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Research Papers: Nuclear Power

Design and Construction of IFMIF/EVEDA Lithium Test Loop

[+] Author and Article Information
H. Kondo

 Japan Atomic Energy Agency, 4002 Narita, O-arai, Ibaraki 311-1393, Japankondo.hiroo@jaea.go.jp

T. Furukawa

 Japan Atomic Energy Agency, 4002 Narita, O-arai, Ibaraki 311-1393, Japanfurukawa.tomohiro@jaea.go.jp

Y. Hirakawa

 Japan Atomic Energy Agency, 4002 Narita, O-arai, Ibaraki 311-1393, Japanhirakawa.yasushi@jaea.go.jp

M. Ida

 Japan Atomic Energy Agency, 2-4 Shirakata-Shirane, Tokai, Ibaraki 319-1195, Japanida.mizuho@jaea.go.jp

I. Matsushita

 Mitsubishi Heavy Industries Mechatronics Systems, Ltd., 1-16 Komatsu-dori 5, Hyogo-ku, Kobe 652-0865, Japanizuru_matsushita@mhims.mhi.co.jp

H. Horiike

 Osaka University, 2-1 Yamada-oka, Suita, Osaka 565-0871, Japanhoriike@nucl.eng.osaka-u.ac.jp

T. Kanemura

 Japan Atomic Energy Agency, 2-4 Shirakata-Shirane, Tokai, Ibaraki 319-1195, Japankanemura.takuji@jaea.go.jp

H. Sugiura

 Osaka University, 2-1 Yamada-oka, Suita, Osaka 565-0871, Japansugiura@stu.nucl.eng.osaka-u.ac.jp

J. Yagi

 University of Tokyo, 2-22 Shirakata-Shirane, Tokai, Ibaraki 319-1188, Japanyagi@nuclear.jp

A. Suzuki

 University of Tokyo, 2-22 Shirakata-Shirane, Tokai, Ibaraki 319-1188, Japansuzuki@nuclear.jp

T. Terai

 University of Tokyo, 2-22 Shirakata-Shirane, Tokai, Ibaraki 319-1188, Japantera@n.t.u-tokyo.ac.jp

S. Fukada

 Kyushu University, Hakozaki, Higashi-ku, Fukuoka 812-8581, Japansfukada@nucl.kyushu-u.ac.jp

H. Nakamura

 Kyushu University, Hakozaki, Higashi-ku, Fukuoka 812-8581, Japan

J. Eng. Gas Turbines Power 133(5), 052910 (Dec 16, 2010) (6 pages) doi:10.1115/1.4002868 History: Received July 12, 2010; Revised August 05, 2010; Published December 16, 2010; Online December 16, 2010

The International Fusion Materials Irradiation Facility (IFMIF) is a D+Li neutron source aimed at producing an intense high energy neutron flux (2MW/m2) 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.

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Copyright © 2011 by American Society of Mechanical Engineers
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References

Figures

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Figure 1

Concept of IFMIF

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Figure 2

P&ID of EVEDA Li test loop

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Figure 3

Elevation view of EVEDA Li test loop

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Figure 4

Target assembly (SS 316L model)

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Figure 5

Confinement vessel

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