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

https://doi.org/10.13182/FST13-770

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

https://doi.org/10.1016/j.fusengdes.2011.04.033

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.

Design and construction of IFMIF/EVEDA Li test loop

Kondo, Hiroo; Furukawa, Tomohiro; Hirakawa, Yasushi; Iuchi, Hiroshi; Tokoro, Daishiro*; Kanemura, Takuji; Ida, Mizuho; Watanabe, Kazuyoshi; Niitsuma, Shigeto; Wakai, Eiichi; et al.

no journal, , 

Engineering Validation and Engineering Design Activities (EVEDA) for the International Fusion Materials Irradiation Facility (IFMIF) were started from July 2007 under an international agreement called ITER Broader Approach. As a major Japanese activity, EVEDA Li test loop (ELTL) to simulate hydraulic and impurity conditions of IFMIF has already designed and is under construction, in which feasibility of hydraulic stability of the liquid Li target, the purification systems of hot traps are major key issues to be validated in this loop. This presentation focuses on the engineering design of the ELTL, and its construction and commissioning.

Construction and first operation of vacuum system for EVEDA Li test loop of International Fusion Materials Irradiation Facility (IFMIF)

Nakamura, Kazuyuki; Ida, Mizuho; Kanemura, Takuji; Kondo, Hiroo; Niitsuma, Shigeto; Hirakawa, Yasushi; Furukawa, Tomohiro; Watanabe, Kazuyoshi; Wakai, Eiichi

no journal, , 

EVEDA Li test loop, which is one of the major conponents for the development of the IFMIF, has been fabricated in Oarai Research Center. A detail of the fabrication and the first operation of the vacuum system, which is compatible with the high temperature and much liquid Li(300 C, 2.5 ton), will be presented.

Development status of lithium target and test facilities in IFMIF/EVEDA project

Wakai, Eiichi; Kondo, Hiroo; Kanemura, Takuji; Ida, Mizuho; Watanabe, Kazuyoshi; Kim, B. J.; Fujishiro, Koji; Sugimoto, Masayoshi; Kimura, Haruyuki; Niitsuma, Shigeto

no journal, , 

no abstracts in English

Activities summary on lithium target system and test facilities in IFMIF/EVEDA Project, 7; Engineering design of lithium target and post irradiation examination facilities in IFMIF

Sugimoto, Masayoshi; Wakai, Eiichi; Kanemura, Takuji; Kikuchi, Takayuki; Ida, Mizuho*; Watanabe, Kazuyoshi*; Niitsuma, Shigeto*; Yamamoto, Michiyoshi*; Yutani, Toshiaki*; Hirano, Michiko*

no journal, , 

The International Fusion Materials Irradiation Facility - Engineering Validation and Engineering Design Activities (IFMIF/EVEDA) is a EU an Japan collaborative project under the framework of the Broader Approach activities for fusion energy development and, after the Intermediate Engineering Design Report has been completed in 2013, the validation test tasks have been conducted up to 2015. About the tasks in charge of Japan were completed in March and now we continue the evaluation of the testing results and examine how to reflect them to updated engineering design. In this report, we present the technical validity of the design based on the results of various validation tests and summarize the issues to be solved in future.