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Kureta, Masatoshi; Kumada, Hiroaki; Kume, Etsuo; Someya, Satoshi*; Okamoto, Koji*
Proceedings of 3rd International Workshop on Process Tomography (IWPT-3) (CD-ROM), 8 Pages, 2009/04
Dynamic neutron tomography velocimetry has been developed in order to obtain the 3-D velocity distribution and flow profile data of liquid metal flow in a heated rod bundle for development of an advanced nuclear reactor. In this paper, data processing methods for the 3-D velocimetry is focused on. The data processing is started from the reading images recorded by the three high-speed video cameras, and is finished to the visualization of velocity of the tracers and the profiles. Basic experiments were carried out using the research reactor JRR-4 and the dynamic neutron tomography system. As the results, it was confirmed that the 3-D velocity distribution and flow profile could be visualized by the new data processing methods.
Kureta, Masatoshi; Kumada, Hiroaki*; Kume, Etsuo; Someya, Satoshi*; Okamoto, Koji*
Journal of Physics; Conference Series, 147, p.012087_1 - 012087_14, 2009/03
The aim of this development is to visualize and measure the velocity distribution in liquid metal flow using the neutron beam with the high-speed imaging technique, computer tomography (CT) technique and particle tracking velocimetry (PTV). Final research purpose is to obtain the velocity distribution and flow profile data of liquid metal flow in a heated rod bundle for development of the FBR core. In this paper, visualization and measurement method using the JRR-4, spring model PTV method for this technique and results of the fundamental PTV experiment were reported. The fundamental experiment was conducted. As the result, cadmium tracers buried in the aluminum column with the speed of 1.5 revolving per second could be visualized as the 3D movie under 125Hz and 250Hz sampling conditions, the profile of the tracer could be traced, and fundamental velocity distribution measurement method could be conformed.
Kureta, Masatoshi; Kumada, Hiroaki; Kume, Etsuo; Someya, Satoshi*; Okamoto, Koji*
Proceedings of 6th International Symposium on Measurement Techniques for Multiphase Flows (ISMTMF 2008) (USB Flash Drive), 14 Pages, 2008/12
The aim of this development is to visualize and measure the velocity distribution in liquid metal flow using the neutron beam with the high-speed imaging technique, computer tomography (CT) technique and particle tracking velocimetry (PTV). Final research purpose is to obtain the velocity distribution and flow profile data of liquid metal flow in a heated rod bundle for development of the FBR core. In this paper, visualization and measurement method using the JRR-4, spring model PTV method for this technique and results of the fundamental PTV experiment were reported. The fundamental experiment was conducted. As the result, cadmium tracers buried in the aluminum column with the speed of 1.5 revolving per second could be visualized as the 3D movie under 125 Hz and 250 Hz sampling conditions, the profile of the tracer could be traced, and fundamental velocity distribution measurement method could be conformed.
Takase, Kazuyuki; Yoshida, Hiroyuki; Shibata, Mitsuhiko; Kitamura, Tatsuaki*; Kume, Etsuo; Zhe, X.*
Nihon Kikai Gakkai Ryutai Kogaku Bumon Koenkai Koen Rombunshu, P. 227, 2006/10
Fluid flow characteristics in a tight-lattice rod bundle with spacers were analyzed numerically using a newly developed two-phase flow analysis code under the conditions of the full bundle size and non-heated isothermal flow. Conventional analysis methods such as sub-channel codes need composition equations based on the experimental data. In case that there are no experimental data about thermal-hydraulics in the tight-lattice core, therefore, it is difficult to obtain high prediction accuracy on the thermal design of the tight-lattice core. Then the direct numerical simulations with the earth simulator were chosen. The axial velocity and void fraction distributions in a simulated tight-lattice rod bundle changed sharply around a spacer and the interface behavior between water and vapor in a narrow coolant channel was clarified using the predicted quantities. The high prospect was acquired on the possibility of establishment of the thermal design procedure of the advanced nuclear reactors with large-scale direct simulations.
