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Sun, Haomin; Kunugi, Tomoaki*; Yokomine, Takehiko*; Shen, X.*; Hibiki, Takashi*
Experimental Thermal and Fluid Science, 154, p.111171_1 - 111171_24, 2024/05
Hasemi, Hiroyuki; Takahashi, Ryuta*; Yamauchi, Yasuhiro*; Ishikado, Motoyuki*; Kawamura, Seiko; Komine, Ryota
JPS Conference Proceedings (Internet), 41, p.011003_1 - 011003_5, 2024/03
Sun, Haomin; Kunugi, Tomoaki*; Yokomine, Takehiko*; Shen, X.*; Hibiki, Takashi*
International Journal of Heat and Mass Transfer, 211, p.124214_1 - 124214_17, 2023/09
Times Cited Count：1 Percentile：0(Thermodynamics)Okazaki, Soichiro*; Ezure, Toshiki; Ohshima, Hiroyuki; Kawara, Zensaku*; Yokomine, Takehiko*; Kunugi, Tomoaki*
Proceedings of 10th Pacific Symposium on Flow Visualization and Image Processing (PSFVIP-10), 8 Pages, 2015/06
A visualization study is performed under suction vortex geometry in water. In the experiment, the shear-sensitive liquid crystal coating (SSLCC) is applied to grasp the distribution of wall shear stress under the suction votex flow. As the result, it was found that the peak value of wall shear stress is appeared at the center and edge of the projected area of suction pipe. The non-dimensional profile of wall shear stress obtained by suction vortex flow experiment agrees well with that of numerical simulation.
Wakai, Eiichi; Kondo, Hiroo; Kanemura, Takuji; Hirakawa, Yasushi; Furukawa, Tomohiro; Hoashi, Eiji*; Fukada, Satoshi*; Suzuki, Akihiro*; Yagi, Juro*; Tsuji, Yoshiyuki*; et al.
Proceedings of Plasma Conference 2014 (PLASMA 2014) (CD-ROM), 2 Pages, 2014/11
In the IFMIF/EVEDA (International Fusion Materials Irradiation Facility/ Engineering Validation and Engineering Design Activity), the validation tests of the EVEDA lithium test loop with the world's highest flow rate of 3000 L/min was succeeded in generating a 100 mm-wide and 25 mm-thick free-surface lithium flow steadily under the IFMIF operation condition of a high-speed of 15 m/s at 250
C in a vacuum of 10 
Pa. Some excellent results of the recent engineering validations including lithium purification, lithium safety, and remote handling technique were obtained, and the engineering design of lithium facility was also evaluated. These results will advance greatly the development of an accelerator-based neutron source to simulate the fusion reactor materials irradiation environment as an important key technology for the development of fusion reactor materials.
Yamamoto, Michiyoshi; Arbeiter, F.*; Yokomine, Takehiko*; Wakai, Eiichi; Theile, J.*; Garcia, A. S.*; Rapisarda, D. S.*; Casal, N. I.*; Mas, A. S.*; Gouat, P.*; et al.
Fusion Engineering and Design, 88(6-8), p.746 - 750, 2013/10
Times Cited Count：14 Percentile：72.14(Nuclear Science & Technology)Under Broader Approach (BA) Agreement between EURATOM and Japan, IFMIF/EVEDA (International Fusion Materials Irradiation Facility/Engineering Validation and Engineering Design Activities) has been performed since the middle of 2007. The present EVEDA phase aims at producing a detailed, compete and fully integrated engineering design of IFMIF. The deivery of the Intermediate IFMIF engineering design report is foreseen mid-2013. The main function of the IFMIF is to provide the materials database for the design and licensing of DEMO reactor and further fusion rectors from the material sets irradiated in High Flux Test Modules (HFTM, Startup Monitoring Module), Medium Flux Test Modules (Creep Fatigues Test Module, Tritium Release Test Module, Liquid Breeder Validation Module) and Low Flux Test Modules of IFMIF. This paper is summarizing the current progress of the engineering design of the test modules within the IFMIF/EVEDA project.
Wakai, Eiichi; Kim, B. J.; Nozawa, Takashi; Kikuchi, Takayuki; Hirano, Michiko*; Kimura, Akihiko*; Kasada, Ryuta*; Yokomine, Takehiko*; Yoshida, Takahide*; Nogami, Shuhei*; et al.
