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Journal Articles

Measurement of Li target thickness in the EVEDA Li Test Loop

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:16 Percentile:77.59(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 $$pm$$ 1 mm under a vacuum condition of 10$$^{-3}$$ 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$$^{-3}$$ Pa, Li temperature of 250$$^{circ}$$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.

Journal Articles

Status of development of Lithium Target Facility in IFMIF/EVEDA project

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 250$$^{circ}$$C in a vacuum of 10 $$^{-3}$$ 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.

Journal Articles

Metallurgical analysis of lithium test assembly operated for 1200 h

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:2 Percentile:15.74(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 $$^{circ}$$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.

Journal Articles

Evaluation of applicability of laser-based distance meter to measure Li-jet thickness for IFMIF/EVEDA project

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:15 Percentile:73.06(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 $$mu$$m. Thus, we concluded that the laser-based distance meter is applicable to the measurement of the Li target thickness.

Journal Articles

Engineering validation and engineering design of lithium target facility in IFMIF/EVEDA project

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:29.67(Nuclear Science & Technology)

Journal Articles

Fabrication and performance test of contact-type liquid level sensor for measuring thickness variation of liquid lithium jet in the IFMIF/EVEDA lithium test loop

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:31.43(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 10$$^{-3}$$Pa. 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.

Journal Articles

Concept of curved magnetically guided liquid lithium target without a back plate for IFMIF

Kimura, Haruyuki; Hoashi, Eiji*

Fusion Engineering and Design, 88(5), p.327 - 340, 2013/06

 Times Cited Count:0 Percentile:0.00(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.

Journal Articles

Development of lithium target system in engineering validation and engineering design activity of the International Fusion Materials Irradiation Facility (IFMIF/EVEDA)

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

AA2012-1008.pdf:2.42MB

no abstracts in English

Journal Articles

Characteristics of surface oscillation on high speed liquid Li jet

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:36.82(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.

Journal Articles

Engineering design of contact-type liquid level sensor for measuring thickness validation of liquid lithium jet in IFMIF/EVEDA lithium test loop

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:31.05(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 10$$^{-3}$$Pa. 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.

Journal Articles

Present status of Japanese tasks for lithium target facility under IFMIF/EVEDA

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:59.68(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.

Journal Articles

Study on surface wave characteristics of free surface flow of liquid metal lithium for IFMIF

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.

Oral presentation

Proposal of curved magnetically guided liquid lithium target without a back plate for an intense neutron source

Kimura, Haruyuki; Hoashi, Eiji*

no journal, , 

no abstracts in English

Oral presentation

Present status of activities in the IFMIF/EVEDA lithium test loop, 2; Measurement tests for the lithium target

Kanemura, Takuji; Kondo, Hiroo; Furukawa, Tomohiro; Hirakawa, Yasushi; Ida, Mizuho; Yamaoka, Nobuo*; Suzuki, Sachiko*; Hoashi, Eiji*; Horiike, Hiroshi*; Wakai, Eiichi

no journal, , 

In the Engineering Validation and Engineering Design Activities (EVEDA) of the International Fusion Materials Irradiation Facility (IFMIF), it is required that a device to measure thickness variation of the lithium (Li) target with precision of 0.1 mm shall be delivered. As a favorable device to meet such a precision, we experimentally evaluated applicability of a laser-based distance meter to measurement of Li target thickness in the EVEDA Li Test Loop. To evaluate the applicability of the device, the measurement precision of the Li thickness was evaluated in the velocities of 10 and 15 m/s. As a result, the precision was 0.03mm. Thus, we concluded that a laser-based distance meter is applicable to measurement of the Li target thickness. The average target thickness varies in the both streamwise and spanwise direction due to the surface wakes initiated at the nozzle edge.

Oral presentation

Progress and scheme of IFMIF/EVEDA project; Lithium target facility

Wakai, Eiichi; Watanabe, Kazuyoshi; Ida, Mizuho*; Kondo, Hiroo; Kanemura, Takuji; Niitsuma, Shigeto*; Fujishiro, Koji; Ito, Yuzuru; Nakaniwa, Koichi; Sugimoto, Masayoshi; et al.

no journal, , 

Oral presentation

Present status of Japanese tasks for lithium target facility under IFMIF/EVEDA, 3; Evaluation of liquid-lithium free-surface flow stability

