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Department of Materials Science; Department of Fusion Engineering Research (Tokai Site)
JAERI-Review 2004-018, 97 Pages, 2004/08
JAERI-Review-2004-018.pdf:18.92MB
Extensive efforts for evaluating the irradiation performances of a reduced activation ferritic/martensitic steel (RAF/M) of F82H* and other several RAF/Ms have been made in recent several years. They are, examinations of the effects of neutron irradiation on (1) Ductile to brittle transition temperature (DBTT) up to a damage level of 20 dpa to explore lower temperature limit, (2) Enhanced He effect on DBTT shift for Ni/B doped heats (isotopic tailoring method was used for B doping), (3) Susceptibility to environmentally assisted cracking by the slow strain rate tensile tests (SSRT) in a high temperature pressurized water and (4) Flow stress-plastic strain relation obtained by measuring the profile of the specimen during tensile testing, together with the activities of (5) the development of the test methods after neutron irradiation and (6) other supporting researches. Results are summarized in the present report. They clearly indicate the good applicability of RAF/Ms to fusion machines.
Sugimoto, Masayoshi; Takeuchi, Hiroshi
Journal of Nuclear Materials, 329-333(Part1), p.198 - 201, 2004/08
Times Cited Count：4 Percentile：29.26(Materials Science, Multidisciplinary)IFMIF is an accelerator-based intense neutron source for developing fusion reactor materials, and a stable and continuous operation is a primary importance. The radioactivity produced by the beam loss prolongs the cooling time before maintenance and results in a potential limit to the availability. The materials selection is important for minimizing the total radioactivity produced by ion beam and neutrons, after about one day cooling time in advance of hands-on maintenance. For the major parts, Cu for cavity and Al for beam duct, the beam loss needs to be reduced below 5nA/m. Such a low loss can be realized by suppressing the beam halo and by using the scrapers made from high-Z material, Ta, to cut the tail of beam. The insertion points of the scrapers are determined from the beam size evolution along the accelerator and the available room for radiation shielding around them. The reduction of the radioactivity after the whole lifetime of facility is another issue and the possibility to use low activation materials coating for cavity and beam duct is presented.
Konishi, Satoshi*; Kimura, Akihiko*; Akiba, Masato; Nakamura, Hiroo; Nagasaka, Takuya*; Muroga, Takeo*; Hasegawa, Akira*; Matsui, Hideki*
Nihon Genshiryoku Gakkai-Shi, 46(5), p.311 - 322, 2004/05
no abstracts in English
Wakai, Eiichi; Kikuchi, Kenji; Yamamoto, Shunya; Aruga, Takeo; Ando, Masami; Tanigawa, Hiroyasu; Taguchi, Tomitsugu; Sawai, Tomotsugu; Oka, Keiichiro*; Onuki, Somei*
Journal of Nuclear Materials, 318, p.267 - 273, 2003/05
Times Cited Count：70 Percentile：96.81(Materials Science, Multidisciplinary)no abstracts in English
Yamada, Reiji; Igawa, Naoki; Taguchi, Tomitsugu; Jitsukawa, Shiro
Journal of Nuclear Materials, 307-311(Part2), p.1215 - 1220, 2002/12
Times Cited Count：24 Percentile：80.63(Materials Science, Multidisciplinary)SiC fiber-reinforced SiC composites (SiC/SiC) are considered an advanced structural material for blanket modules of a fusion reactor, which requires high thermal conductivity in order to keep thermal stresses in the material lower than the allowable design stress. The sintered SiC fiber recently developed has obtained high thermal conductivity, so it is highly expected that sintered SiC fiber-reinforced SiC/SiC composites would also show high thermal conductivity. In this study several types of 3D SiC/SiC composites were fabricated by either CVI or PIP method. The results of the thermal conductivity measurements show that the maximum thermal conductivity at room temperature was about 60 W/mK for CVI composites or 25W/mK for PIP ones. These values are considerably higher than those of non-sintered SiC fiber reinforced SiC/SiC composites, which indicates a possibility that the developed materials would be promising. The FEM thremal analysis shows the good agreement between the caluculated and experimental results.
