Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Akutsu-Suyama, Kazuhiro*; Yamada, Norifumi*; Ueda, Yuki; Motokawa, Ryuhei; Narita, Hirokazu*
Applied Sciences (Internet), 12(3), p.1215_1 - 1215_10, 2022/02
Times Cited Count:1 Percentile:26.57(Chemistry, Multidisciplinary)no abstracts in English
Yamada, Hirokazu*; Sakurai, Shinji; Nakamura, Shigetoshi
FAPIG, (187), p.28 - 31, 2014/02
The activity of "Broader approach (BA)" is carried out under the Japan-EU collaboration towards the early realization of nuclear fusion energy, and the construction of JT-60SA (Super Advanced) has been started as a part of BA. Divertor target of JT-60 consisted of carbon fiber composite tiles bolted on heat sink plate. Due to extension of plasma heating power and pulse duration, divertor target for JT-60SA has to be changed to the concept of carbon fiber block jointed to cooling tube of Cu-alloy for active cooling. Brazing joint between the carbon block and cooling tube is easy to cause joint defect due to the difference in the coefficient of linear expansion of a material. The joint defect reduces heat removal performance of the target. On the occasion of the apparatus manufacture concerned, the structural improvement realized those problems. This paper reports the contents of a structural improvement in the divertor target manufacturing for JT-60SA, etc.
Tsuchiya, Kunihiko; Hoshino, Tsuyoshi; Kawamura, Hiroshi; Mishima, Yoshinao*; Yoshida, Naoaki*; Terai, Takayuki*; Tanaka, Satoru*; Munakata, Kenzo*; Kato, Shigeru*; Uchida, Munenori*; et al.
Nuclear Fusion, 47(9), p.1300 - 1306, 2007/09
Times Cited Count:23 Percentile:61.91(Physics, Fluids & Plasmas)no abstracts in English
Tsuchiya, Kunihiko; Hoshino, Tsuyoshi; Kawamura, Hiroshi; Mishima, Yoshinao*; Yoshida, Naoaki*; Terai, Takayuki*; Tanaka, Satoru*; Munakata, Kenzo*; Kato, Shigeru*; Uchida, Munenori*; et al.
Proceedings of 21st IAEA Fusion Energy Conference (FEC 2006) (CD-ROM), 8 Pages, 2007/03
no abstracts in English
Yamada, Hirokazu*; Kawamura, Hiroshi; Nagao, Yoshiharu; Takada, Fumiki; Kono, Wataru*
Journal of Nuclear Materials, 355(1-3), p.119 - 123, 2006/09
Times Cited Count:5 Percentile:36.24(Materials Science, Multidisciplinary)In this study, the bending properties of welding joint of irradiated material and un-irradiated material (irradiated/un-irradiated joints) were investigated using SS316LN-IG, which is the candidate material for the cooling pipe of ITER. The results of this study showed that the bending position of joints using un-irradiated material was un-irradiated part and that the bending position of irradiated/irradiated joints was fusion area or HAZ (heat affected zone). Although the bending position of joints was different bor the combination pattern between irradiated and un-irradiated materials, the bending strength of joint was almost same. Additionally, it is confirmed that bending strength did not depend on the combination pattern between the irradiated and un-irradiated materials, nor on the relationship between the heat input direction and the bending load direction.
Yamada, Hirokazu*; Tsuchiya, Kunihiko
FAPIG, (173), p.16 - 20, 2006/07
no abstracts in English
Yamada, Hirokazu*; Sato, Satoshi; Mori, Kensuke*; Nagao, Yoshiharu; Takada, Fumiki; Kawamura, Hiroshi
Fusion Engineering and Design, 81(1-7), p.631 - 637, 2006/02
Times Cited Count:1 Percentile:9.94(Nuclear Science & Technology)This study estimated the neutron irradiation effect with 1.5 dpa on the mechanical properties of the SS/SS HIP joint materials jointed in the standard HIP joint condition. Results of this study showed that the HIP process in the standard HIP condition could make SS/SS HIP joint material of which tensile properties was equivalent to that of the SS base material. In addition, the effect of surface roughness at the HIP joint material on the mechanical properties of SS/SS HIP joint material was estimated.
