Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Kanemura, Takuji; Kondo, Hiroo; Furukawa, Tomohiro; Hirakawa, Yasushi; Hoashi, Eiji*; Yoshihashi, Sachiko*; Horiike, Hiroshi*; Wakai, Eiichi
Fusion Engineering and Design, 98-99, p.1991 - 1997, 2015/10
Times Cited Count：14 Percentile：75.12(Nuclear Science & Technology)A high-speed (15 m/s) liquid lithium jet is planned to be utilized as the target of two 40 MeV - 125 mA deuteron beams in the International Fusion Materials Irradiation Facility (IFMIF). The target thickness is required to be maintained within 25 
1 mm under a vacuum condition of 10
Pa. This paper reports the result of measurements of the Li-target thickness under the IFMIF condition (Li speed of 10 to 20 m/s, vacuum pressure of 10 Pa, Li temperature of 250
C) in the EVEDA Li Test Loop. The target thickness was found to be 26.08 mm on average at the speed of 15 m/s at the center of the IFMIF beam footprint. As for temporal fluctuation, average and maximum amplitude at the same measurement position were 0.26 and 1.45 mm, respectively, and more than 99.7% of all amplitudes measured were within the design requirement. Therefore, it was found that the Li target fulfilled the required stability for IFMIF.
Wakai, Eiichi; Kondo, Hiroo; Kanemura, Takuji; Hirakawa, Yasushi; Furukawa, Tomohiro; Hoashi, Eiji*; Fukada, Satoshi*; Suzuki, Akihiro*; Yagi, Juro*; Tsuji, Yoshiyuki*; et al.
Proceedings of Plasma Conference 2014 (PLASMA 2014) (CD-ROM), 2 Pages, 2014/11
In the IFMIF/EVEDA (International Fusion Materials Irradiation Facility/ Engineering Validation and Engineering Design Activity), the validation tests of the EVEDA lithium test loop with the world's highest flow rate of 3000 L/min was succeeded in generating a 100 mm-wide and 25 mm-thick free-surface lithium flow steadily under the IFMIF operation condition of a high-speed of 15 m/s at 250C in a vacuum of 10 Pa. Some excellent results of the recent engineering validations including lithium purification, lithium safety, and remote handling technique were obtained, and the engineering design of lithium facility was also evaluated. These results will advance greatly the development of an accelerator-based neutron source to simulate the fusion reactor materials irradiation environment as an important key technology for the development of fusion reactor materials.
Kanemura, Takuji; Kondo, Hiroo; Hoashi, Eiji*; Suzuki, Sachiko*; Yamaoka, Nobuo*; Horiike, Hiroshi*; Furukawa, Tomohiro; Hirakawa, Yasushi; Wakai, Eiichi
Fusion Engineering and Design, 89(7-8), p.1642 - 1647, 2014/10
Times Cited Count：14 Percentile：72.16(Nuclear Science & Technology)In the Engineering Validation and Engineering Design Activities (EVEDA) of the International Fusion Materials Irradiation Facility (IFMIF), a device to measure thickness variation of a high-speed (15 m/s) liquid lithium (Li) jet must be developed. The required measurement precision is 0.1 mm. For this purpose, we newly focused on a laser-based distance meter. This paper describes the result of an applicability test of the new sensor conducted in the Osaka University Li Loop. In the experiment, thickness variation of a Li jet (10 mm in thickness) was measured at the sampling frequency of 500 kHz in the velocity range of 10 to 15 m/s at the Li temperature of 573 K under argon atmosphere of 0.12 MPa. To evaluate the applicability of the device, the measurement precision of the Li level was evaluated. As a result, the precision was approximately 9 
m. Thus, we concluded that the laser-based distance meter is applicable to the measurement of the Li target thickness.
Furukawa, Tomohiro; Kondo, Hiroo; Kanemura, Takuji; Hirakawa, Yasushi; Yamaoka, Nobuo*; Hoashi, Eiji*; Suzuki, Sachiko*; Horiike, Hiroshi*
Fusion Engineering and Design, 89(7-8), p.1674 - 1678, 2014/10
Times Cited Count：1 Percentile：8.75(Nuclear Science & Technology)One key issue in the development of the IFMIF is the corrosion/erosion of the lithium components. At Osaka University, lithium free-surface flow experiments to verify the design of the IFMIF target have been carried out, and the test assembly was operated in high-speed lithium flow for 1200 hours at 300 C. Since the test assembly is important to understand the corrosion/erosion behavior as the demonstration experimental data, the metallurgical analysis was been performed. Slight irregularities which were trace of high-speed lithium flow were observed at the tip of the nozzle. On the other hand, mottled unevenness with many micro-cracks of a few micrometer depths was observed at the inlet of the nozzle, whose velocity ratio was 0.1-0.4 as compared with the nozzle tip. It was estimated that the phenomena was caused by carburizing from liquid lithium, and it was newly proven that carbon control in lithium was also important for corrosion / erosion protection of the IFMIF components.
