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Shimomura, Kenta; Yamashita, Takuya; Nagae, Yuji
Proceedings of 11th European Review Meeting on Severe Accident Research Conference (ERMSAR 2024) (Internet), 12 Pages, 2024/05
Wakai, Eiichi; Taguchi, Tomitsugu; Yamamoto, Toshio*; Tomita, Hideki*; Takada, Fumiki; Jitsukawa, Shiro
Materials Transactions, 46(3), p.481 - 486, 2005/03
Times Cited Count：9 Percentile：56.67(Materials Science, Multidisciplinary)no abstracts in English
Taguchi, Tomitsugu; Jitsukawa, Shiro; Sato, Michitaka*; Matsukawa, Shingo*; Wakai, Eiichi; Shiba, Kiyoyuki
Journal of Nuclear Materials, 335(3), p.457 - 461, 2004/12
Times Cited Count：11 Percentile：58.02(Materials Science, Multidisciplinary)F82H (Fe-8Cr-2W) and its variant doped with 2%Ni were irradiated up to 20 dpa at 300
C in the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory. Post irradiation tensile testing was performed at room temperature. During testing, the images of the specimens including the necked region were continuously recorded. Tests on cold worked material were also carried out for comparison. From the load-displacement curves and the strain distributions obtained from the images, flow stress levels and strain hardening behavior was evaluated. A preliminary constitutive equation for the plastic deformation of irradiated F82H is presented. The results suggest that the irradiation mainly causes defect-induced hardening while it did not strongly affect strain hardening at the same flow stress level for F82H irradiated at 300C. The strain hardening of Ni doped specimens was, however, strongly affected by irradiation. Results provide basics to determine allowable stress levels at temperatures below 400C.
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：170 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.
Wakai, Eiichi; Hishinuma, Akimichi; Usami, Koji; Kato, Yasushi*; Takaki, Seiichi*; Abiko, Kenji*
Materials Transactions, JIM, 41(9), p.1180 - 1183, 2000/09
no abstracts in English
Oku, Tatsuo*; Kurumada, Akira*; McEnaney, B.*; Burchell, T. D.*; Ishihara, Masahiro; Hayashi, Kimio; Baba, Shinichi; Aihara, Jun
Proceedings of 1st World Conference of Carbon (EUROCARBON 2000), 1, p.947 - 947, 1999/07
no abstracts in English
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Advances in Cryogenic Engineering Materials, Vol.34, p.173 - 181, 1988/00
no abstracts in English
Seguchi, Tadao; Arakawa, Kazuo; ; Hayakawa, Naohiro; Machi, Sueo
Radiation Physics and Chemistry, 21(6), p.495 - 501, 1983/00
no abstracts in English
; ; Ueda, Shuzo
Nihon Kikai Gakkai Rombunshu, A, 42(359), p.2034 - 2041, 1976/00
no abstracts in English
; ;
Translation, 19(203), p.1 - 11, 1970/00
no abstracts in English