Yamada, Hirokazu; Kawamura, Hiroshi
JAEA-Technology 2005-001, 28 Pages, 2006/01
As a study about the joint technology of copper alloy and stainless steel for utilization as cooling piping in International Thermonuclear Experimental Reactor (ITER), AlO-dispersed strengthened copper or CuCrZr was joined to stainless steel by three kinds of joint methods (casting joint, brazing joint and friction welding method) for the evaluation of the neutron irradiation effect on joints. A neutron irradiation test was performed to three types of joints and each copper alloy. The average value of fast neutron fluence in this irradiation test was about 210n/m(E1MeV), and the irradiation temperature was about 130C. As post-irradiation examinations, tensile tests, hardness tests and observation of fracture surface after the tensile tests were performed. All type joints changed to be brittle by the neutron irradiation effect like each copper alloy material, and no particular neutron irradiation effect due to the effect of joint process was observed. On the casting and friction welding, hardness of copper alloy near the joint boundary changed to be lower than that of each copper alloy by the effect of joint procedure. However, tensile strength of joints was almost the same as that of each copper alloy before/after neutron irradiation. On the other hand, tensile strength of joints by brazing changed to be much lower than CuAl-25 base material by the effect of joint process before/after neutron irradiation. Results in this study showed that the friction welding method and the casting would be able to apply to the joint method of piping in ITER.
Yamada, Hirokazu*; Kawamura, Hiroshi; Tsuchiya, Kunihiko; Kalinin, G.*; Nagao, Yoshiharu; Takada, Fumiki; Nishikawa, Masahiro*
Journal of Nuclear Materials, 340(1), p.57 - 63, 2005/04
Times Cited Count:5 Percentile:35.66(Materials Science, Multidisciplinary)This study was performed to clear the effect of neutron re-irradiation on mechanical properties to welding material un-irradiated and irradiated stainless steel. The effect of re-irradiation to these weldaments were evaluated by tensile tests, metallographical observation and hardness test. The result of tensile tests shows that ultimate tensile strength of all joints specimen were almost similar, 0.2% yield strength and total elongation were depend on the irradiation damage and weldaments or not. Therefore, fracture mechanism was not change by re-irradiation. However, brittlement of material was depend on irradiation damage and the property of deformation was sensitive by the effect of irradiation damage or the effect of welding heat.
Yamada, Hirokazu*; Kawamura, Hiroshi; Tsuchiya, Kunihiko; Kalinin, G.*; Nagao, Yoshiharu; Sato, Satoshi; Mori, Kensuke*
Journal of Nuclear Materials, 335(1), p.33 - 38, 2004/10
Times Cited Count:8 Percentile:48.76(Materials Science, Multidisciplinary)no abstracts in English
Tsuchiya, Kunihiko; Kikukawa, Akihiro*; Hoshino, Tsuyoshi; Nakamichi, Masaru; Yamada, Hirokazu*; Yamaki, Daiju; Enoeda, Mikio; Ishitsuka, Etsuo; Kawamura, Hiroshi; Ito, Haruhiko; et al.
Journal of Nuclear Materials, 329-333(Part2), p.1248 - 1251, 2004/08
Times Cited Count:10 Percentile:55.63(Materials Science, Multidisciplinary)no abstracts in English
Yamada, Hirokazu*; Kawamura, Hiroshi; Tsuchiya, Kunihiko; Ishitsuka, Etsuo; Uchida, Munenori*; Akutsu, Yoichi; Motoki, Ryozo; Watanabe, Wataru; Hirata, Shogo*
JAERI-Tech 2004-036, 138 Pages, 2004/03
This document shows the model case concerned with the utilization of constructed facility for the construction of post irradiation examination facility for fusion blanket. In this report, the radioisotope application and development laboratory is considered as constructed facility for post irradiation examination facility and we planned to improve the radioisotope application and development laboratory to the facility of post irradiation examination for fusion material to reduce the construction fee for this facility and promotion of efficiency by concentration of any equipment for fusion material research.
