Design and Construction of IFMIF/EVEDA Lithium Test Loop

Author:

Kondo H.1,Furukawa T.1,Hirakawa Y.1,Ida M.2,Matsushita I.3,Horiike H.4,Kanemura T.2,Sugiura H.4,Yagi J.5,Suzuki A.5,Terai T.5,Fukada S.6,Nakamura H.6

Affiliation:

1. Japan Atomic Energy Agency, 4002 Narita, O-arai, Ibaraki 311-1393, Japan

2. Japan Atomic Energy Agency, 2-4 Shirakata-Shirane, Tokai, Ibaraki 319-1195, Japan

3. Mitsubishi Heavy Industries Mechatronics Systems, Ltd., 1-16 Komatsu-dori 5, Hyogo-ku, Kobe 652-0865, Japan

4. Osaka University, 2-1 Yamada-oka, Suita, Osaka 565-0871, Japan

5. University of Tokyo, 2-22 Shirakata-Shirane, Tokai, Ibaraki 319-1188, Japan

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

Abstract

Abstract 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 (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.

Publisher

ASME International

Subject

Mechanical Engineering,Energy Engineering and Power Technology,Aerospace Engineering,Fuel Technology,Nuclear Energy and Engineering

Reference8 articles.

1. IFMIF International Team, “IFMIF Comprehensive Design Report,” IEA online publication, http://www.iea.org/Textbase/techno/technologies/fusion/IFMIF-CDR_partA.pdf and partB

2. Martone, M. , 1996, “IFMIF Conceptual Design Activity,” ENEA Frascati Report No. RT/ERG/FUS/96/17.

3. Moeslang, A. , 1999, “IFMIF Conceptual Design Evaluation Report,” Forschungszentrum Karlsruhe Report No. FZKA 6199.

4. IFMIF International Team, 2003, “IFMIF KEP Report,” JAERI Laboratory Report No. JAERI-Tech 2003-005.

5. Thermal-Hydraulic Characteristics of IFMIF Liquid Lithium Target;Ida;Fusion Eng. Des.

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