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Dive into the research topics where Hirokazu Sugiura is active.

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Featured researches published by Hirokazu Sugiura.


Nuclear Fusion | 2011

IFMIF/EVEDA lithium test loop: design and fabrication technology of target assembly as a key component

Hiroo Kondo; Tomohiro Furukawa; Yasushi Hirakawa; Kazuyuki Nakamura; Mizuho Ida; K. Watanabe; Takuji Kanemura; E. Wakai; Hiroshi Horiike; Nobuo Yamaoka; Hirokazu Sugiura; Takayuki Terai; Akihiro Suzuki; Juro Yagi; Satoshi Fukada; Hiroo Nakamura; Izuru Matsushita; F. Groeschel; K. Fujishiro; P. Garin; Haruyuki Kimura

The engineering validation and engineering design activity (EVEDA) for the International Fusion Materials Irradiation Facility (IFMIF) is proceeding as one of the ITER broader approach activities. In the concept of the IFMIF, two 40 MeV deuteron beams are injected into a liquid Li stream (Li target) flowing at a velocity of 15 m s−1. The EVEDA Li test loop (ELTL) is aimed at validating the hydraulic stability of the Li target at a velocity up to 20 m s−1 under a vacuum condition of 10−3 Pa as the most important issue. Construction of the ELTL, which is the largest liquid metal loop possessing 5.0 m3 Li for the fusion research ever, was completed in the O-arai Research & Development Center in the Japan Atomic Energy Agency on 22 November 2010. This paper presents the design and fabrication technology of a target assembly called integrated target assembly, in which the Li target is produced by a contraction nozzle along a concave channel. There are two concepts regarding the target assembly: the integrated target assembly and the bayonet target assembly. Both target assemblies are outlined in this paper, and then the newly proposed design of the integrated target assembly for the ELTL and its fabrication technology are given. The integrated target assembly was processed by a five-axis milling machine and the processing accuracy was measured by 3D measurement tools. Finally, methods applied for the validation of the stability of the Li target are introduced in this paper.


Journal of Nuclear Science and Technology | 2011

Experimental Study on Wave Propagation Behavior on Free Surface of Lithium Flow for IFMIF

Hirokazu Sugiura; Takuji Kanemura; Sachiko Yoshihashi-Suzuki; Hiroo Kondo; Taizo Kanai; Nobuo Yamaoka; Mizuho Ida; Hiroshi Horiike

Velocity measurement of surface waves on high-speed liquid lithium (Li) flow was conducted by using the Li circulation loop at Osaka University to support target monitor and diagnostics applications for the International Fusion Materials Irradiation Facility (IFMIF). Free surface shapes were recorded with a high-speed video camera, and surface waves were tracked with the statistical correlations of image intensity patterns over a velocity range of 5 to 15 m/s. As a result, the velocity distribution of surface waves was measured. The development of surface velocity beyond the nozzle edge was clearly measured. The velocity measurement by this method might suffer from some influence from stationary waves, which were generated by a damaged nozzle edge. The measured velocity in a region free from stationary waves was seen to exceed the mean flow velocity, probably due to two-dimensional regular waves. For this case, the measured velocity may consist of the advection velocity of the Li flow and the phase velocity of the wave. For an irregular wave region, the measured velocity was shown to be approximately the same as the mean flow velocity. The present flow velocity measurement can be used in the high-velocity range where random waves are generated.


Journal of Engineering for Gas Turbines and Power-transactions of The Asme | 2011

Design and Construction of IFMIF/EVEDA Lithium Test Loop

Hiroo Kondo; T. Furukawa; Y. Hirakawa; Mizuho Ida; Izuru Matsushita; Hiroshi Horiike; Takuji Kanemura; Hirokazu Sugiura; J. Yagi; A. Suzuki; T. Terai; S. Fukada; H. Nakamura

The International Fusion Materials Irradiation Facility (IFMIF) is a D + ―Li neutron source aimed at producing an intense high energy neutron flux (2 MW/m 2 ) for testing candidate fusion reactor materials. Under Broader Approach activities, Engineering Validation and Engineering Design Activities (EVEDAs) of IFMIF started on July 2007. Regarding the lithium (Li) target facility, design, construction, and tests of EVEDA Li test loop (ELTL) is a major Japanese activity. The detail design of the loop was started since early 2009. Construction of the loop was started at the middle of 2009, and completion is scheduled at the end of February 2011. This paper focuses on the design of the loop configuration and the major components. ELTL was designed to consist of two major Li loops, which are a main loop and a purification loop including an impurity monitoring loop. The main loop equips a target assembly which produces a high-speed free-surface Li flow to test the flow stability as the D + beam target. The maximum flow rate of an electromagnetic pump in the main loop was set to 3000 l/min, so that flow velocity in the target assembly is 20 m/s at the maximum. Regarding the purification loop, a cold trap and two hot traps and impurity monitors are installed in order to purify and monitor impurities in Li. The configuration of these components in addition to the specification and configuration of the whole loop is presented.


