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Tanigawa, Hiroyasu; Shiba, Kiyoyuki; M
slang, A.*; Stoller, R. E.*; Lindau, R.*; Sokolov, M. A.*; Odette, G. R.*; Kurtz, R. J.*; Jitsukawa, Shiro
Journal of Nuclear Materials, 417(1-3), p.9 - 15, 2011/10
Times Cited Count：131 Percentile：99.57(Materials Science, Multidisciplinary)ITER construction was started, and R&D toward DEMO shifted to more practical stage. On this stage, the candidate material for DEMO blanket have to be the one which have sound engineering bases to be ready for engineering designing activity for DEMO reactor in 10 years. Reduced activation ferritic/martensitic (RAFM) steels, such as F82H (Fe-8Cr-2W-0.2V-0.04Ta) or EUROFER97 (Fe-9Cr-1W-0.2V- 0.12Ta), is the only material which currently have enough potential to meet this requirement, and selected as the target material in the R&D on materials engineering for DEMO blanket under the International Fusion Energy Research Centre (IFERC) project in the Broader Approach (BA) activities between EU and Japan. In this paper, current status of RAFM R&D is overviewed especially on fabrication technology, inspection/testing technology, and material database. Overview on irradiation effect study is also provided.
Kikuchi, Kenji; Yong, D.*; Al Mazouzi, A.*; Jean, H.*; Maloy, S.*; Lindau, R.*; Park, J. Y.*; Grschel, F.*
no journal, ,
MEGAPIE (Megawatt Pilot Experiment) was successfully done in 2006. Components performance during high-energy proton beam bombardment under the liquid lead-bismuth flow will be studied to define ADS quality condition. Samples are cut from the spent target and distributed to collaborated organizations. PIE (Post Irradiation Experiment) will provide knowledge on materials quality evaluated by design, construction and operation. It is scheduled to pre-test in 2008-2009 and to do PIE in 2010 and 2011. Before conducting PIE round robin test is to be done in order to secure experiment technology level.
Hayashi, Kimio; Araki, Masanori; Baluc, N.*; Yamanishi, Toshihiko; Nishitani, Takeo; Hernandez, T.*; Morono, A.*; Moriani, A.*; Tosti, S.*; Nozawa, Takashi; et al.
no journal, ,
The Broader Approach (BA) activities have started in mid 2007. The DEMO R&D activities are intended to support the BA activities for design of fusion demonstration reactor (DEMO). The progress so far in the DEMO R&D activities is presented in this conference. Based on the common interest of the EU and Japan towards DEMO, current activities are smoothly proceeding in the following five areas: (1) SiC/SiC composites, (2) Tritium technology, (3) Materials engineering for DEMO blanket, (4) Advanced neutron multiplier, and (5) Advanced tritium breeders. From 2010 these R&D activities will be accelerated, after the preparation of the experimental equipment and facilities is completed.
Hayashi, Kimio; Nakajima, Noriyoshi*; Clement Lorenzo, S.*; Baluc, N.*; Nishitani, Takeo; Yamanishi, Toshihiko; Morono, A.*; Hernandez, T.*; Moriani, A.*; Tosti, S.*; et al.
no journal, ,
The DEMO R&D activities are intended to support the design activities of fusion demonstration reactor (DEMO) in the Broader Approach (BA). Recent progress in the DEMO R&D activities, particularly the status and plan for EU/JA collaboration activities, is presented in this conference. Equipment for investigation of the erosion /corrosion behavior of SiC/SiC composites in Pb-
Li is under fabrication for installation and experiments at the Rokkasho site. Irradiation of reduced activation ferritic /martensitic steels (EUROFER and F82H) in a Belgian reactor, BR2, is being prepared. Exchange of RAFM, neutron multiplier and tritium breeder samples between EU and JA is planned for collaborative characterization. Thus, the R&D activities are being upgraded.
