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Kondo, Hiroo; Furukawa, Tomohiro; Hirakawa, Yasushi; Nakamura, Kazuyuki; Ida, Mizuho; Watanabe, Kazuyoshi; Kanemura, Takuji; Wakai, Eiichi; Horiike, Hiroshi*; Yamaoka, Nobuo*; et al.
Nuclear Fusion, 51(12), p.123008_1 - 123008_12, 2011/12
Times Cited Count：39 Percentile：82.4(Physics, Fluids & Plasmas)The Engineering Validation and Engineering Design Activity (EVEDA) for the International Fusion Materials Irradiation Facility (IFMIF) is proceeded as one of the ITER Broader Approach (BA) activities. The EVEDA Li test loop (ELTL) is aimed at validating stability of the Li target and feasibility of a Li purification system as the key issues. In this paper, the design of the ELTL especially of a target assembly in which the Li target is produced by the contraction nozzle is presented.
Nakamura, Kazuyuki; Furukawa, Tomohiro; Hirakawa, Yasushi; Kanemura, Takuji; Kondo, Hiroo; Ida, Mizuho; Niitsuma, Shigeto; Otaka, Masahiko; Watanabe, Kazuyoshi; Horiike, Hiroshi*; et al.
Fusion Engineering and Design, 86(9-11), p.2491 - 2494, 2011/10
Times Cited Count：10 Percentile：60.88(Nuclear Science & Technology)In IFMIF/EVEDA, tasks for lithium target system are shared to 5 validation tasks (LF1-5) and a design task (LF6). The purpose of LF1 task is to construct and operate the EVEDA lithium test loop, and JAEA has a main responsibility to the performance of the Li test loop. LF2 is a task for the diagnostics of the Li test loop and IFMIF design. Basic research for the diagnostics equipment has been completed, and the construction for the Li test loop will be finished before March in 2011. LF4 is a task for the purification systems with nitrogen and hydrogen. Basic research for the purification equipment has been completed, and the construction of the nitrogen system for the Li test loop will be finished before March in 2011. LF5 is a task for the remote handling system with the target assembly. JAEA has an idea to use the laser beam for cutting and welding of the lip part of the flanges. LF6 is a task for the design of the IFMIF based on the validation experiments of LF1-5.
Kanemura, Takuji; Sugiura, Hirokazu*; Yamaoka, Nobuo*; Suzuki, Sachiko*; Kondo, Hiroo; Ida, Mizuho; Matsushita, Izuru*; Horiike, Hiroshi*
Fusion Engineering and Design, 86(9-11), p.2462 - 2465, 2011/10
Times Cited Count：5 Percentile：38.65(Nuclear Science & Technology)Wave period of free-surface waves on a high-speed liquid lithium (Li) jet is very important wave characteristics to investigate for validation of a Li target of the International Fusion Materials Irradiation Facility (IFMIF). In this paper, we report characteristics of wave period measured by a contact-type liquid level sensor. The experiments were conducted at a Li loop in Osaka University. In this loop, a plane Li jet simulating the IFMIF Li target can be controlled at the velocities of up to 15 m/s. Probability density distribution of the measured wave periods was nearly equal to the log-normal distribution. The fact that the wave period distribution is nearly equal to the log-normal distribution has been already identified in the ocean waves which are known for its random property. From present and previous our experimental results, it was concluded that random wave property developed for the ocean waves can apply to the free-surface waves on the Li jet.
Ida, Mizuho; Fukada, Satoshi*; Furukawa, Tomohiro; Hirakawa, Yasushi; Horiike, Hiroshi*; Kanemura, Takuji*; Kondo, Hiroo; Miyashita, Makoto; Nakamura, Hiroo; Sugiura, Hirokazu*; et al.