Journal of Engineering for Gas Turbines and Power-transactions of The Asme | 2011

Measurement of Wavy Surface Oscillations on Liquid Metal Lithium Jet for IFMIF Target

Hirokazu Sugiura; Takuji Kanemura; Sachiko Yoshihashi-Suzuki; Hiroo Kondo; Tomohide Yoshikawa; Nobuo Yamaoka; Mizuho Ida; H. Nakamura; Izuru Matsushita; Hiroshi Horiike

The International Fusion Materials Irradiation Facility (IFMIF) has been conceived as a high-flux 14 MeV neutron source for testing candidate fusion reactor materials. In the current design, neutrons are generated by irradiating a target with a deuteron beam and high-speed free-surface flow of liquid metal lithium (Li) is adopted as the target. To reveal the stability of the Li flow, we have examined characteristics of surface waves at a location 175 nm downstream from a nozzle exit, which corresponds to the center of the beam irradiated region. In this study, the characteristics of surface waves just downstream of the nozzle exit were measured experimentally, since the initial growth of surface waves exerts a definite influence on the surface behavior of the Li flow in the downstream region. Experiments were carried out with a focus on surface oscillations of the Li flow using the lithium circulation loop at Osaka University. These oscillations are measured using an electro-contact probe apparatus, which can detect electrically a contact between the probe tip and the Li surface and provide local height data of surface waves. The apparatus was installed at a location 15 mm downstream from the nozzle exit and scanned the Li surface by moving along the liquid-depth direction. The experiments were performed for the velocity range of 3-15 m/s under argon gas atmosphere at a pressure of 0.13 MPa. The contact signal recorded in the experiment was used to analyze the characteristics of surface waves, and then the root-mean-square wave amplitude and the frequency of surface waves were calculated. It was found that the root-mean-square wave amplitudes of surface waves increased with a rise in the flow velocity, and reached approximately 0.18 mm at 14-15 m/s. And also, obtained frequencies were analyzed using a linear stability theory, and the variation of frequencies was examined with the mean flow velocity.


18th International Conference on Nuclear Engineering: Volume 6 | 2010

Current Status of Design and Construction of IFMIF/EVEDA Lithium Test Loop

Hiroo Kondo; Tomohiro Furukawa; Yasushi Hirakawa; Izuru Matsushita; Mizuho Ida; Hiroshi Horiike; Takuji Kanemura; Hirokazu Sugiura; Juro Yagi; Akihiro Suzuki; Takayuki Terai; Satoshi Fukada; H. Nakamura

The International Fusion Materials Irradiation Facility (IFMIF) is a D+ -Li neutron source aimed at producing an intense high energy neutron flux (2 MW/m2 ) 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. This paper presents the current status of the design and construction of EVEDA Li Test Loop. The EVEDA Li Test Loop consists of a main loop system and a purification loop system. 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. Currently, the system diagram of the EVEDA Li Test Loop is finished to be defined. The diagram and function of major components in the main loop system and the purification loop system are described in this paper.Copyright


Fusion Engineering and Design | 2010

Development of measurement technique for surface waves on high-speed liquid lithium jet for IFMIF target

Hiroo Kondo; Takuji Kanemura; Hirokazu Sugiura; Nobuo Yamaoka; Mizuho Ida; H. Nakamura; Izuru Matsushita; Takeo Muroga; Hiroshi Horiike


Fusion Engineering and Design | 2011

Overview: Free surface measurement with renewed nozzle of Osaka Li loop

Sachiko Yoshihashi-Suzuki; Hirokazu Sugiura; Eiji Hoashi; Hiroo Kondo; Takuji Kanemura; Nobuo Yamaoka; Mizuho Ida; Hiroo Nakamura; Kazuyuki Nakamura; Izuru Matsushita; Hiroshi Horiike


Fusion Engineering and Design | 2011

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

Kazuyuki Nakamura; Tomohiro Furukawa; Yasushi Hirakawa; Takuji Kanemura; Hiroo Kondo; Mizuho Ida; Shigeto Niitsuma; Masahiko Ohtaka; K. Watanabe; Hiroshi Horiike; Eiji Hoashi; Sachiko Suzuki; Nobuo Yamaoka; Hirokazu Sugiura; Takayuki Terai; Akihiro Suzuki; Juro Yagi; Mikiko Bannai; Satoshi Fukada; Hiroo Nakamura; Yuki Edao; Yoshiyuki Tsuji; Kazuyuki Furuya


Journal of Nuclear Materials | 2011

Characteristics of free-surface wave on high-speed liquid lithium jet for IFMIF

Takuji Kanemura; Sachiko Yoshihashi-Suzuki; Hiroo Kondo; Hirokazu Sugiura; Nobuo Yamaoka; Mizuho Ida; H. Nakamura; Izuru Matsushita; Takeo Muroga; Hiroshi Horiike


symposium on fusion technology | 2009

Thickness distribution of high-speed free-surface lithium flow simulating IFMIF target

H. Kondo; Takuji Kanemura; Hirokazu Sugiura; Nobuo Yamaoka; S. Miyamoto; Mizuho Ida; H. Nakamura; Izuru Matsushita; Takeo Muroga; Hiroshi Horiike

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Mizuho Ida

Japan Atomic Energy Agency

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Hiroo Kondo

Japan Atomic Energy Agency

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Izuru Matsushita

Mitsubishi Heavy Industries

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H. Nakamura

Japan Atomic Energy Agency

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