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Sumita, Junya; Nakano, Masaaki*; Tsuji, Nobumasa*; Shibata, Taiju; Ishihara, Masahiro
JAERI-Tech 2004-055, 25 Pages, 2004/08
JAERI-Tech-2004-055.pdf:4.25MB
Neutron irradiation remarkably reduces the thermal conductivity of graphite, and the reduced thermal conductivity is recovered by annealing effect if the graphite is heated above the irradiation temperature. Therefore, it is expected that the reduced thermal conductivity of graphite components in the HTGR could be recovered by the annealing effect in accidents, such as a depressurization accident. Then, an analytical investigation of the annealing effect on thermal performance of a HTGR core was carried. The analysis showed that the annealing effect reduces the maximum fuel temperature about 70
C, and it is important to introduce the annealing effect appropriately in the temperature analysis of the core components and reactor internals. In addition, an annealing test method was investigated to evaluate the effect quantitatively, and the test plan was made.
Fusion Neutron Laboratory
JAERI-Review 2004-017, 163 Pages, 2004/07
JAERI-Review-2004-017.pdf:25.47MB
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.
Ishitsuka, Etsuo; Kawamura, Hiroshi; Tanaka, Satoru*
JAERI-Conf 2004-006, 347 Pages, 2004/03
JAERI-Conf-2004-006.pdf:35.63MB
This report is the Proceedings of the Sixth International Energy Agency International Workshop on Beryllium Technology for Fusion. The workshop was held on December 2-5, 2003, at SEAGAIA in Miyazaki City, Japan with 69 participants who attended from Europe, the Russian Federation, Kazakhstan, Ukraine, China, the United States and Japan. The topics for papers were arranged into nine sessions; Status of beryllium study, Plasma and tritium interactions, ITER oriented issues, Neutron irradiation effects, Beryllide application, Disposal and recycling, Molten salt, Health and safety issues and Panel discussion. The issues in these topics were discussed intensively on the bases of 49 presentations. In the Panel discussion, the international collaboration for three topics, i.e., Neutron irradiation effects, Beryllide application, Recycling and Disposal, were discussed, and necessary items for the international collaboration were proposed.
Nemoto, Yoshiyuki; Hasegawa, Akira*; Sato, Manabu*; Abe, Katsunori*; Hiraoka, Yutaka*
Journal of Nuclear Materials, 324(1), p.62 - 70, 2004/01
Times Cited Count：38 Percentile：90.02(Materials Science, Multidisciplinary)In this study, stress-relieved specimens and recrystallized specimens of pure Mo and Mo-Re alloys (Re content=2,4,5,10,13 and 41wt%) were neutron irradiated up to 20dpa at various temperatures (681-1072K). On microstructure observation, sigma phase and chi phase precipitates were observed in all irradiated Mo-Re alloys. Voids were observed in all irradiated specimen, and dislocation loops and dislocations were observed in the specimens that were irradiated at lower temperatures. On Vickers hardness testing, all of the irradiated specimens showed hardening. Especially Mo-41Re were drastically embrittled after irradiation at 874K or less. From these results, authors discuss about relation between microstructure development and radiation hardening, embrittlement, and propose the most efficient Re content and thermal treatment for Mo-Re alloys to be used under irradiation condition.
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.
Ishii, Toshimitsu; Ooka, Norikazu; Hoshiya, Taiji; Kobayashi, Hideo*; Saito, Junichi; Niimi, Motoji; Tsuji, Hirokazu
Journal of Nuclear Materials, 307-311(Part.1), p.240 - 244, 2002/12
Times Cited Count：3 Percentile：23.39(Materials Science, Multidisciplinary)no abstracts in English
Iida, Toshiyuki*; Tanaka, Teruya*; Sato, Fuminobu*; Ochiai, Kentaro; Nishitani, Takeo
JAERI-Tech 2002-077, 38 Pages, 2002/09
no abstracts in English
Nishitani, Takeo; Shikama, Tatsuo*; Fukao, M.*; Reichle, R.*; Sugie, Tatsuo; Kakuta, Tsunemi; Kasai, Satoshi; Snider, R.*; Yamamoto, Shin
Fusion Engineering and Design, 56-57, p.905 - 909, 2001/10
Times Cited Count：21 Percentile：80.2(Nuclear Science & Technology)no abstracts in English
Sakamoto, Yukio; Yamaguchi, Yasuhiro
JAERI-Tech 2001-042, 29 Pages, 2001/06
JAERI-Tech-2001-042.pdf:1.79MB
no abstracts in English
Shimakawa, Satoshi; ; Nagao, Yoshiharu;
JAERI-Tech 95-023, 26 Pages, 1995/03
no abstracts in English
Yamaguchi, Yasuhiro
Journal of Nuclear Science and Technology, 31(11), p.1233 - 1235, 1994/11
Times Cited Count：0 Percentile：0.49(Nuclear Science & Technology)no abstracts in English
Hoshiya, Taiji; ; Kizaki, Minoru; *; Sudo, Kenji; ;
JAERI-M 89-205, 68 Pages, 1989/12
no abstracts in English
; *; *
Journal of Nuclear Materials, 144, p.205 - 206, 1987/00
Times Cited Count：2 Percentile：64.42(Materials Science, Multidisciplinary)no abstracts in English
; *
Radiation-Induced Changes in Microstructure, Part 1, p.27 - 37, 1987/00
no abstracts in English
; *
Journal of the Physical Society of Japan, 55(1), p.193 - 199, 1986/00
Times Cited Count：0 Percentile：0.01(Physics, Multidisciplinary)no abstracts in English
; ; ; ;
JAERI-M 85-088, 39 Pages, 1985/07
no abstracts in English
; Aruga, T.; *
Journal of Nuclear Materials, 136, p.159 - 163, 1985/00
Times Cited Count：15 Percentile：84.23(Materials Science, Multidisciplinary)no abstracts in English
*; ; *; *
Journal of Nuclear Materials, 135, p.32 - 39, 1985/00
Times Cited Count：4 Percentile：54.54(Materials Science, Multidisciplinary)no abstracts in English
; *
Radiat.Eff.Lett., 86, p.43 - 46, 1985/00
no abstracts in English
