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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.
Nobuta, Yuji*; Yamauchi, Yuji*; Hino, Tomoaki*; Akamaru, Satoshi*; Hatano, Yuji*; Matsuyama, Masao*; Suzuki, Satoshi; Akiba, Masato
Fusion Engineering and Design, 87(7-8), p.1070 - 1073, 2012/08
Times Cited Count：2 Percentile：16.97(Nuclear Science & Technology)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
Kawamura, Yoshinori; Shu, Wataru*; Matsuyama, Masao*; Yamanishi, Toshihiko
Fusion Science and Technology, 60(3), p.986 - 989, 2011/10
Times Cited Count：4 Percentile：31.43(Nuclear Science & Technology)Assuming the blanket sweep gas at the outlet of the blanket, tritium gas monitor by 
-ray induced X-ray spectroscopy has been modified, and has measured tritium at 120 
C. The counting rate at 120 C was about 1/2 of that at the room temperature. In this work, the measurement system was a closed system. When two systems have same volume and same pressure, the number of molecules in higher temperature system is smaller. This is one of the causes of small counting rate. The deterioration of the scintillator after heating was not observed.
Kobayashi, Makoto*; Wang, W.*; Kurata, Rie; Matsuyama, Masao*; Hayashi, Takumi; Yamanishi, Toshihiko; Asakura, Yamato*; Oya, Yasuhisa*; Okuno, Kenji*
Fusion Science and Technology, 60(1), p.403 - 406, 2011/07
Times Cited Count：0 Percentile：0.00(Nuclear Science & Technology)The trapping and release mechanisms of hydrogen isotopes for the stainless steel (SS) oxidized at various temperatures were investigated. The oxide layer was mainly consisted of iron oxides (Fe
O
) and its decomposition temperature was almost consistent with the release temperature of deuterium, where major chemical form was a molecular deuterium (D
). The deuterium retention was increased as the oxidation temperature increased. It was considered that the thickness of oxide layer would make a large influence on the retention of hydrogen isotopes. On the other hand, the amount of released deuterium as heavy water (DO) was independent with oxidation temperature. It was considered that the formation of hydrogen isotope as water form was depended on the amount of FeO on the top most surface layer of SS.
Tsuchiya, Kunihiko; Hanawa, Yoshio; Kitagishi, Shigeru; Ito, Masayasu; Hatano, Yuji*; Matsuyama, Masao*
Heisei-21-Nendo Toyama Daigaku Kyodo Riyo, Kyodo Kenkyu Seika Hokokusho, p.9 - 10, 2010/12
no abstracts in English
Matsuyama, Masao*; Hayashi, Takumi; Yamanishi, Toshihiko
Purazuma, Kaku Yugo Gakkai-Shi, 86(7), p.431 - 435, 2010/07
The facilities at University of Toyama (Hydrogen Isotope Research Center) and at JAEA (Tritium Process Laboratory) have been operated with a large amount of tritium for 25-30 years. Through these operation experiences, a set of valuable data has been obtained. On the other hand, the tritium facilities have still been required for R&D on tritium technologies for DEMO reactors. In this paper, a series of maintenance activities for the facility at University of Toyama has been described. The activities at JAEA have also been pointed out for a new facility at Rokkasho and a future program. A long continuous effort should be required for the tritium technologies for fusion reactors. Finally, future programs in the field of tritium have thus been discussed.
Matsuyama, Masao*; Yamanishi, Toshihiko
Purazuma, Kaku Yugo Gakkai-Shi, 86(2), p.97 - 103, 2010/02
In Japan, the technologies handling a large amount of tritium have been developed at TPL (Tritium Process Laboratory) of JAEA (Japan Atomic Energy Agency) and Hydrogen Isotope Research Center of Toyama University for 30 years. These facilities have been operated with no tritium release and no accident. The tritium handling technologies have thus been demonstrated by using a large amount of tritium. Through these products, the tritium handling technologies have been established in Japan also. To construct these facilities, many tritium researchers made their efforts. Significant R&D results and the above efforts are reported from viewpoint of succeed to the tritium handling technologies and of maintenance of the facilities.
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：62.12(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：20 Percentile：74.67(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.
Kawamura, Yoshinori; Shu, Wataru*; Matsuyama, Masao*; Yamanishi, Toshihiko
no journal, ,
Assuming the blanket sweep gas at the outlet of the blanket, tritium gas monitor by -ray induced X-ray spectroscopy has been modified, and has measured tritium at 120C. The counting rate at 120C was about 1/2 of that at the room temperature. In this work, the measurement system was a closed system. When two systems have same volume and same pressure, the number of molecules in higher temperature system is smaller. This is one of the causes of small counting rate. The deterioration of the scintillator after heating was not observed.
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 50C. 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.
Tsuchiya, Kunihiko; Hanawa, Yoshio; Kitagishi, Shigeru; Ito, Masayasu; Hatano, Yuji*; Matsuyama, Masao*
no journal, ,
no abstracts in English