Journal of Nuclear Materials, 417(1-3), p.1294 - 1298, 2011/10
Times Cited Count：4 Percentile：26.02(Materials Science, Multidisciplinary)Engineering Validation and Engineering Design Activities (EVEDA) of the International Fusion Materials Irradiation Facility (IFMIF) was started. As a Japanese activity for the target system, EVEDA Lithium Test Loop simulating hydraulic and impurity conditions of IFMIF is under design and preparation for fabrication. Feasibility of thermo-mechanical structure of the target assembly and the replaceable back-plate made of F82H (a RAFM) and 316L (a stainless steel) is a key issue. Toward final validation on the EVEDA loop, diagnostics applicable to a high-speed free-surface Li flow and hot traps to control nitrogen and hydrogen in Li are under tests. For remote handling of target assemblies and the replaceable back-plates activated up to 50 dpa/y, lip weld on 316L-316L by laser and dissimilar weld on F82H-316L are under investigation. As engineering design of the IFMIF target system, water experiments and hydraulic/thermo-mechanical analyses of the back-plate are going.
Kanemura, Takuji; Kondo, Hiroo; Sugiura, Hirokazu*; Horiike, Hiroshi*; Yamaoka, Nobuo*; Furukawa, Tomohiro; Ida, Mizuho; Matsushita, Izuru*; Nakamura, Kazuyuki
Proceedings of 19th International Conference on Nuclear Engineering (ICONE-19) (CD-ROM), 7 Pages, 2011/10
Regarding R&Ds on the International Fusion Materials Irradiation Facility (IFMIF), validation of hydraulic stability of a liquid Li jet simulating the IFMIF Li target is of crucial importance and thus, is planned to be performed using EVEDA Li test loop. This paper presents diagnostics of the Li jet to be implemented in validation tests of the jet stability. In the tests, the following physical parameters need to be measured; thickness of the jet; height, length and frequency of free-surface waves; and Li evaporation rate. A high-speed video (HSV) camera is planned to be used for understanding of detailed structure of free-surface waves, and the HSV images are to be analyzed to obtain wave velocity and frequency. To measure jet thickness and wave height, a contact-type liquid level sensor is to be used. With regard to Li evaporation rate, deposition of Li on the specimens installed near the free surface is to be measured. In addition, frequency change of a crystal quartz will be utilized.
Hoashi, Eiji*; Sugiura, Hirokazu*; Suzuki, Sachiko*; Kanemura, Takuji; Kondo, Hiroo; Yamaoka, Nobuo*; Horiike, Hiroshi*
Proceedings of 19th International Conference on Nuclear Engineering (ICONE-19) (CD-ROM), 9 Pages, 2011/10
Free surface flow of a liquid metal Lithium (Li) is planned as a target irradiated by two deuteron beams to generate intense neutrons and it is thus important to obtain knowledge of the surface wave characteristic for the safety and the efficiency of system in the IFMIF. This paper reports the results of the wave height and the surface velocity examined experimentally using a Li loop at Osaka University and numerically using computational fluid dynamics (CFD) code, FLUENT. In the experiment, an electro-contact probe apparatus was used to obtain the wave height, and a high speed video was used to measure the surface velocity. A CFD simulation was also conducted to obtain information on the relation of the free surface with the inner flow. In the simulation, the model included from a two-staged contraction nozzle to a flow channel with a free surface flow region and simulation results were compared with the experimental data. We resulted in knowledge of the surface wave growth mechanism.
Kondo, Hiroo; Kanemura, Takuji*; Sugiura, Hirokazu*; Yamaoka, Nobuo*; Ida, Mizuho; Nakamura, Hiroo; Matsushita, Izuru*; Muroga, Takeo*; Horiike, Hiroshi*
Fusion Engineering and Design, 85(7-9), p.1102 - 1105, 2010/12
Times Cited Count：12 Percentile：62.3(Nuclear Science & Technology)This paper reports a measurement technique for surface waves on a liquid lithium jet for a Li target of the International Fusion Materials Irradiation Facility. The characteristic of the waves was successfully clarified by a contact-type liquid level detector. As a result, it was found that the wave distributions in the all jet velocity range up to 15 m/s were conformed each other in normalized form and Rayleigh distribution which is one of popular model to show irregular water wave.
