TY - JOUR
T1 - IFMIF/EVEDA lithium test loop
T2 - Design and fabrication technology of target assembly as a key component
AU - Kondo, H.
AU - Furukawa, T.
AU - Hirakawa, Y.
AU - Nakamura, K.
AU - Ida, M.
AU - Watanabe, K.
AU - Kanemura, T.
AU - Wakai, E.
AU - Horiike, H.
AU - Yamaoka, N.
AU - Sugiura, H.
AU - Terai, T.
AU - Suzuki, A.
AU - Yagi, J.
AU - Fukada, S.
AU - Nakamura, H.
AU - Matsushita, I.
AU - Groeschel, F.
AU - Fujishiro, K.
AU - Garin, P.
AU - Kimura, H.
N1 - Funding Information:
We thank Da-Yeong Jeong (Healthcare Claims & Management Inc., Jeonju, Republic of Korea) of data management and statistical analysis.
Funding Information:
This study was supported by a grant from Dalin Biotech Korea Co. Ltd. The funders had no role in study design, data collection and analysis, decision to publish, or preparation of the manuscript.
PY - 2011/12
Y1 - 2011/12
N2 - 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.
AB - 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.
UR - http://www.scopus.com/inward/record.url?scp=82555195129&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=82555195129&partnerID=8YFLogxK
U2 - 10.1088/0029-5515/51/12/123008
DO - 10.1088/0029-5515/51/12/123008
M3 - Article
AN - SCOPUS:82555195129
SN - 0029-5515
VL - 51
JO - Nuclear Fusion
JF - Nuclear Fusion
IS - 12
M1 - 123008
ER -