Wakai, Eiichi; Kondo, Hiroo; Kanemura, Takuji; Furukawa, Tomohiro; Hirakawa, Yasushi; Watanabe, Kazuyoshi; Ida, Mizuho*; Ito, Yuzuru; Niitsuma, Shigeto; Edao, Yuki; et al.
Fusion Science and Technology, 66(1), p.46 - 56, 2014/07
Times Cited Count：4 Percentile：30.65(Nuclear Science & Technology)Kanemura, Takuji; Kondo, Hiroo; Hoashi, Eiji*; Suzuki, Sachiko*; Yamaoka, Nobuo*; Horiike, Hiroshi*; Furukawa, Tomohiro; Hirakawa, Yasushi; Ida, Mizuho; Matsushita, Izuru*; et al.
Fusion Engineering and Design, 88(9-10), p.2547 - 2551, 2013/10
Times Cited Count：4 Percentile：32.11(Nuclear Science & Technology)In the Engineering Validation and Engineering Design Activities (EVEDA) project of the International Fusion Materials Irradiation Facility (IFMIF), thickness variation of a liquid lithium (Li) jet simulating the IFMIF Li target is to be measured in the EVEDA Li Test Loop. This paper presents fabrication and performance tests results of a contact-type liquid level sensor for measuring the jet thickness variation. The sensor can detect contacts between a probe and Li, and analysis of the contact signals yields average jet thickness and amplitude distribution. One of the key fabrication requirements is to drive the probe by 0.1 mm step with positioning precision of 0.01 mm under the vacuum condition of 10Pa. To achieve such requirements, a high torque motor reducer and a friction-reduced ball screw were selected. As a result of the performance tests, the measurement results of the positioning resolution and precision were 0.1 mm and 0.01 mm, respectively.
Kimura, Haruyuki; Hoashi, Eiji*
Fusion Engineering and Design, 88(5), p.327 - 340, 2013/06
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)Curved magnetically guided lithium target (MGLT) without a back plate was proposed for accelerator-based intense neutron source such as IFMIF. The curved MGLT can replace conventional lithium target with a curved back plate under the most severe condition on neutron irradiation. The magnetic field suited for MGLT is produced in combination of radiation-proof resistive coils and F82H parts (yokes, nozzles and high flux test module (HFTM)). Shape of the magnetic field becomes curved in the target region by setting HFTM closely to MGLT. Lithium flow on MGLT was analyzed in detail by two dimensional equations of motion with magnetic field calculated by the Poisson Superfish code. The necessary magnetic flux density at the target region was found to be about 0.5 T to fulfill the IFMIF target conditions; flow speed of 15 m/s, curvature radius of 1-1.6 m and flow thickness of 0.025 m. A narrow gap (a few mm) between MGLT and HFTM could be controlled via control of the coil current.
Wakai, Eiichi; Kondo, Hiroo; Sugimoto, Masayoshi; Fukada, Satoshi*; Yagi, Juro*; Ida, Mizuho; Kanemura, Takuji; Furukawa, Tomohiro; Hirakawa, Yasushi; Watanabe, Kazuyoshi; et al.
Purazuma, Kaku Yugo Gakkai-Shi, 88(12), p.691 - 705, 2012/12
no abstracts in English
Suzuki, Sachiko*; Hoashi, Eiji*; Kanemura, Takuji; Kondo, Hiroo; Yamaoka, Nobuo*; Horiike, Hiroshi*
Fusion Engineering and Design, 87(7-8), p.1434 - 1438, 2012/08
Times Cited Count：5 Percentile：37.76(Nuclear Science & Technology)In the international fusion materials irradiation facility (IFMIF), the high speed liquid metal lithium (Li) wall jet will be used as a target irradiated by two deuteron beams to generate intense neutrons. It is thus important to obtain the surface wave characteristic for the safety and the efficiency of system in the IFMIF. In this paper, the free surface oscillation was measured at 175 mm and 15 mm downstream from the nozzle exit with an electro-contact probe apparatus installed on a renewal flow channel of an Osaka University Li loop. At the velocity of more than 9 m/s, maximum wave amplitudes were about 2 mm, which exceed the current design value of IFMIF. However, the number of large-amplitude waves was found to be very low.
Kanemura, Takuji; Kondo, Hiroo; Suzuki, Sachiko*; Hoashi, Eiji*; Yamaoka, Nobuo*; Horiike, Hiroshi*; Furukawa, Tomohiro; Ida, Mizuho; Nakamura, Kazuyuki; Matsushita, Izuru*; et al.