Kondo, Hiroo; Furukawa, Tomohiro; Hirakawa, Yasushi; Ida, Mizuho; Matsushita, Izuru*; Horiike, Hiroshi*; Kanemura, Takuji; Sugiura, Hirokazu*; Yagi, Juro*; Suzuki, Akihiro*; et al.
Journal of Engineering for Gas Turbines and Power, 133(5), p.052910_1 - 052910_6, 2010/12
Times Cited Count：7 Percentile：38.81(Engineering, Mechanical)As a major Japanese activity for the IFMIF/EVEDA, EVEDA Li Test Loop (ELTL) to simulate hydraulic and impurity conditions of IFMIF is under design and preparation for fabrication. Feasibility of hydraulic stability of the liquid Li target and the purification systems of hot traps are major key issues to be validated. This paper presents the current status of the design and construction of the EVEDA Li Test Loop. Detail designs of the loop components such as the target assembly, tanks, an electro-magnetic pump and flow meter and a cold trap for purification system are described in addition to the flow diagnostics system and the hot traps.
Kondo, Hiroo; Furukawa, Tomohiro; Hirakawa, Yasushi; Nakamura, Hiroo*; Ida, Mizuho; Watanabe, Kazuyoshi; Miyashita, Makoto*; Horiike, Hiroshi*; Yamaoka, Nobuo*; Kanemura, Takuji; et al.
Proceedings of 23rd IAEA Fusion Energy Conference (FEC 2010) (CD-ROM), 8 Pages, 2010/10
The Engineering Validation and Engineering Design Activity (EVEDA) for the International Fusion Materials Irradiation Facility (IFMIF) is proceeded as one of the ITER Broader Approach (BA) activities. The EVEDA Li test loop (ELTL) is aimed at validating stability of the Li target and feasibility of a Li purification system as the key issues. In this paper, the design of the ELTL especially of a target assembly in which the Li target is produced by the contraction nozzle is presented.
Kondo, Hiroo; Furukawa, Tomohiro; Hirakawa, Yasushi; Matsushita, Izuru*; Ida, Mizuho; Horiike, Hiroshi*; Kanemura, Takuji; Sugiura, Hirokazu*; Yagi, Juro*; Suzuki, Akihiro*; et al.
Proceedings of 18th International Conference on Nuclear Engineering (ICONE-18) (CD-ROM), 9 Pages, 2010/05
IFMIF is a neutron source aimed at producing an intense high energy neutron flux for testing candidate fusion reactor materials. Under Broader Approach activities, Engineering Validation and Engineering Design Activities (EVEDA) of IFMIF started on July 2007. Regarding to the lithium (Li) target facility, design and construction of EVEDA Li Test Loop is a major activity and is in progress. The detail design was started at the early 2009. Fabrication of the loop was started at middle of 2009, and completion is planned at the end of Feb. 2011.
Kondo, Hiroo*; Kanemura, Takuji*; Sugiura, Hirokazu*; Yamaoka, Nobuo*; Miyamoto, Seiji*; Ida, Mizuho; Nakamura, Hiroo; Matsushita, Izuru*; Muroga, Takeo*; Horiike, Hiroshi*
Fusion Engineering and Design, 84(7-11), p.1086 - 1090, 2009/06
Times Cited Count：9 Percentile：53.3(Nuclear Science & Technology)A liquid lithium(Li) target of International Fusion Materials Irradiation Facility (IFMIF) is formed as flat plane free-surface flow by a nozzle and flows at high speed around 15 m/s. This paper focuses on flatness of the liquid Li target. A Li flow experiment was conducted in Osaka University Li Loop with a test section which was 1/2.5 scaled model of IFMIF. A thickness of the Li flow was measured and obtained by a contact method which was developed for the measurement. Analytical study on Kelvin wake and numerical calculation on wakes near side walls of the flow channel were also conducted and compared with the experimental results. As the results, positions of wake crest obtained from both of the experiment and numerical calculation assuming contact angle 140
agreed well with an iso-phase line of the analytical model. Generation of the wake are likely depends on wettability between Li and a structural material which is 304SS in the present study.