Kume, Etsuo; Kitamura, Tatsuaki*; Takase, Kazuyuki; Ose, Yasuo*
Kashika Joho Gakkai-Shi, 25(Suppl.2), p.369 - 370, 2005/10
no abstracts in English
Hoshi, Yoshiyuki; Kume, Etsuo
JAERI-Data/Code 2005-010, 48 Pages, 2005/09
JAERI-Data-Code-2005-010.pdf:8.7MB
In scientific and engineering calculations, recently, computational sizes and amounts of calculated results have been increased rapidly due to speedup of computers and increase in memory size. Post processing or visualization of a huge amount of numerical data plays a very important role for understanding the meaning of the data. Computational loads for visualization of large-scale data are still heavy even for graphic computers. Processing speeds for visualization of large-scale data are measured using general-purpose visualization software on graphic computers in JAERI. A guideline is summarized in this report to choose appropriate graphic computers according to the size of the data.
Al cable-in-conduit conductorKoizumi, Norikiyo; Matsui, Kunihiro; Kume, Etsuo; Okuno, Kiyoshi
IEEE Transactions on Applied Superconductivity, 15(2), p.1363 - 1366, 2005/06
Times Cited Count：0 Percentile：0(Engineering, Electrical & Electronic)The NbAl Insert was developed by JAERI aiming at the demonstration of a NbAl conductor to fusion reactor magnets. A quench test was performed on the NbAl Insert at 13 T with various temperature margins, which are defined as a difference between current sharing temperature and operating temperature. The initial normalcy was initiated by using an inductive heater and a coil current was kept for several seconds. The normal zone propagation velocity was accelerated after 3 s from the onset of heating in case that the temperature margin was set at 0.5 K. A simulation using one-dimensional stability and quench simulation code was performed. The calculation results indicate that such rapid propagation occurred due to a temperature rise beyond a current sharing temperature because of a large pressure increase even at the location where the normal front did not reach yet. This large pressure rise was caused since the coolant was contained in the closed circulation circuit of the cooling system, which is usually applied to a large magnet cooling system.
Fujimoto, Hirofumi*; Pinak, M.; Nemoto, Toshiyuki*; O'Neill, P.*; Kume, Etsuo; Saito, Kimiaki; Maekawa, Hideaki*
Journal of Computational Chemistry, 26(8), p.788 - 798, 2005/06
Times Cited Count：23 Percentile：57.53(Chemistry, Multidisciplinary)Clustered DNA damage sites induced by ionizing radiation have been suggested to have serious consequences to organisms. In this study, approaches based on molecular dynamics (MD) simulation have been applied to examine conformational changes and energetic properties of DNA molecules containing clustered damage sites consisting of 2 lesioned sites, 8-oxoG and AP site. After 1 nanosecond of MD simulation, one of the 6 DNA molecules containing a clustered damage site develop specific characteristic features: sharp bending at the lesioned site and weakening or complete loss of electrostatic interaction energy between 8-oxoG and bases locating on the complementary strand. From these results it is suggested that these changes would make it difficult for the repair enzyme to bind to the lesions within the clustered damage site and thereby result in a reduction of its repair capacity.
Kikuchi, Masamitsu; Taki, Mitsumasa; Kume, Etsuo; Kobayashi, Hideo*; Yamada, Toshio*; Yamaguchi, Takenori
JAERI-Data/Code 2004-006, 146 Pages, 2004/03
JAERI-Data-Code-2004-006.pdf:6.87MB
The nuclear facilities, which are required to control the released radioactive gases and liquid, exist in Tokai research establishment as much as 40. These radioactive controls are carried out complying with the statutes in each facility. The released radioactivity data of each facility must be reported to MEXT and Ibaraki Prefecture from Tokai Research Establishment. This system is developed to make the database gathering the radioactivity data of each facilities for unitary control as Tokai Research Establishment and contribute to make the reports to MEXT and Ibaraki Prefecture.
Masuko, Kenji*; Watanabe, Ritsuko; Kume, Etsuo
JAERI-Data/Code 2004-005, 72 Pages, 2004/03
JAERI-Data-Code-2004-005.pdf:10.48MB
no abstracts in English
ray dose rate in nuclear fusion reactorSato, Satoshi; Kawasaki, Nobuo*; Kume, Etsuo; Nishitani, Takeo
Journal of Nuclear Science and Technology, 41(Suppl.4), p.62 - 65, 2004/03
no abstracts in English
Fujimoto, Hirofumi; Pinak, M.; Nemoto, Toshiyuki*; Sakamoto, Kiyotaka*; Yamada, Kazuyuki*; Hoshi, Yoshiyuki*; Kume, Etsuo
Journal of Molecular Structure; THEOCHEM, 681(1-3), p.1 - 8, 2004/01
We developed the novel system, Fujitsu Bio Molecular Visualization System (F-BMVS), that enables to produce real pictures and an animation by arranging them along a time series of a large scale simulation of biomolecules associated with a molecular dynamics (MD) simulation program. This animation system is used to study the results of molecular dynamics code, AMBER, in order to find structural differences on the lesioned DNA comparing with non-damaged DNA. These structural differences would be a factor that guides a repair enzyme to discriminate a lesion from non-damaged DNA region.