Proceedings of 24th IAEA Fusion Energy Conference (FEC 2012) (CD-ROM), 6 Pages, 2013/03
Wakai, Eiichi; Kikuchi, Takayuki; Yokomine, Takehiko*; Yamamoto, Michiyoshi; Soldaini, M.*; Polato, A.*
Fusion Science and Technology, 62(1), p.246 - 251, 2012/07
Times Cited Count：6 Percentile：43.52(Nuclear Science & Technology)Wakai, Eiichi; Yamamoto, Michiyoshi; Molla, J.*; Yokomine, Takehiko*; Nogami, Shuhei*
Fusion Engineering and Design, 86(6-8), p.712 - 715, 2011/10
Times Cited Count：6 Percentile：44.28(Nuclear Science & Technology)The main purpose of present phase of IFMIF/EVEDA (International Fusion Materials Irradiation Facility/Engineering Validation and Engineering Design Activities) is to produce a detailed report of IFMIF engineering design with the integrated design of all facilities in IFMIF. The main function of the IFMIF is to give the demanded design database for the licensing of DEMO reactors and further reactors, and it is achieved from the materials data set obtained from the high, medium, and low flux test modules (HFTM, MFTM and LFTM) of IFMIF. In the evaluation using small specimens, developments and guidelines of small specimen test technique or technology (SSTT) are also demanded for the achievements. This paper is summarized about the design plan and requirements in these test modules and testing items in IFMIF.
Wakai, Eiichi; Kikuchi, Takayuki; Kogawara, Takafumi; Kimura, Haruyuki; Yokomine, Takehiko*; Kimura, Akihiko*; Nogami, Shuhei*; Kurishita, Hiroaki*; Saito, Masahiro*; Nishimura, Arata*; et al.
Proceedings of 23rd IAEA Fusion Energy Conference (FEC 2010) (CD-ROM), 6 Pages, 2011/03
Japanese activities of test facilities in IFMIF-EVEDA (International Fusion Materials Irradiation Facility-Engineering Validation and Engineering Design Activities) project have three subjects of engineering design of post irradiation examination (PIE) facilities, small specimen test technique (SSTT), and engineering design of high flux test module (HFTM), and this paper is summarized about present status. Functional analysis and design of 2-D and 3-D models of PIE facility were performed. In HFTM, as materials of heater, W-3Re alloy and/or SiC/SiC composite were selected in the points of high temperature materials, fabrication technology and some suitable properties such as resistance of thermal shock, high temperature re-crystallization, ductility, resistance of irradiation degradation, and low-activation. In SSTT, a test machine of fracture toughness was designed and developed for small specimens with 10 mm square, and it had high accuracy controllability for stress and displacement.
(rusty-rock lichen) mycobiontFujii, Hiromitsu*; Hara, Kojiro*; Komine, Masashi*; Ozaki, Takuo; Onuki, Toshihiko; Yamamoto, Yoshikazu*
Journal of Nuclear and Radiochemical Sciences, 6(1), p.115 - 118, 2005/07
We studied the association of a Cu tolerant mycobiont, Tremolecia atrata (rusty-rock lichen) with Cu. T. atrata mycobiont cell aggregates, which grew into a sperical shape, rapidly absorbed Cu into their inner and outer parts. The EDS/SEM study showed that Cu was more highly accumulated in the inner part than the outer part of the aggregates. The XANES study revealed that the Cu absorbed by the T. atrata mycobiont was both monovalent and divalent. These results suggested that the T. atrata mycobiont's high tolerance to Cu is attributable to its ability to store Cu(I) inside the cytoplasm and to adsorb Cu(II) on the cell wall.
Noguchi, Masayasu*; Komine, Takashi*; Kamioki, Hiroshi; Matsumoto, Mikio*
Radioisotopes, 50(7), p.301 - 307, 2001/07
no abstracts in English
Tsuji, Hiroshi; Okuno, Kiyoshi*; Thome, R.*; Salpietro, E.*; Egorov, S. A.*; Martovetsky, N.*; Ricci, M.*; Zanino, R.*; Zahn, G.*; Martinez, A.*; et al.
