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Kondo, Hiroo; Furukawa, Tomohiro; Hirakawa, Yasushi; Nakamura, Kazuyuki; Ida, Mizuho; Watanabe, Kazuyoshi; Kanemura, Takuji; Wakai, Eiichi; Horiike, Hiroshi*; Yamaoka, Nobuo*; et al.
Nuclear Fusion, 51(12), p.123008_1 - 123008_12, 2011/12
Times Cited Count：39 Percentile：82.4(Physics, Fluids & Plasmas)The Engineering Validation and Engineering Design Activity (EVEDA) for the International Fusion Materials Irradiation Facility (IFMIF) is proceeded as one of the ITER Broader Approach (BA) activities. The EVEDA Li test loop (ELTL) is aimed at validating stability of the Li target and feasibility of a Li purification system as the key issues. In this paper, the design of the ELTL especially of a target assembly in which the Li target is produced by the contraction nozzle is presented.
Nakamura, Kazuyuki; Furukawa, Tomohiro; Hirakawa, Yasushi; Kanemura, Takuji; Kondo, Hiroo; Ida, Mizuho; Niitsuma, Shigeto; Otaka, Masahiko; Watanabe, Kazuyoshi; Horiike, Hiroshi*; et al.
Fusion Engineering and Design, 86(9-11), p.2491 - 2494, 2011/10
Times Cited Count：10 Percentile：60.88(Nuclear Science & Technology)In IFMIF/EVEDA, tasks for lithium target system are shared to 5 validation tasks (LF1-5) and a design task (LF6). The purpose of LF1 task is to construct and operate the EVEDA lithium test loop, and JAEA has a main responsibility to the performance of the Li test loop. LF2 is a task for the diagnostics of the Li test loop and IFMIF design. Basic research for the diagnostics equipment has been completed, and the construction for the Li test loop will be finished before March in 2011. LF4 is a task for the purification systems with nitrogen and hydrogen. Basic research for the purification equipment has been completed, and the construction of the nitrogen system for the Li test loop will be finished before March in 2011. LF5 is a task for the remote handling system with the target assembly. JAEA has an idea to use the laser beam for cutting and welding of the lip part of the flanges. LF6 is a task for the design of the IFMIF based on the validation experiments of LF1-5.
Ida, Mizuho; Fukada, Satoshi*; Furukawa, Tomohiro; Hirakawa, Yasushi; Horiike, Hiroshi*; Kanemura, Takuji*; Kondo, Hiroo; Miyashita, Makoto; Nakamura, Hiroo; Sugiura, Hirokazu*; et al.
Journal of Nuclear Materials, 417(1-3), p.1294 - 1298, 2011/10
Times Cited Count：4 Percentile：26.02(Materials Science, Multidisciplinary)Engineering Validation and Engineering Design Activities (EVEDA) of the International Fusion Materials Irradiation Facility (IFMIF) was started. As a Japanese activity for the target system, EVEDA Lithium Test Loop simulating hydraulic and impurity conditions of IFMIF is under design and preparation for fabrication. Feasibility of thermo-mechanical structure of the target assembly and the replaceable back-plate made of F82H (a RAFM) and 316L (a stainless steel) is a key issue. Toward final validation on the EVEDA loop, diagnostics applicable to a high-speed free-surface Li flow and hot traps to control nitrogen and hydrogen in Li are under tests. For remote handling of target assemblies and the replaceable back-plates activated up to 50 dpa/y, lip weld on 316L-316L by laser and dissimilar weld on F82H-316L are under investigation. As engineering design of the IFMIF target system, water experiments and hydraulic/thermo-mechanical analyses of the back-plate are going.
Kondo, Hiroo; Furukawa, Tomohiro; Hirakawa, Yasushi; Ida, Mizuho; Matsushita, Izuru*; Horiike, Hiroshi*; Kanemura, Takuji; Sugiura, Hirokazu*; Yagi, Juro*; Suzuki, Akihiro*; et al.
Journal of Engineering for Gas Turbines and Power, 133(5), p.052910_1 - 052910_6, 2010/12
Times Cited Count：7 Percentile：38.81(Engineering, Mechanical)As a major Japanese activity for the IFMIF/EVEDA, EVEDA Li Test Loop (ELTL) to simulate hydraulic and impurity conditions of IFMIF is under design and preparation for fabrication. Feasibility of hydraulic stability of the liquid Li target and the purification systems of hot traps are major key issues to be validated. This paper presents the current status of the design and construction of the EVEDA Li Test Loop. Detail designs of the loop components such as the target assembly, tanks, an electro-magnetic pump and flow meter and a cold trap for purification system are described in addition to the flow diagnostics system and the hot traps.
Kondo, Hiroo; Furukawa, Tomohiro; Hirakawa, Yasushi; Nakamura, Hiroo*; Ida, Mizuho; Watanabe, Kazuyoshi; Miyashita, Makoto*; Horiike, Hiroshi*; Yamaoka, Nobuo*; Kanemura, Takuji; et al.
Proceedings of 23rd IAEA Fusion Energy Conference (FEC 2010) (CD-ROM), 8 Pages, 2010/10
The Engineering Validation and Engineering Design Activity (EVEDA) for the International Fusion Materials Irradiation Facility (IFMIF) is proceeded as one of the ITER Broader Approach (BA) activities. The EVEDA Li test loop (ELTL) is aimed at validating stability of the Li target and feasibility of a Li purification system as the key issues. In this paper, the design of the ELTL especially of a target assembly in which the Li target is produced by the contraction nozzle is presented.
Kondo, Hiroo; Furukawa, Tomohiro; Hirakawa, Yasushi; Matsushita, Izuru*; Ida, Mizuho; Horiike, Hiroshi*; Kanemura, Takuji; Sugiura, Hirokazu*; Yagi, Juro*; Suzuki, Akihiro*; et al.