Akiyama, Mitsunaga*; Katakura, Fumishige*; Kawasaki, Nobuo*; Nemoto, Toshiyuki*; Tsuruoka, Takuya*; Adachi, Masaaki*; Ishizuki, Shigeru*; Kume, Etsuo
JAERI-Data/Code 2003-009, 307 Pages, 2003/07
JAERI-Data-Code-2003-009.pdf:10.37MB
Several computer codes in the nuclear field have been vectorized, parallelized and transported on the supar computer system at Center for Promotion of Computational Science and Engineering in Japan Atomic Energy Research Institute. We dealt with 10 codes in fiscal 2001. In this report, the parallelization of Newtron Radiography for 3 dimensional CT code NR3DCT, the vectorization of Unsteady-state heat conduction code THERMO3D, the porting of initial program of MHD simulation, the tuning of Heat And Mass Balance Analysis Code HAMBAC, the porting and parallelization of Monte Carlo N-Particle transport code MCNP4C3, the porting and parallelization of Monte Carlo N-Particle Transport code system MCNPX2.1.5, the porting of code CINAC-V4, the porting of Assisted Model Building with Energy Refinement Amber5 code system, the part of additional VisLink library Multidimensional Two-fluid model code ACD3D and the porting of experiment data processing code for GS8500 to SR8000 are described.
Takase, Kazuyuki; Masuko, Kenji*; Ose, Yasuo*; Tamai, Hidesada; Kume, Etsuo
Kashika Joho Gakkai-Shi, 23(Suppl.1), p.363 - 364, 2003/07
no abstracts in English
Sakurai, Kiyoshi; Kume, Etsuo; Maekawa, Fujio; Nojiri, Ichiro*
Nihon Genshiryoku Gakkai Wabun Rombunshi, 2(2), p.196 - 201, 2003/06
New attempt on the Monte Carlo seminars is as following; authors prepared the practical lecture note and the text book of continuous energy Monte Carlo method. The exact evaluation method of lower weight bound was proposed in the shielding safety analysis seminar and the high energy calculation seminar. For the general Monte Carlo calculation, the neutron cross-section library including 340 nuclides with 293K, that was compiled from JENDL-3.2, was used for all Monte Carlo Calculation seminars. Also for the check of the calculation method, benchmark experiment problem was used for each calculation seminar.
Takase, Kazuyuki; Kitamura, Tatsuaki*; Kume, Etsuo; Ichimiya, Koichi*; Komada, Ichiro*
Nihon Kikai Gakkai Kanto Shibu Yamanashi Koenkai (2003) Koen Rombunshu, No.030-4, p.77 - 78, 2003/00
no abstracts in English
Kume, Tamikazu; Amano, Etsuo*; Nakanishi, Tomoko*; Chino, Mitsuo*
Journal of Nuclear Science and Technology, 39(10), p.1106 - 1113, 2002/10
Times Cited Count：3 Percentile：23.41(Nuclear Science & Technology)no abstracts in English
Kato, Katsumi*; Kume, Etsuo
JAERI-Data/Code 2002-019, 116 Pages, 2002/09
JAERI-Data-Code-2002-019.pdf:26.15MB
no abstracts in English
Takase, Kazuyuki; Ose, Yasuo*; Yoshida, Hiroyuki; Tamai, Hidesada; Kume, Etsuo; Kitamura, Tatsuaki*
Dai-16-Kai Suchi Ryutai Rikigaku Shimpojiumu Koen Yoshishu, 7 Pages, 2002/00
no abstracts in English
-ray transport calculation systemSato, Satoshi; Kawasaki, Nobuo*; Kume, Etsuo
JAERI-Data/Code 2001-017, 99 Pages, 2001/06
JAERI-Data-Code-2001-017.pdf:3.19MB
no abstracts in English