Sugiura, Hirokazu*; Kondo, Hiroo*; Kanemura, Takuji*; Niwa, Yuta*; Yamaoka, Nobuo*; Miyamoto, Seiji*; Ida, Mizuho; Nakamura, Hiroo; Matsushita, Izuru*; Muroga, Takeo*; et al.
Fusion Engineering and Design, 84(7-11), p.1803 - 1807, 2009/06
Times Cited Count：3 Percentile：24.52(Nuclear Science & Technology)To develop a diagnostics system in view of its application on International Fusion Materials Irradiation Facility (IFMIF) liquid lithium (Li) target, velocity measurements on a liquid Li flow were performed in a Li circulation loop at Osaka University with a test section having a contraction nozzle 1/2.5 scale of IFMIF and producing a flat plane jet of 70 mm width and 10 mm thickness. Based on the Particle Image Velocimetry (PIV) technique, a local Li flow velocity distribution was measured by tracking brightness intensity patterns of surface waves generated on the flow. Measured surface velocity showed good agreement with a surface velocity obtained in previous water experiments, and had an insignificant effect at an area corresponding to a deuteron beam irradiation area on the IFMIF target.
Sugiura, Hirokazu*; Kondo, Hiroo*; Kanemura, Takuji*; Niwa, Yuta*; Yamaoka, Nobuo*; Miyamoto, Seiji*; Horiike, Hiroshi*; Ida, Mizuho; Nakamura, Hiroo; Matsushita, Izuru*; et al.
no journal, ,
no abstracts in English
Sugiura, Hirokazu*; Kondo, Hiroo*; Kanemura, Takuji*; Yamaoka, Nobuo*; Miyamoto, Seiji*; Ida, Mizuho; Nakamura, Hiroo; Matsushita, Izuru*; Muroga, Takeo*; Horiike, Hiroshi*
no journal, ,
no abstracts in English
Kondo, Hiroo; Kanemura, Takuji*; Sugiura, Hirokazu*; Yamaoka, Nobuo*; Nakamura, Hiroo; Ida, Mizuho; Matsushita, Izuru*; Muroga, Takeo*; Horiike, Hiroshi*
no journal, ,
Design of International Fusion Materials Irradiation Facility (IFMIF) is in progress in a framework of ITER Broader Approach. IFMIF produces a neutron field by a deuteron (D) - lithium (Li) nuclear reaction and tests materials to be used in a DEMO fusion reactor. The Li target for the D beam is formed into film flow by a nozzle, and flows at the maximum speed of 20 m/s. Since the Li target has free-surface to be faced to the D beam, hydraulic stability of the free-surface flow is one of the research issues. The present study conducted experiments on liquid Li free-surface flow in a Li circulation loop for the study on the hydraulic stability, and for studies on issues necessary for engineering design of the IFMIF Li circulation loop system.
Kondo, Hiroo; Furukawa, Tomohiro; Hirakawa, Yasushi; Iuchi, Hiroshi; Nakamura, Kazuyuki; Ida, Mizuho; Wakai, Eiichi; Watanabe, Kazuyoshi; Kanemura, Takuji; Horiike, Hiroshi*; et al.
no journal, ,
The International Fusion Materials Irradiation Facility (IFMIF) is a neutron source aimed at producing an intense high energy neutron flux for testing candidate materials to be used in the fusion demonstration reactor. Engineering Validation and Engineering Design Activities (EVEDA) on IFMIF started under Broader Approach. As a major Japanese activity for Li target tasks of EVEDA, EVEDA Li Test Loop is under construction. Feasibility of hydraulic stability of the Li target and purification systems of hot traps is major key issues to be validated. Toward the validation at the loop, laboratory-scale tests and design for diagnostics to the high-speed free-surface Li target and the hot traps to control nitrogen and hydrogen in Li are carried out along with the construction of the loop. Regarding to progress of the construction, all major components except a target assembly are installed in a mount of the loop. The construction is scheduled to be finished on Feb. 2011.
