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Ota, Kyugo*; Watabe, Yuki*; Haga, Yoshinori; Iesari, F.*; Okajima, Toshihiko*; Matsumoto, Yuji*
Symmetry (Internet), 15(8), p.1488_1 - 1488_13, 2023/07
Times Cited Count：1 Percentile：66.09(Multidisciplinary Sciences)Tateishi, Ryo*; Shimada, Koji; Iwamori, Akiyuki*; Wada, Shinya*; Seno, Shotaro*; Nagata, Ken*
Chishitsugaku Zasshi (Internet), 128(1), p.63 - 64, 2022/04
The Tsuruga Fault is an active right-lateral strike-slip fault that is about 20 km in length and distributed in the northeast-southwest direction from the eastern part of Tsuruga City to the southern part of Mihama Town, Fukui Prefecture. The Tsuruga fault borders the Jurassic accretionary complex (mixed rock) and the late Cretaceous granite around the Oritodani area in the Shinjo district of Mihama-cho. Lateral bendings of valleys along the fault in this area are clear geomorphological signatures of fault activity. We briefly report newly found multiple fault outcrops at these bending points with photos of them. This research is the result of joint research by Kansai Electric Power Company, University of Toyama, and JAEA.
hydrogen partitioning controlToda, Hiroyuki*; Yamaguchi, Masatake; Matsuda, Kenji*; Shimizu, Kazuyuki*; Hirayama, Kyosuke*; Su, H.*; Fujihara, Hiro*; Ebihara, Kenichi; Itakura, Mitsuhiro; Tsuru, Tomohito; et al.
Tetsu To Hagane, 105(2), p.240 - 253, 2019/02
Times Cited Count：0 Percentile：0(Metallurgy & Metallurgical Engineering)no abstracts in English
Matsumoto, Yuji*; Haga, Yoshinori; Tateiwa, Naoyuki; Yamamoto, Etsuji; Fisk, Z.*
Journal of the Physical Society of Japan, 87(2), p.024706_1 - 024706_4, 2018/02
Times Cited Count：0 Percentile：0(Physics, Multidisciplinary)Kobayashi, Kazuhiro; Torikai, Yuji*; Saito, Makiko; Alimov, V. Kh.*; Miya, Naoyuki; Ikeda, Yoshitaka
Fusion Science and Technology, 67(2), p.428 - 431, 2015/03
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)Disassembly of the JT-60U torus was started in 2010 after 18 years deuterium operations. In the disassembly of the JT-60U torus, tritium retention in the vacuum vessel of the JT-60U is one of the most important safety issues for the fusion reactor. It was very important to study the tritium behavior in Inconel 625 from viewpoint of the clearance procedure in the future plan. After the tritium release for about 1 year at 298 K, the residual tritium in the specimen was released by heating up to 1073 K, and then the residual tritium in the specimen was measured by chemical etching method. Most of the chemical form of the released tritium was HTO. The contaminated specimen by tritium was released continuously the diffusible tritium under the ambient condition. In the tritium release experiment, most of tritium in the specimen was released during 1 year.
Dorn, C. K.*; Tsuchiya, Kunihiko; Takemoto, Noriyuki; Ito, Masayasu; Hori, Junichi*; Chekushina, L.*; Hatano, Yuji*; Chakrov, P.*; Kawamura, Hiroshi
Proceedings of 6th International Symposium on Material Testing Reactors (ISMTR-6) (Internet), 9 Pages, 2013/10
no abstracts in English
Ito, Masayasu; Kitagishi, Shigeru; Hanawa, Yoshio; Tsuchiya, Kunihiko; Hatano, Yuji*; Matsuyama, Masao*; Nagasaka, Takuya*; Hishinuma, Yoshimitsu*
Annual Report of National Institute for Fusion Science; April 2011 - March 2012, P. 535, 2012/12
Beryllium has been utilized as a moderator and/or reflector in a number of material testing reactors. Beryllium is also supposed to be widely used in fusion reactors as neutron multiplier and protective walls of plasma facing components. It is important to perform the characterization of the different grade beryllium such as the productivity, mechanical and chemical properties and the interaction under water and/or gas environment. In this study, three kinds of beryllium (S-200F, S-65H, I-220H) were prepared, and corrosion test and surface analysis of these beryllium samples were carried out for life time expansion under pure water. As a result, the surface change of each Be sample was observed by the corrosion test and influenced by the content of BeO and the grain size.
