on correlation coefficients were extensively investigated. The difference in mechanism between gas and liquid cross flows was pointed out.

Journal Articles

Numerical investigation of cross flow phenomena in a tight-lattice rod bundle using advanced interface tracking method

Zhang, W.; Yoshida, Hiroyuki; Ose, Yasuo*; Onuki, Akira; Akimoto, Hajime; Hotta, Akitoshi*; Fujimura, Ken*

Proceedings of 15th International Conference on Nuclear Engineering (ICONE-15) (CD-ROM), 8 Pages, 2007/04

The innovative Water Reactor for FLexible fuel cycle (FLWR) adopts a tight triangular lattice arrangement with about 1 mm gap between adjacent fuel rods. In view of the importance of accurate prediction of cross flow between subchannels in the evaluation of the boiling transition (BT) in the FLWR core, this study numerically simulated steam-water two-phase cross flow between two modeled subchannels of tight-lattice rod bundle for the FLWR by using a detailed two-phase flow simulation code with an advanced interface tracking method (named TPFIT), statistically evaluated the simulation results, and clarified mechanisms of cross flow for developing a model. The effects of flow pattern, inlet and outlet of mixing section, and gap spacing on cross flow, and the local and general characters of cross flow were extensively investigated.

Journal Articles

A Large-scale simulation on water-vapor bubbly flow dynamics in fuel bundles of advanced nuclear reactors

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

Annual Report of the Earth Simulator Center April 2005 - March 2006, p.261 - 265, 2007/01

no abstracts in English

Journal Articles

Direct numerical simulation on turbulent channel flow under a uniform magnetic field for large-scale structures at high Reynolds number

Satake, Shinichi*; Kunugi, Tomoaki*; Takase, Kazuyuki; Ose, Yasuo*

Physics of Fluids, 18(12), p.125106_1 - 125106_8, 2006/12

 Times Cited Count:29 Percentile:26.78(Mechanics)

no abstracts in English

Journal Articles

A Large-scale simulation on two-phase flow characteristics around duel rods in a tight-lattice core

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

Proceedings of 2006 ASME International Mechanical Engineering Congress & Exposition (IMECE 2006) (CD-ROM), 8 Pages, 2006/11

Water-vapor two-phase flow structure in a fuel bundle of an advanced light water reactor was analyzed numerically by large-scale direct simulations. A newly developed two-phase flow analysis code was used. It can precisely predict the interface behavior between the liquid and gas phase by using the interface tracking method. The present analytical geometry simulates a tight-lattice fuel bundle with 37 fuel rods and four spacers. The fuel rod outer diameter is 13 mm and gap spacing between each rod is 1.3 mm. Each spacer is installed in an arbitrary axial position in order to keeping the gap width. Water flows upward from the bottom of the fuel bundle. The inlet conditions of water are as follows: temperature 283$$^{circ}$$C, pressure 7.2 MPa, flow rate 400 kg/m$$^{2}$$s, and the Reynolds number 40,000. In the present study three-dimensional computations were carried out under the non-heated isothermal flow condition in order to remove the effect of heat transfer by the fuel rods. The average mesh size in the present numerical study was 0.15 mm. From results of a series of the numerical simulations, the following consideration was derived: (1) The fuel rod surface is encircled with thin water film; (2) The bridge phenomenon by the water film appears in the region where the spacing between fuel rods is narrow; (3) Vapor flows downward the triangular region where the spacing between fuel rods is large; and, (4) A flow configuration of vapor shows the streak structure in the vertical direction.

Journal Articles

Direct numerical simulation of gas entrainment from free-surface

Kunugi, Tomoaki*; Kawara, Zensaku*; Ose, Yasuo*; Ito, Kei; Sakai, Takaaki

Proceedings of 5th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-5), p.385 - 390, 2006/11

In order to design the compact FBR with higher coolant velocity compared to the conventional reactor designs, it is necessary to clarify a criterion of a cover gas entrainment (GE) from the free-surface of the coolant pool in the reactor vessel to the heat exchanger through the hot leg. Three flow regimes are considered as the GE phenomena: a vortex dimple, a waterfall and a surface disturbance. In this study, to evaluate the GE vortex phenomena: especially for the vortex dimple, the DNS based on the MARS (Multi-interfaces Advection and Reconstruction Solver (Kunugi, 2001)) were performed for simulating the unsteady vortex-shedding experiment accompanied with the GE phenomena (Okamoto et al., 2004). The applicability of the present DNS to predict the onset of the GE vortex phenomena is discussed.

Journal Articles

Numerical analysis of complicated two-phase flow behavior in nuclear reactor cores

Takase, Kazuyuki; Yoshida, Hiroyuki; Tamai, Hidesada; Ose, Yasuo*; Aoki, Takayuki*; Xu, Z.*

Nippon Kikai Gakkai 2006-Nendo Nenji Taikai Koen Rombunshu, Vol.2, p.39 - 40, 2006/09

Three-dimensional large-scale numerical simulations were carried out to predict the complicated water-vapor two-phase flow characteristics in a fuel bundle of an advanced light water reactor. Conventional analysis methods with a two-fluid model need composition equations and empirical correlations based on the experimental data. Therefore, it is difficult to obtain high prediction accuracy when experimental data are nothing. Then, a new two-phase flow analysis method was proposed and the TPFIT code was developed. This paper describes the predicted liquid film, bubbly and droplet flow behavior in the simulated fuel channels with the TPFIT code, and the predicted two-phase flow behavior around a curved fuel rod with the FLUENT code which is one of the most famous commercial code. From the present results, the high prospect was acquired on the possibility of development of the thermal design procedure of the advanced nuclear reactors by large-scale simulations.

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