Proceedings of 18th International Conference on Nuclear Engineering (ICONE-18) (CD-ROM), 9 Pages, 2010/05
IFMIF is a neutron source aimed at producing an intense high energy neutron flux for testing candidate fusion reactor materials. Under Broader Approach activities, Engineering Validation and Engineering Design Activities (EVEDA) of IFMIF started on July 2007. Regarding to the lithium (Li) target facility, design and construction of EVEDA Li Test Loop is a major activity and is in progress. The detail design was started at the early 2009. Fabrication of the loop was started at middle of 2009, and completion is planned at the end of Feb. 2011.
Kondo, Hiroo; Furukawa, Tomohiro; Hirakawa, Yasushi; Iuchi, Hiroshi; Nakamura, Kazuyuki; Ida, Mizuho; Wakai, Eiichi; Watanabe, Kazuyoshi; Kanemura, Takuji; Horiike, Hiroshi*; et al.
no journal, ,
The International Fusion Materials Irradiation Facility (IFMIF) is a neutron source aimed at producing an intense high energy neutron flux for testing candidate materials to be used in the fusion demonstration reactor. Engineering Validation and Engineering Design Activities (EVEDA) on IFMIF started under Broader Approach. As a major Japanese activity for Li target tasks of EVEDA, EVEDA Li Test Loop is under construction. Feasibility of hydraulic stability of the Li target and purification systems of hot traps is major key issues to be validated. Toward the validation at the loop, laboratory-scale tests and design for diagnostics to the high-speed free-surface Li target and the hot traps to control nitrogen and hydrogen in Li are carried out along with the construction of the loop. Regarding to progress of the construction, all major components except a target assembly are installed in a mount of the loop. The construction is scheduled to be finished on Feb. 2011.
modelTakahashi, Momoko; Noguchi, Miho; Hirakawa, Hirokazu*; Okayasu, Ryuichi*
no journal, ,
Ionizing radiation has been widely used as a tool for tumor treatment. However, there are still difficulties to treat the solid tumor with only irradiation. Several studies have been shown that the combination therapy using both X-irradiation and antitumor drug is more effective to tumor compared with X-irradiation only. Previously Noguchi et al. showed the Hsp90 inhibitor 17AAG induced tumor cell death effectively with X-irradiation. Hsp90 is the enzymes activated by cellular stress and activates several tumor-related genes. To clarify whether or not the combination therapy of carbon ion beam and 17AAG is effective to solid tumors, we tested the growth of solid tumor with the combination of X-irradiation and 17AAG and compared the results from 
study.
Okayasu, Ryuichi*; Hirakawa, Hirokazu*; Noguchi, Miho; Yu, D.*; Takahashi, Momoko; Hirayama, Ryoichi*; Fujimori, Akira*
no journal, ,
17AAG, an Hsp90 inhibitor was shown to radiosensitize certain human tumor cells exposed to X-rays, while this sensitization was not clearly observed in normal human cells. The mechanism of this was suggested to come from inhibition of DNA double strand break (DSB) repair, particularly impairment of homologous recombination repair (HRR) pathway by this drug (Noguchi et al 2006). Key proteins associated with HRR seem to be affected by this inhibitor. To our surprise, tumor radiosensitization with 17AAG was also observed in cells exposed to high LET carbon ions (70 kev/um). Independently we also found that knockdown of BRCA2, a key HRR protein significantly radiosensitized human tumor cells. These results indicate that there seem to be a radio-sensitization mechanism associated with the combination of HRR inhibition and high LET radiation, and this may occur particularly in S-phase cells. Furthermore, we also used mouse xenograft model to examine the combined effect of 17AAG and high LET carbon irradiation. For this purpose, SQ5 human lung tumor cells were implanted on the leg of nude mice and the tumor growth was observed in the combined treatment as compared with radiation or drug treatment alone. Our preliminary results indicate that tumor growth was more inhibited in the 17AAG and carbon irradiation than carbon or 17AAG treatment alone. These data suggest that an effective tumor control might be obtained by combining an HRR inhibitor with high LET carbon irradiation.
Furukawa, Tomohiro; Kondo, Hiroo; Hirakawa, Yasushi; Kanemura, Takuji; Nakamura, Kazuyuki; Wakai, Eiichi; Sugiura, Hirokazu*; Yamaoka, Nobuo*; Suzuki, Sachiko*; Hoashi, Eiji*; et al.
no journal, ,
This paper describes the metallurgical analysis of lithium test assembly used for lithium flow experiment at Osaka University.
Kanemura, Takuji; Kondo, Hiroo; Sugiura, Hirokazu*; Hoashi, Eiji*; Yoshihashi, Sachiko*; Muroga, Takeo*; Furukawa, Tomohiro; Hirakawa, Yasushi; Wakai, Eiichi; Horiike, Hiroshi*
no journal, ,
Application studies of liquid metal (LM) wall jets are progressing in nuclear fusion researches. Examples are LM diverters or the Li target of the International Fusion Materials Irradiation Facility (IFMIF). It is important to understand flow characteristics based on measurement in order to judge whether a LM wall jet is feasible as a coolant or a nuclear target. To do so, diagnostics applicable to LM must be developed. The authors started researches on the flow characteristics of the IFMIF Li target in 2002. The diagnostics we developed are a high-speed video camera for visualization of free surface, a contact-type liquid level sensor and a laser probe method for measurement of amplitude of free-surface waves, etc. We have succeeded in understanding the flow characteristics of the Li wall jet by measuring them. The diagnostics we developed are applicable to other LM free-surface flows, and the flow characteristics we obtained are valuable as fundamental data for other LM flows.
