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Journal Articles

Development of an extensive database of mechanical and physical properties for reduced-activation martensitic steel F82H

Jitsukawa, Shiro; Tamura, Manabu*; Van der Schaaf, B.*; Klueh, R. L.*; Alamo, A.*; Petersen, C.*; Schirra, M.*; Spaetig, P.*; Odette, G. R.*; Tavassoli, A. A.*; et al.

Journal of Nuclear Materials, 307-311(Part1), p.179 - 186, 2002/12

 Times Cited Count:162 Percentile:99.28(Materials Science, Multidisciplinary)

Reduced activation ferritic/martensitic steel is the primary candidate structural material for ITER Test Blanket Modules and DEMOnstration fusion reactor because of its excellent dimensional stability under irradiation and lower residual activity as compared with the Ni bearing steels such as the austenitic stainless steels. In this paper, microstructural features, tensile, fracture toughness, creep and fatigue properties of a reduced activation martensitic steel F82H (8Cr-2W-0.04Ta-0.1C) are reported before and after irradiation, in addition to the design concept used for development of this alloy. A large number of collaborative test results including those generated under the IEA working group implementing agreements are collected and are used to evaluate the feasibility of use of F82H steel as one of the reference alloys. The effect of metallurgical variables on the irradiation hardening is reviewed and compared with the results obtained from irradiation experiments.

Oral presentation

Progress in DEMO R&D activities within the BA-IFERC project

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.

Oral presentation

EU and JA collaboration activities in DEMO R&D of the BA-IFERC project

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-$$^{17}$$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.

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