Kikuchi, Taiji; Yamada, Hirokazu*; Saito, Takashi; Nakamichi, Masaru; Tsuchiya, Kunihiko; Kawamura, Hiroshi
JAERI-Tech 2004-026, 28 Pages, 2004/03
Iirradiation capsule for irradiation test of tritium breeder and inner capsule for pebble bed of tritium breeder is inserted. Post irradiation examination of tritium breeder will be performed after irradiation test. On cutting of irradiation capsule, sweep gas line should be sealed to prevent the tritium gas release or inflow of water to sweep gas line. However, general valve and plug cannot apply to sweep gas line sealing because of the effect of neutron irradiation or limited space in irradiation capsule. Therefore, sealing plug for sweep gas line sealing has to be developed. This report shows the development of sealing plug for sweep gas line sealing and operating procedure of sealing plug in irradiation capsule.
Uda, Minoru*; Iwadachi, Takaharu*; Uchida, Munenori*; Yamada, Hirokazu*; Nakamichi, Masaru*; Kawamura, Hiroshi
JAERI-Conf 2004-006, p.60 - 65, 2004/03
no abstracts in English
Yamada, Hirokazu*; Nagao, Yoshiharu; Kawamura, Hiroshi; Nakao, Makoto*; Uchida, Munenori*; Ito, Haruhiko
Fusion Engineering and Design, 69(1-4), p.269 - 273, 2003/09
Times Cited Count:14 Percentile:66.87(Nuclear Science & Technology)no abstracts in English
Kawamura, Hiroshi; Kikukawa, Akihiro*; Tsuchiya, Kunihiko; Yamada, Hirokazu*; Nakamichi, Masaru; Ishitsuka, Etsuo; Enoeda, Mikio; Ito, Haruhiko
Fusion Engineering and Design, 69(1-4), p.263 - 267, 2003/09
Times Cited Count:3 Percentile:25.75(Nuclear Science & Technology)no abstracts in English
Tsuchiya, Kunihiko; Alvani, C.*; Kawamura, Hiroshi; Yamada, Hirokazu*; Casado, S.*; Contini, V.*
Fusion Engineering and Design, 69(1-4), p.443 - 447, 2003/09
Times Cited Count:4 Percentile:31.59(Nuclear Science & Technology)no abstracts in English
Kawamura, Hiroshi; Ishitsuka, Etsuo; Tsuchiya, Kunihiko; Nakamichi, Masaru; Uchida, Munenori*; Yamada, Hirokazu*; Nakamura, Kazuyuki; Ito, Haruhiko; Nakazawa, Tetsuya; Takahashi, Heishichiro*; et al.
Nuclear Fusion, 43(8), p.675 - 680, 2003/08
Times Cited Count:28 Percentile:63.92(Physics, Fluids & Plasmas)no abstracts in English
Kawamura, Hiroshi; Takahashi, Heishichiro*; Yoshida, Naoaki*; Shestakov, V.*; Ito, Yoshio*; Uchida, Munenori*; Yamada, Hirokazu*; Nakamichi, Masaru; Ishitsuka, Etsuo
Fusion Engineering and Design, 61-62, p.391 - 397, 2002/11
Times Cited Count:40 Percentile:90.08(Nuclear Science & Technology)no abstracts in English
Kuroda, Toshimasa*; Sato, Kazuyoshi; Akiba, Masato; Ezato, Koichiro; Enoeda, Mikio; Osaki, Toshio*; Kosaku, Yasuo; Sato, Satoshi; Sato, Shinichi*; Suzuki, Satoshi*; et al.
JAERI-Tech 2002-044, 25 Pages, 2002/03
no abstracts in English