Nuclear Fusion, 41(5), p.645 - 651, 2001/05
Times Cited Count：57 Percentile：83.02(Physics, Fluids & Plasmas)no abstracts in English
Kubo, Hiroatsu*; Omine, T.*; Yoshida, Kiyoshi
JAERI-Tech 98-050, 69 Pages, 1998/11
no abstracts in English
Sawada, Kota; Maruyama, Koichi; Komine, Ryuji; Nagae, Yuji
PNC TN9410 98-018, 32 Pages, 1998/02
Mod.9Cr-1Mo steel has a martensitic lath structure. Recovery of the lath structure takes place hl the course of creep. Microstructural degradation due to the recovery results in the acceleration of creep rate and the subsequent failure of a specimen. Change of lath width during creep of the steel was quantitatively investigated to propose a residual life assessment methodology based on the recovery process. Since the steel was tempered at 1053K, the lath structure is thermally stable at the testing temperatures (848K
923K). However, recovery of lath structure readily takes place during creep, indicating that the recovery is induced by creep deformation. Lath width 
increases with creep strain and saturates to a value 
determined by creep stress. The increase of is faster at a higher stress and temperature. A normalized ehange in lath width, 
/, was introduced to explain the variation of lath growth rate with creep stress and temperature. is the change in lath width from the initial value 
, and is the difference between and . / is uniquely related to creep strain 
and the relationship is independent of creep stress as well as ereep temperature. This /- relationship obtained by an accelerated creep test at a higher temperature or stress is applicable to any creep condition including service conditions of engineering plants. Creep strain can be evaluted from the measurement of / based on the /- relationship. A creep curve under any creep condition can readily be calculated by creep data of the steel. Combining these information one can assess residual life of a structural component made of the steel.
Sawada, Kota; Maruyama, Koichi; Komine, Ryuji; Nagae, Yuji
PNC TN9410 97-035, 41 Pages, 1997/03
Several microstructural changes take place in a material during the course of creep. These changes can be a measure of creep life consumption. In this paper, microstructural changes in Mod.9Cr-1Mo steel were studied in order to examine their ability as the measure of crecp life consumption. Macroscopic structural changes, such as void growth, rotation of lath structure toward the tensile axis and elongation of grains, are evident only in the necked portion of ruptured specimens. These macroscopic structural changes are not useful for creep life assessment. Lath width increases and dislocation density within lath decreases with increasing creep duration. These changes in dislocation substructure start in the early stage of creep life, and cause the increase of strain rate in the tertiary creep stage. The lath width and the dislocation density reach a stationary value before rupture. The stationary values are independent of temperature, and uniquely related to creep stress normalized by shear modulus. The extent of these microstructural changes are greater at lower stresses under which the material is practically used. These facts suggest that the lath width and the dislocation density within lath can be a useful measure of creep life consumption. Hardness of crept specimens is closely related to the lath width and the dislocation density within lath. The changes of these microstructural features can be evaluated by the measurement of handness.
Sawada, Kota*; Maruyama, Koichi*; Komine, Ryuji; Nagae, Yuji
Tetsu To Hagane, 83(7), p.466 - 471, 1997/00
None
Watashi, Katsumi; Aoto, Kazumi; Aoki, M; Komine, Ryuji; Ito, Takushi; Hasebe, Shinichi; Kato, Shoichi; Koi, Mamoru; Wada, Yusaku
PNC TN9410 93-142, 120 Pages, 1993/06
Much progress has been made in improving established creep properties of Type 316 stainless steel and to develop a new structural material named "FBR Grade Type 316 Stainless Steel", 316FR, with superior creep properties. This report includes a draft of Material Strength Standard of 316FR and its interpretation on the basis of the major result of research and development conducted so far. The draft includes identical items described in the "Standards for the Strength of Materials" for Monju, and was carefully prepared to have an identical style for convenience in design evaluation. Creep damage evaluation diagrams, which are depicted in the "Structural Design Guide for Class 1 Components of Prototype Fast Breeder Reactor for Elevated Temperature Service" (ETSDG) for individual materials, are also included in this report.
Ara, Katsuyuki; Yagi, Hideyuki; Omura, Toshitsugu*; Ikeda, Hideo*; Omine, Megumi*; Moriyasu, Masaharu*
Kenkyukai Shiryo, p.57 - 65, 1987/06
no abstracts in English
Ara, Katsuyuki; Yagi, Hideyuki; *; Omura, Toshitsugu*; Omine, Megumi*; Moriyasu, Masaharu*; Ikeda, Hideo*
MAG-87-19, p.47 - 55, 1987/00
no abstracts in English