Kanemura, Takuji; Kondo, Hiroo; Sugiura, Hirokazu*; Horiike, Hiroshi*; Yamaoka, Nobuo*; Suzuki, Sachiko*; Furukawa, Tomohiro; Ida, Mizuho; Matsushita, Izuru*; Nakamura, Kazuyuki
no journal, ,
In the current design of International Fusion Materials Irradiation Facility (IFMIF), thickness variation of a liquid lithium target is required to be less than 1 mm. Therefore, validation of stability of the target is absolutely necessary for the final design of IFMIF. In Engineering Validation and Engineering Design Activities (EVEDA) of IFMIF, validation tests on stability of a lithium jet simulating the IFMIF target is planned to be conducted in EVEDA lithium test loop. Measurement objects of the tests are amplitude, frequency and velocity of surface waves, average thickness of the jet, and evaporation rate of lithium. Wave amplitude and average thickness will be measured by a contact-type liquid level sensor. Wave frequency and velocity will be obtained by analyzing sequential images recorded by a high-speed video camera. Evaporation rate of lithium will be obtained from frequency change of a crystal oscillator and weight change of a metal plate set near the jet surface.
Furukawa, Tomohiro; Kondo, Hiroo; Hirakawa, Yasushi; Kanemura, Takuji; Nakamura, Kazuyuki; Wakai, Eiichi; Sugiura, Hirokazu*; Yamaoka, Nobuo*; Suzuki, Sachiko*; Hoashi, Eiji*; et al.
no journal, ,
This paper describes the metallurgical analysis of lithium test assembly used for lithium flow experiment at Osaka University.
Okita, Takafumi*; Suzuki, Sachiko*; Hoashi, Eiji*; Sugiura, Hirokazu*; Kanemura, Takuji; Kondo, Hiroo; Yamaoka, Nobuo*; Horiike, Hiroshi*
no journal, ,
In the International Fusion Materials Irradiation Facility (IFMIF), a stable lithium (Li) target is required to maintain the integrity of the Li target itself and guarantee the desired neutron flux level. In this study, amplitudes of the free-surface waves were measured in an Osaka University Li loop with a contact-type liquid level sensor, and based on the measurement results, heat deposition rate from the deuteron beam to the flow channel (back wall) was calculated. Measurement results showed that at 175 mm downstream from the nozzle exit, maximum amplitudes at the velocity of more than 9 m/s were approximately 2 mm, which is larger than the IFMIF design specification value of 1 mm. However occurrence frequency of such large-amplitude waves were very low. Based on the amplitude measurement data, heat deposition rate from the deuteron beam to the flow channel was calculated to be less than 200 W in the simple model.
Kanemura, Takuji; Kondo, Hiroo; Sugiura, Hirokazu*; Hoashi, Eiji*; Yoshihashi, Sachiko*; Muroga, Takeo*; Furukawa, Tomohiro; Hirakawa, Yasushi; Wakai, Eiichi; Horiike, Hiroshi*
no journal, ,
Application studies of liquid metal (LM) wall jets are progressing in nuclear fusion researches. Examples are LM diverters or the Li target of the International Fusion Materials Irradiation Facility (IFMIF). It is important to understand flow characteristics based on measurement in order to judge whether a LM wall jet is feasible as a coolant or a nuclear target. To do so, diagnostics applicable to LM must be developed. The authors started researches on the flow characteristics of the IFMIF Li target in 2002. The diagnostics we developed are a high-speed video camera for visualization of free surface, a contact-type liquid level sensor and a laser probe method for measurement of amplitude of free-surface waves, etc. We have succeeded in understanding the flow characteristics of the Li wall jet by measuring them. The diagnostics we developed are applicable to other LM free-surface flows, and the flow characteristics we obtained are valuable as fundamental data for other LM flows.
