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Takada, Eiji*; Fujimoto, Nozomu; Matsuda, Atsuko*; Nakagawa, Shigeaki
JAERI-Tech 2003-040, 23 Pages, 2003/03
JAERI-Tech-2003-040.pdf:1.28MB
In the High Temperature Engineering Test Reactor (HTTR), since the primary circuit is very high at the high temperature test operation, the special alloy Alloy800H is used as the metallic material for cladding tubes and spines of the control rods to endure the temperature of 950 degrees centigrade. The control rod is supposed to be exchanged for the excess use of its temperature limit 900 degrees centigrade according to the strength data of Alloy800H. The scram shutdown by loss of off-site electric power at the high temperature test operation is assumed as an event of the temperature of the control rods to exceed 900 degrees centigrade. In this report, the temperature of the control rods is analyzed by using the measurement data of the rise-to-power test. The result of this analysis it is confirmed that the control rod temperature does not exceed its limitation value even after the most temperature raises event of the loss of off-site electric power at the high temperature test operation.
Kaji, Yoshiyuki; Kikuchi, Kenji; Penkalla, H. J.*
Proceedings of the 7th International Conference on Creep and Fatigue at Elevated Temperatures (CREEP7), p.179 - 183, 2001/06
A creep constitutive equation in Alloy800H was developed at 700, 800 and 850oC. In the equation, the inelastic strain rate is written in the form of a flow equation of the Norton-Bailey type and the hardening during deformation under various loads is induced by an internal stress which is subdivided into back stress and friction stress. The back stress represents a conservative part of the creep resistance while the friction stress includes all the dissipative parts in the internal structure such as grain boundary sliding, diffusion and interaction between dislocation and precipitation. Parameters were determined by the deformation properties for creep under constant stress conditions at each temperature. Deformation analyses show a good agreement between calculations and experimental results for creep tests at each temperature.
Tachibana, Yukio; E.Krempl*
J. Eng. Mater. Technol., 120(3), p.193 - 196, 1998/07
Times Cited Count：16 Percentile：62.26(Engineering, Mechanical)no abstracts in English
Tachibana, Katsumi; Nishi, Hiroshi; Eto, Motokuni;
JAERI-Tech 98-010, 107 Pages, 1998/03
no abstracts in English
parameterKaji, Yoshiyuki; M.Roedig*; Kikuchi, Kenji
Int. J.Press. Vessels Piping, 75(15), p.1065 - 1074, 1998/00
Times Cited Count：2 Percentile：31.91(Engineering, Multidisciplinary)no abstracts in English
Tachibana, Yukio; Shiozawa, Shusaku; *; *; *
Nucl. Eng. Des., 172(1-2), p.93 - 102, 1997/00
Times Cited Count：8 Percentile：56.29(Nuclear Science & Technology)no abstracts in English
Kaji, Yoshiyuki; Kikuchi, Kenji
Nihon Zairyo Kyodo Gakkai-Shi, 30(2), p.59 - 73, 1996/00
no abstracts in English
Tachibana, Yukio; E.Krempl*
Trans. ASME, Ser. H, 117, p.456 - 461, 1995/10
no abstracts in English
Hada, Kazuhiko; Nishiguchi, Isoharu; ; Tsuji, Hirokazu
Nucl. Eng. Des., 132, p.1 - 11, 1991/00
Times Cited Count：24 Percentile：90.25(Nuclear Science & Technology)no abstracts in English
Nishiguchi, Isoharu; Tachibana, Yukio; Motoki, Yasuo; Shiozawa, Shusaku
JAERI-M 90-152, 31 Pages, 1990/09
no abstracts in English
Maruyama, So; Nishiguchi, Isoharu; Fujimoto, Nozomu; *; Shiozawa, Shusaku; Sudo, Yukio
JAERI-M 90-104, 60 Pages, 1990/07
no abstracts in English
; ; ; ;
JAERI-M 82-196, 29 Pages, 1982/12
no abstracts in English
;
JAERI-M 9185, 20 Pages, 1980/11
no abstracts in English
