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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; Otsuka, Hideo*; Matsukawa, Shingo; Furuya, Kazuyuki*; Tanigawa, Hiroyasu; Oka, Keiichiro*; Onuki, Somei*; Yamamoto, Toshio*; Takada, Fumiki; Jitsukawa, Shiro
Fusion Engineering and Design, 81(8-14), p.1077 - 1084, 2006/02
Times Cited Count：12 Percentile：60.83(Nuclear Science & Technology)no abstracts in English
Onizawa, Kunio; Suzuki, Masahide
JSME International Journal, Series A, 47(3), p.479 - 485, 2004/07
In the structural integrity assessment of reactor pressure vessel, fracture toughness values are estimated by assuming that the radiation effect on fracture toughness is equivalent to that on Charpy properties. Therefore, it is necessary to establish the correlation between both properties especially on irradiation embrittlement. In this paper, we present the fracture toughness data obtained by applying the master curve approach that was adopted recently in the ASTM test method. Materials used in this study are five ASTM A533B class 1 steels and one weld metal. Neutron irradiation for Charpy-size specimens as well as standard Charpy-v specimens was carried out at the Japan Materials Testing Reactor. The shifts of the reference temperature on fracture toughness due to neutron irradiation are evaluated. Correlation between the fracture toughness reference temperature and Charpy transition temperature is established. Based on the correlation, the optimum test temperature for fracture toughness testing and the method to determine a lower bound fracture toughness curve are discussed.
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：183 Percentile：99.31(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.
Hayashi, Hirokazu; Minato, Kazuo
JAERI-Conf 2001-016, 181 Pages, 2001/12
JAERI-Conf-2001-016.pdf:11.72MB
Applications of molten salts technology to separations and syntheses of materials have been studied eagerly, which would develop new fields of materials science. Research Group for Actinides Science, Department of Materials Science, Japan Atomic Energy Research Institute (JAERI), together with Reprocessing and Recycle Technology Division, Atomic Energy Society of Japan, organized the Workshop on Molten Salts Technology and Computer Simulation at Tokai Research Establishment, JAERI on September 18, 2001. In the workshop eleven lectures were made and lively discussions were there on the bases and applications of the molten salts technology that covered the structure and basic properties of molten salts, the pyrochemical reprocessing technology and the relevant computer simulation.
Iguchi, Tadashi
JAERI-Research 2000-050, 107 Pages, 2000/09
JAERI-Research-2000-050.pdf:4.29MB
no abstracts in English
Oku, Tatsuo*; Kurumada, A.*; Nakata, M.*; Takeda, K.*; Kawamata, K.*; Arai, Taketoshi; Ishihara, Masahiro
Proceedings of 24th Biennial Conference on Carbon (CARBON '99), p.574 - 575, 1999/07
no abstracts in English
; ; Ueda, Shuzo
Nihon Kikai Gakkai Rombunshu, A, 42(359), p.2034 - 2041, 1976/00
no abstracts in English
Nakano, Hiroko; Takeuchi, Tomoaki; Hirota, Noriaki; Ide, Hiroshi; Hanawa, Masashige*; Tsuchiya, Kunihiko
no journal, ,
Since the accident at the Fukushima Dai-ichi Nuclear Power Plants (NPPs), it has started a research and development which corresponds to the provisions to monitor NPPs situations during a severe accident (SA). Considering that reactor vessel might be exposed to high radiation at high temperature under SA, difficulties may arrear in the measurement of temperature and pressure in the reactor vessel for long time. Thus it is necessary for the measurements of them to develop mineral insulated (MI) cables with radiation- and heat-resistant. In this study, the electric and corrosion properties of the MI cables were evaluated in the conditions that may simulate SA to develop MI cables that can be used even in SA environment. Based on the experiments above, the prospect is obtained that MI cable using nickel alloy as a sheath material can be proposed as a high-temperature MI cable that can be used even in SA environment.
