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Journal Articles

Preparation for lower port integration engineering for ITER diagnostic systems in JADA

Kitazawa, Sin-iti; Maruyama, Toshiyuki; Ogawa, Hiroaki; Itami, Kiyoshi; Casal, N.*

Plasma and Fusion Research (Internet), 10(Sp.2), p.3402044_1 - 3402044_4, 2015/04

Journal Articles

Current status of the engineering design of the test modules for the IFMIF

Yamamoto, Michiyoshi; Arbeiter, F.*; Yokomine, Takehiko*; Wakai, Eiichi; Theile, J.*; Garcia, A. S.*; Rapisarda, D. S.*; Casal, N. I.*; Mas, A. S.*; Gouat, P.*; et al.

Fusion Engineering and Design, 88(6-8), p.746 - 750, 2013/10

 Times Cited Count:12 Percentile:73.42(Nuclear Science & Technology)

Under Broader Approach (BA) Agreement between EURATOM and Japan, IFMIF/EVEDA (International Fusion Materials Irradiation Facility/Engineering Validation and Engineering Design Activities) has been performed since the middle of 2007. The present EVEDA phase aims at producing a detailed, compete and fully integrated engineering design of IFMIF. The deivery of the Intermediate IFMIF engineering design report is foreseen mid-2013. The main function of the IFMIF is to provide the materials database for the design and licensing of DEMO reactor and further fusion rectors from the material sets irradiated in High Flux Test Modules (HFTM, Startup Monitoring Module), Medium Flux Test Modules (Creep Fatigues Test Module, Tritium Release Test Module, Liquid Breeder Validation Module) and Low Flux Test Modules of IFMIF. This paper is summarizing the current progress of the engineering design of the test modules within the IFMIF/EVEDA project.

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