Dorn, C. K.*; Tsuchiya, Kunihiko; Hatano, Yuji*; Chakrov, P.*; Kodama, Mitsuo*; Kawamura, Hiroshi
Proceedings of 5th International Symposium on Material Testing Reactors (ISMTR-5) (Internet), 9 Pages, 2012/10
The JMTR has used beryllium reflector since it began operation in 1968. Beryllium has been used as the reflector element material in the reactor, specifically S-200F structural grade beryllium in JMTR. As a part of the reactor upgrade, the Japan Atomic Energy Agency (JAEA) has carried out the cooperation experiments to extend the operating lifetime of the beryllium reflector elements. Thus, three kinds of beryllium metals such as S-200F, S-65H and I-220H were selected at the viewpoints of production methods, impurities and grain size of beryllium starting powders, mechanical properties. Now, data of the material properties and interaction between pure water and these beryllium grades are accumulated under un-irradiated. Additionally, irradiation tests have been prepared and development of PIE technologies has been performed. In this paper, the results of various properties and irradiation test plan for lifetime expansion of beryllium are described for material testing reactors.
Dorn, C. K.*; Tsuchiya, Kunihiko; Hatano, Yuji*; Chakrov, P.*; Kodama, Mitsuo*; Kawamura, Hiroshi
JAEA-Conf 2011-003, p.93 - 97, 2012/03
The JMTR has used beryllium reflector since it began operation in 1968. Beryllium has been used as the reflector element material in the reactor, specifically S-200F structural grade beryllium in JMTR. As a part of the reactor upgrade, the Japan Atomic Energy Agency (JAEA) has carried out the cooperation experiments to extend the operating lifetime of the beryllium reflector elements. Thus, three kinds of beryllium metals such as S-200F, S-65H and I-220H were selected at the viewpoints of production methods, impurities and grain size of beryllium starting powders, mechanical properties. Now, data of the material properties of these beryllium grades are accumulated under un-irradiated and irradiated conditions. In this paper, the results of various properties and irradiation test plan for lifetime expansion of beryllium are described for material testing reactors.
Yokoyama, Takeshi*; Mizuguchi, Mineyuki*; Nabeshima, Yuko*; Kusaka, Katsuhiro*; Yamada, Taro*; Hosoya, Takaaki*; Ohara, Takashi*; Kurihara, Kazuo; Tomoyori, Katsuaki*; Tanaka, Ichiro*; et al.
Journal of Structural Biology, 177(2), p.283 - 290, 2012/02
Times Cited Count：48 Percentile：83.41(Biochemistry & Molecular Biology)Tsuchiya, Kunihiko; Kitagishi, Shigeru; Ito, Masayasu; Hanawa, Yoshio; Hatano, Yuji*; Matsuyama, Masao*; Nagasaka, Takuya*; Hishinuma, Yoshimitsu*
Annual Report of National Institute for Fusion Science; April 2010 - March 2011, P. 545, 2011/11
no abstracts in English
Tsuchiya, Kunihiko
Heisei-22-Nendo Toyama Daigaku Kyodo Kenkyu Seika Hokokusho, p.31 - 32, 2011/06
no abstracts in English
Division of Fusion Energy Technology
JAEA-Review 2009-032, 100 Pages, 2009/11
JAEA-Review-2009-032.pdf:21.88MB
The Division of Fusion Energy Technology of the Fusion Research and Development Directorate is carrying out cooperating researches with universities, research institutes and industries using five fusion engineering facilities; Caisson Assembly for Tritium Safety Study (CATS), Fusion Neutronics Source (FNS), JAEA Electron Beam Irradiation System (JEBIS), RF Test Stand (RFTS). In the fiscal year 2007 (from April 1, 2008 to March 31, 2009), 19 activities were carried out as the cooperating researches. This report reviews the results of 8 activities which were completed in the fiscal year 2008.
