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Ozawa, Masaaki*; Amaya, Masaki
Nihon Genshiryoku Gakkai Wabun Rombunshi, 19(4), p.185 - 200, 2020/12
no abstracts in English
Nakano, Hiroko; Hirota, Noriaki; Shibata, Hiroshi; Takeuchi, Tomoaki; Tsuchiya, Kunihiko
Mechanical Engineering Journal (Internet), 5(2), p.17-00594_1 - 17-00594_12, 2018/04
no abstracts in English
Nemoto, Yoshiyuki; Kaji, Yoshiyuki; Ogawa, Chihiro*; Nakashima, Kazuo*; Tojo, Masayuki*
Proceedings of 2017 Water Reactor Fuel Performance Meeting (WRFPM 2017) (USB Flash Drive), 10 Pages, 2017/09
To cope with the hypothetical severe accident in spent fuel pools (SFPs), it is important to understand the high temperature oxidation behavior of the Zirconium claddings exposed in the air or in the atmosphere of air/steam mixture. In this study, oxidation tests on Zircaloy-2 (Zry2) and Zircaloy-4 (Zry4) short samples were conducted in the atmosphere of air - steam mixture, and mixing ratio was varied to evaluate its influence on the oxidation kinetics in the temperature range from 600 to 1100
C. From 900 to 1000C for Zry2, and from 800 to 1000C for Zry4, oxidation rates appeared higher in air - steam mixture than in dry air or in steam without air. This tendency was appeared more evident in post-breakaway transition phase after fracture of dense oxide layer on the surface of specimens. These results suggest importance of the oxidation model development in consideration of the air - steam mixture environment for the SFP accident analysis.
Uwaba, Tomoyuki
JNC TN9420 2000-005, 28 Pages, 2000/03
JNC-TN9420-2000-005.pdf:0.94MB
In the first phase of the feasibility study, their basic objectives are presentating the feasible image and scenario of development of the FBR cycle system, which is composed of the fast reactor, spent fuel reprocessing and fuel manufacturing facility. In the development of the FBR system in this phase, various ideas of plants are to be studied, which include coolant types such as sodium, heavy metals, gases(CO
, He), wator, and middle or small size of the reactor, and fuel types (MOX, metal and nitride). In this report, as a part of this study, materials used for the core of the helium gas cooled reactor and their integrity (corrosion, mechanical and irradiation property) under high temperature helium atmosphere were investigated from open literatures.
Futakawa, Masatoshi; Steinbrech, R. W.*
Journal of the American Ceramic Society, 81(7), p.1819 - 1842, 1998/07
no abstracts in English
in high-T
superconducting La
Sr
CuO
pellet by flow-coulometrySasaki, Yuji; Aoyagi, Hisao; Takeishi, Hideyo; Yoshida, Zenko
Physica C, 191, p.347 - 353, 1992/00
Times Cited Count：7 Percentile：55.21no abstracts in English
Sasaki, Yuji; Aoyagi, Hisao; Takeishi, Hideyo; Yoshida, Zenko
Analytical Sciences, 7(Suppl.), p.1201 - 1204, 1991/00
no abstracts in English
; Kondo, Tatsuo
Boshoku Gijutsu, 31(3), p.125 - 132, 1982/00
no abstracts in English
Shindo, Masami; Kondo, Tatsuo
Tetsu To Hagane, 10, p.150 - 159, 1982/00
no abstracts in English
Shindo, Masami; Kondo, Tatsuo
JAERI-M 8770, 18 Pages, 1980/03
no abstracts in English
; Kondo, Tatsuo
Tainetsu Kinzoku Zairyo Dai-123-Iinkai Kenkyu Hokoku, 20(1), p.49 - 58, 1979/00
no abstracts in English
*; Kondo, Tatsuo
Tainetsu Kinzoku Zairyo Dai-123-Iinkai Kenkyu Hokoku, 20(1), p.93 - 102, 1979/00
no abstracts in English
Shindo, Masami; ; Kondo, Tatsuo
Tainetsu Kinzoku Zairyo Dai-123-Iinkai Kenkyu Hokoku, 19(3), p.331 - 338, 1978/00
no abstracts in English
Shindo, Masami; Kondo, Tatsuo
Tetsu To Hagane, 62(12), p.1540 - 1549, 1976/12
no abstracts in English
; ;
Nihon Genshiryoku Gakkai-Shi, 18(4), p.217 - 224, 1976/04
no abstracts in English
;
Nihon Genshiryoku Gakkai-Shi, 10(6), p.319 - 324, 1968/00
no abstracts in English
Nemoto, Yoshiyuki
no journal, ,
To evaluate the safety measures for the spent fuel pool accident, it is required to construct the oxidation model of the fuel cladding materials in air environment to upgrade the simulation codes. The author reviews the latest studies and introduce the own research on oxidation behavior of the zircalloy 2 and 4.
Nakahara, Kaito*; Kawada, Rio*; Irisawa, Eriko; Ueda, Mitsutoshi*; Kawamura, Kenichi*
no journal, ,
In order to develop oxygen sensor using oxide scales formed on the surface of zirconium alloy, we focused on zirconium and copper alloy system. It was expected that the oxide scale of Zr oxide on the alloy is thin and elaborate compared with that on the pure Zr because the activity of Zr in the alloy is reduced and the oxidation rate of alloy become slow. Therefore the oxidation behavior and mechanism of two phase alloy, Zr-35Cu which is composed of ZrCu and Zr
Cu
, was studied. The results showed the oxidation rate of the alloy was same with that of the pure Zr.
Nemoto, Yoshiyuki; Fujimura, Yuki; Sakamoto, Kan*; Yamashita, Shinichiro
no journal, ,
FeCrAl-ODS steel is one of candidates for Accident Tolerant Fuel (ATF) cladding material. To investigate the detail oxidation behavior of the material, the authors conducted oxidation tests in high temperature steam flow in thermobalance chamber. After the tests, surface oxide layer was studied by using laser Raman spectroscopy, scanning electron microscopy and electron dispersed X-ray spectroscopy to discuss the difference of oxidation behavior at different testing temperature. At 1150 C, the surface oxide layer was Alumina, and at 750 C, it was Fe oxides. The detail of our investigation will be discussed in the session.
Ohigashi, Jun*; Ueda, Mitsutoshi*; Kawamura, Kenichi*; Irisawa, Eriko; Komatsu, Atsushi; Kato, Chiaki
no journal, ,
In order to develop an oxygen sensor using high temperature oxide film of zirconium alloy as a solid electrolyte, an alloy of zirconium with nickel was investigated to suppress the growth rate of zirconia oxide film on the alloy. In this study, the high temperature oxidation behavior of zirconium-nickel alloy was evaluated. The alloy was oxidized at 873 K in a mixture of argon and 1% oxygen. The relationship between the difference in oxidation rate and in the properties of the oxide film were compared and discussed with the cross-sectional images of the oxide film. The oxidation rate was the same or slightly higher than that of pure zirconium. In addition, the oxide film became thicker and voids were formed in some areas, and some cracks were also observed. The results did not show any tendency to reduce the activity of zirconium in the alloy and to decrease the oxidation rate.