Nakamura, Hiroo; Burgazzi, L.*; Cevolani, S.*; Dell'Ocro, G.*; Fazio, C.*; Giusti, D.*; Horiike, Hiroshi*; Ida, Mizuho*; Kakui, Hideo*; Loginov, N.*; et al.
Journal of Nuclear Materials, 307-311(2), p.1675 - 1679, 2002/12
no abstracts in English
Ehrlich, K.*; Bloom, E. E.*; Kondo, Tatsuo
Journal of Nuclear Materials, 283-287(1), p.79 - 88, 2000/12
Times Cited Count：86 Percentile：97.75(Materials Science, Multidisciplinary)no abstracts in English
Ishii, Toshimitsu; Omi, Masao; Saito, Junichi; Hoshiya, Taiji; Ooka, Norikazu; Jitsukawa, Shiro; Eto, Motokuni
Journal of Nuclear Materials, 283-287(Part.2), p.1023 - 1027, 2000/12
Times Cited Count：12 Percentile：62.16(Materials Science, Multidisciplinary)no abstracts in English
Nakamura, Hiroo; Morimoto, Yuichi*; Ochiai, Kentaro; Sugimoto, Masayoshi; Nishitani, Takeo; Takeuchi, Hiroshi
JAERI-Review 2000-016, 47 Pages, 2000/10
JAERI-Review-2000-016.pdf:3.15MB
no abstracts in English
Omi, Masao; Saito, Junichi; ; Hoshiya, Taiji; Jitsukawa, Shiro
JAERI-Conf 99-009, p.151 - 162, 1999/09
no abstracts in English
Jitsukawa, Shiro; Naito, Akira; *
Journal of Nuclear Materials, 271-272, p.87 - 91, 1999/00
Times Cited Count：6 Percentile：45.57(Materials Science, Multidisciplinary)no abstracts in English
Noda, Kenji; Ehrlich, K.*; Jitsukawa, Shiro; Moeslung, A.*; Zinkle, S.*
Journal of Nuclear Materials, 258(263), p.97 - 105, 1998/10
Times Cited Count：20 Percentile：81.49(Materials Science, Multidisciplinary)no abstracts in English
Shiba, Kiyoyuki; Hishinuma, Akimichi
Purazuma, Kaku Yugo Gakkai-Shi, 74(5), p.436 - 441, 1998/05
no abstracts in English
Arai, Taketoshi; Ito, Hisayoshi; Terai, Takayuki*; Ishino, Shiori*
ECN-R--98-005, p.113 - 124, 1998/00
no abstracts in English
O sintered pelletsYamaki, Daiju; Tanifuji, Takaaki; Noda, Kenji
Fusion Engineering and Design, 39-40, p.723 - 729, 1998/00
Times Cited Count：2 Percentile：24.49(Nuclear Science & Technology)no abstracts in English
; Kiuchi, Kiyoshi; *; *; *
Journal of Nuclear Materials, 258-263, p.1066 - 1072, 1998/00
Times Cited Count：0 Percentile：0.01(Materials Science, Multidisciplinary)no abstracts in English
March 1996JAERI-Review 96-017, 277 Pages, 1997/01
JAERI-Review-96-017.pdf:12.81MB
no abstracts in English
Kudo, Hisaaki; Kasai, Noboru; Sasuga, Tsuneo; Seguchi, Tadao
Irradiation of Polymers; Fundamentals and Technological Applications (ACS Symp. Series 620), 0, p.313 - 322, 1996/00
no abstracts in English
Sugimoto, Masayoshi; *; Kinsho, Michikazu; M.A.Chernogubovsky*; Maekawa, Hiroshi
NUP-A-96-10, 0, p.89 - 91, 1996/00
no abstracts in English
M.A.Chernogubovsky*
NUP-A-96-10, 0, p.325 - 327, 1996/00
no abstracts in English