Shu, Wataru; Matsuyama, Masao*; Suzuki, Takumi; Nishi, Masataka
Fusion Engineering and Design, 81(1-7), p.803 - 808, 2006/02
Times Cited Count：12 Percentile：63.1(Nuclear Science & Technology)In this work, the counting rate of bremsstrahlung X-rays was measured against the tritium partial pressure in two mixed gases diluted with helium or hydrogen. Subsequently, the counting rate was also measured against total pressure for T
-He mixture at a constant tritium partial pressure of 93 Pa or 1.3 kPa. For both mixtures, the counting rate of bremsstrahlung X-rays decreased linearly with the decreasing tritium partial pressure when the total pressure is smaller than about 10 kPa. At higher pressures, the deviation from the linear relationship appeared due to absorption of beta-particles in the gas phase, and this can be decreased by some commercially available arrangements. On the other hand, the counting rate of bremsstrahlung X-rays depended only upon the tritium partial pressure when absorption of beta-particles in the gas phase is negligibly small. The results obtained show that this method of tritium monitoring is very promising for the fuel processing system of fusion reactors, especially for tritium recovery system of breeding blankets.
Shu, Wataru; Matsuyama, Masao*; Suzuki, Takumi; Nishi, Masataka
Nuclear Instruments and Methods in Physics Research A, 521(2-3), p.423 - 429, 2004/04
Times Cited Count：19 Percentile：75.21(Instruments & Instrumentation)The characteristics of a promising tritium process monitor using a NaI(Tl) scintillation detector for X-rays was examined with pure tritium in a concentration range of 10
-10
GBq/m
. The measurement of tritium concentration was achieved by observing the bremsstrahlung X-rays generated by the interaction between the tritium beta particles and a gold film coated on the inside of beryllium window. A linear relationship between the counting rate of bremsstrahlung X-rays and the tritium concentration was observed for tritium concentration range of 10-10
GBq/m, and the sensitivity of the monitor was determined to be about 0.5GBq/m per cpm in this concentration range. The characteristics were also investigated with a tritium mixture diluted with deuterium (atomic ration of tritium: 0.83%), and He release from a uranium bed during heating was traced with this monitor.
Nakamura, Hirofumi; Hatano, Yuji*
no journal, ,
no abstracts in English
Dorn, C. K.*; Tsuchiya, Kunihiko; Hatano, Yuji*; Chakrov, P.*; Kodama, Mitsuhiro*; Kawamura, Hiroshi
no journal, ,
no abstracts in English
Ito, Masayasu; Takeuchi, Tomoaki; Nozaki, Teo*; Hatano, Yuji*; Matsuyama, Masao*; Tsuchiya, Kunihiko
no journal, ,
Beryllium metal is used as a neutron reflector in the JMTR. JMTR is scheduled to restart on FY2012. Furthermore, the study of material to improve lifetime of beryllium frame is being conducted. In this study, the corrosion behavior of beryllium metal has been investigated under JMTR reactor-water-simulated condition. Beryllium metal samples for this study are S-200F, S-65H and I-220H, and were prepared by Vacuum Hot Pressing (VHP) and Hot Isostatic Pressing (HIP). The corrosion test changed corrosion time, and was examined under pure water at 50
C. After the corrosion test, X-Ray Diffraction (XRD) and X-ray Photoelectron Spectroscopy (XPS) were examined as a surface analysis of beryllium metal, and electrical conductivity and impurity measurement were examined as a water analysis. As a result, I-220H indicated the highest corrosion resistance of three beryllium metal samples.
Haga, Yoshinori; Matsumoto, Yuji*; Tateiwa, Naoyuki; Yamamoto, Etsuji
no journal, ,
(
: Al, Ga, Si)Haga, Yoshinori; Matsumoto, Yuji*; Yamamoto, Etsuji
no journal, ,
no abstracts in English