Fusion Science and Technology, 62(1), p.258 - 264, 2012/07
Times Cited Count：4 Percentile：31.65(Nuclear Science & Technology)In the Engineering Validation and Engineering Design Activities (EVEDA) project of the International Fusion Materials Irradiation Facility (IFMIF), which is one of the Broader Approach (BA) activities, thickness variation of a liquid lithium (Li) jet simulating the IFMIF Li target is planned to be measured in the EVEDA Li Test Loop (ELTL). For this purpose, a contact-type liquid level sensor was developed, which can detect contacts between a probe and Li. Analysis of the contact signals yields average jet thickness and amplitude distribution. One of the key development requirements is to drive the probe by 0.1 mm step with positioning accuracy of 0.01 mm under the vacuum condition of 10Pa. To satisfy such a requirement, the sensor's own weight load and moment load were calculated, and based on those calculation results a powerful motor and a friction-reduced ball screw were selected and strong structure was adopted. We have successfully completed the design work of the sensor.
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：60.56(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.
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.
Wakai, Eiichi; Kondo, Hiroo; Kanemura, Takuji; Furukawa, Tomohiro; Hirakawa, Yasushi; Nakaniwa, Koichi; Ito, Yuzuru; Tanaka, Hiroshi; Tsuji, Yoshiyuki*; Ito, Takahiro*; et al.
no journal, ,
no abstracts in English
Kanemura, Takuji; Kondo, Hiroo; Furukawa, Tomohiro; Hirakawa, Yasushi; Hoashi, Eiji*; Yoshihashi, Sachiko*; Horiike, Hiroshi*; Wakai, Eiichi
no journal, ,
A high-speed (15 m/s) liquid lithium jet is planned to be utilized as the target of two 40 MeV - 125 mA deuteron beams in the International Fusion Materials Irradiation Facility (IFMIF). The target thickness is required to be maintained within 25 1 mm under a vacuum condition of 10 Pa. This paper reports the result of measurements of the Li-target thickness under the IFMIF condition (Li speed of 10 to 20 m/s, vacuum pressure of 10 Pa, Li temperature of 250C) in the EVEDA Li Test Loop. The target thickness was found to be 26.08 mm on average at the speed of 15 m/s at the center of the IFMIF beam footprint. As for temporal fluctuation, average and maximum amplitude at the same measurement position were 0.26 and 1.45 mm, respectively, and more than 99.7% of all amplitudes measured were within the design requirement. Therefore, it was found that the Li target fulfilled the required stability for IFMIF.
Kanemura, Takuji; Kondo, Hiroo; Furukawa, Tomohiro; Hirakawa, Yasushi; Hoashi, Eiji*; Yoshihashi, Sachiko*; Horiike, Hiroshi*; Wakai, Eiichi
no journal, ,
A high-speed (15 m/s) liquid lithium jet is planned to serve as the target of two 40 MeV - 125 mA deuteron two-beams in the International Fusion Materials Irradiation Facility (IFMIF). The target thickness is required to be maintained within 25 1 mm under a vacuum condition of 10 Pa. In this study, we report the result of measurements of the Li target thickness under the IFMIF condition (Li speed of 15 m/s, vacuum pressure of 10 Pa, Li temperature of 250 C) in the EVEDA Li Test Loop. The target was found to be adequately smooth on average inside the corresponding IFMIF beam footprint. The measurement result of temporal fluctuations showed they were dominated by small waves with amplitude of less than 1 mm, and that the average amplitude at the center of beam footprint was 0.26 mm. Therefore, it was found that the Li target fulfilled the required stability for IFMIF.
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.
Kanemura, Takuji; Kondo, Hiroo; Furukawa, Tomohiro; Yamaoka, Nobuo*; Suzuki, Sachiko*; Hoashi, Eiji*; Horiike, Hiroshi*; Nakamura, Kazuyuki
no journal, ,
In the Engineering Validation and Engineering Design Activities (EVEDA) of the International Fusion Materials Irradiation Facility (IFMIF) which is one of the Broader Approach (BA) activities, the thickness variation of the liquid lithium (Li) jet simulating the IFMIF Li target is planned to be measured in EVEDA Li Test Loop (ELTL). A contact-type liquid level sensor which will be utilized for thickness measurement was developed. The sensor can detect the contacts between a probe and Li, and by analyzing the contact signals, variation characteristics such as average jet thickness and an amplitude distribution can be obtained. One of the key points of development is to drive the probe by 0.1 mm step with repeat accuracy of 0.01 mm under vacuum condition of 10Pa. To satisfy such a requirement, a powerful motor which has good positioning performance and a friction-reduced ball screw were selected. It is finally confirmed that the sensor performance satisfies the specification.
Wakai, Eiichi; Kondo, Hiroo; Kanemura, Takuji; Hirakawa, Yasushi; Furukawa, Tomohiro; Kikuchi, Takayuki; Ito, Yuzuru*; Hoashi, Eiji*; Yoshihashi, Sachiko*; Horiike, Hiroshi*; et al.
no journal, ,
no abstracts in English
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.