Kanemura, Takuji; Kondo, Hiroo; Furukawa, Tomohiro; Hirakawa, Yasushi; Yoshihashi, Sachiko*; Hoashi, Eiji*; Yamaoka, Nobuo*; Horiike, Hiroshi*; Wakai, Eiichi

no journal, , 

A high-speed (15 m/s) liquid lithium (Li) jet is planned to be utilized as the target of two 40 MeV - 125 mA deuteron beams in the International Fusion Materials Irradiation Facility. The target thickness is required to be maintained within 25 $$pm$$ 1 mm under a vacuum condition of 10$$^{-3}$$ Pa. This paper presents the measurement results of the Li target thickness at the velocity of 10, 15 and 20 m/s under an Ar pressure of 0.12 MPa. The target was found to be rather smooth and approx. 26 mm in thickness on average at the all velocities in the region of interest. As for temporal variation, average wave amplitude was 0.3 mm at the all velocities in the same region. Therefore, it was found that the Li target stability was completely within the requirement on average under an Ar pressure of 0.12 MPa. The next step is to measure the Li target under the IFMIF condition of 10$$^{-3}$$ Pa.

Oral presentation

Progress of activities in the IFMIF/EVEDA lithium test loop, 2-2; Thickness measurement of Li target

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. The target thickness is required to be maintained within 25 $$pm$$ 1 mm under a vacuum condition of 10$$^{-3}$$ Pa. At present, measurements of the Li target thickness at the velocities of up to 20 m/s under an Ar pressure of 10$$^{-3}$$ Pa $$sim$$ 0.12 MPa have been finished. The target was found to be approx. 26 mm in thickness on average at the velocity of 15 m/s under a pressure of 0.12 MPa in the region of interest. As for temporal variation, average wave amplitude was 0.3 mm under the same condition in the same region. Therefore, it was found that the Li target stability was completely within the requirement on average under an Ar pressure of 0.12 MPa. The analysis of measurement results under the IFMIF condition of 10$$^{-3}$$ Pa are ongoing, and they seem almost identical to the result of 0.12 MPa.

Oral presentation

Award lecture; Progress of activities in the IFMIF/EVEDA lithium test loop

Kanemura, Takuji; Kondo, Hiroo; Furukawa, Tomohiro; Hirakawa, Yasushi; Hoashi, Eiji*; Yoshihashi, Sachiko*; Horiike, Hiroshi*; Wakai, Eiichi

no journal, , 

(Award lecture) A high-speed (15 m/s) liquid lithium (Li) jet is to be utilized as the target of two 40 MeV - 125 mA deuteron beams in the International Fusion Materials Irradiation Facility. The target thickness is required to be maintained within 25 $$pm$$ 1 mm under a vacuum condition of 10$$^{-3}$$ Pa. This presentation reports the measurement and analysis results of the Li target thickness at the velocity of 10, 15 and 20 m/s under an Ar pressure of 0.12 MPa. The measurement result showed that the thickness was approx. 26.0 mm $$pm$$ 1.5 mm at the all velocities in the region of interest. Therefore, it was found that the Li target stability under an Ar atmosphere exceeded slightly more than the design requirement. By modeling static pressure gradient, the target thickness was analyzed based on the theory of fluid mechanics. The result showed good agreement with the measurement result, which means the static pressure gradient is a dominant factor for determination of the target thickness.

Oral presentation

R&D of lithium target and test facilities for the fusion neutron source

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

Oral presentation

Study on free-surface flow of liquid lithium, 2; Simulation of boundary layer flow inside nozzle in IFMIF

Oka, Takeshi*; Hoashi, Eiji*; Suzuki, Sachiko*; Takita, Masahiro*; Kanemura, Takuji; Kondo, Hiroo; Furukawa, Tomohiro; Yamaoka, Nobuo*; Horiike, Hiroshi*

no journal, , 

In the International Fusion Materials Irradiation Facility (IFMIF), a lithium (Li) jet produced by a nozzle is designed as a deuteron-beam target to generate neutrons. To maintain integrity of the Li target, amplitude of surface waves on the jet is designed to be less than 1 mm. In this study, a numerical simulation with a CFD code was conducted to examine a boundary layer flow along the nozzle wall which directly affects generation of the surface waves. Calculation results with Large-Eddy Simulation (LES) model showed that Goertler vortices were generated along the wall near the nozzle exit. After flow separation at the nozzle exit, the generated Goertler vortices did not disappear underneath the free surface. This suggests the vortices affects generation of the surface waves near the nozzle exit.

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