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Ishihara, Masahiro; Yamaji, Masatoshi*; Baba, Shinichi; Hanawa, Satoshi
Key Engineering Materials, 297-300, p.201 - 206, 2005/11
no abstracts in English
Kojima, Kensuke; Okajima, Shigeaki; Yamane, Tsuyoshi; Ando, Masaki; Kataoka, Masaharu*; Iwanaga, Kohei
JAERI-Tech 2004-016, 38 Pages, 2004/03
JAERI-Tech-2004-016.pdf:1.46MB
To investigate the void coefficient in the Reduced-Moderation Water Reactor (RMWR), an infinite multiplication factor was measured in the FCA-XXII-1 (65V) core. Axial and radial fission rate distributions were measured by micro fission chambers with four different kinds of nuclides. The infinite multiplication factor was derived from the material buckling, which was obtained from both the axial and radial fission rate distributions, and the migration area calculated. The value of it in the test region of the FCA-XXII-1 (65V) core was 1.344
0.034. It was compared with the calculation, the ratio of the calculation to the measurement was 1.0080.026. The improvement in measurement accuracy was also considered.
Omori, Junji*; Araki, Masanori
JAERI-Tech 2000-006, p.15 - 0, 2000/02
JAERI-Tech-2000-006.pdf:0.66MB
no abstracts in English
Yamane, Yuichi; Miyoshi, Yoshinori
Proceedings of 6th International Conference on Nuclear Criticality Safety (ICNC '99), 1, p.180 - 185, 1999/00
no abstracts in English
Ishihara, Masahiro; Iyoku, Tatsuo; Futakawa, Masatoshi
Nucl. Eng. Des., 148, p.91 - 100, 1994/00
Times Cited Count：4 Percentile：42.35(Nuclear Science & Technology)no abstracts in English
Iyoku, Tatsuo; Shiozawa, Shusaku; Ishihara, Masahiro; ; Oku, Tatsuo*
Nucl. Eng. Des., 132, p.23 - 30, 1991/00
Times Cited Count：23 Percentile：89.72(Nuclear Science & Technology)no abstracts in English
Nishiguchi, Isoharu; Kaji, Yoshiyuki; Ioka, Ikuo; *; *
J. Pressure Vessel Technol., 112, p.233 - 239, 1990/08
Times Cited Count：8 Percentile：54.28(Engineering, Mechanical)no abstracts in English
Hoshiya, Taiji; ; *;
JAERI-M 89-199, 35 Pages, 1989/12
no abstracts in English
Ueda, Shuzo
Nucl.Eng.Des., 85, p.251 - 260, 1985/00
Times Cited Count：9 Percentile：74.17(Nuclear Science & Technology)no abstracts in English
; Yamamoto, Masahiro; ; *; *; *; *
Journal of Nuclear Science and Technology, 21(5), p.341 - 355, 1984/00
Times Cited Count：4 Percentile：45.52(Nuclear Science & Technology)no abstracts in English
O assembly; ;
Journal of Nuclear Science and Technology, 5(1), p.1 - 6, 1968/00
Times Cited Count：1no abstracts in English
Pu fueled system from the data of composite Pu-
U fueled fast critical assemblyNihon Genshiryoku Gakkai-Shi, 4(11), p.746 - 753, 1962/00
no abstracts in English
Miura, Kazuhiro*; Okafuji, Takashi*; Sago, Hiromi*; Shimomura, Kenta; Okajima, Satoshi; Sato, Kenichiro*
no journal, ,
Buckling evaluation methods capable of evaluating elasto-plastic buckling under axial compression, bending, and shear loads are required for cylindrical vessels of fast reactors in order to cope with thinning due to the increase in diameter, adoption of new materials, and adoption of seismic isolation design due to the increase in the standard seismic ground motion. Buckling evaluation methods corresponding to the above are being considered in the fast reactor standards of the Japan Society of Mechanical Engineers. In this study, in order to examine the applicability of the proposed buckling evaluation equation, Monte Carlo simulation was carried out using material properties and initial imperfections, which are the fluctuation factors of buckling strength, as parameters, and the effect of the fluctuation of these factors on buckling load was evaluated. When the buckling load was normalized by the buckling critical value according to the proposed formula using the longitudinal elastic modulus and the design yield stress of JSME S NC2-2013, the 95% lower confidence limit exceeded the threshold of the proposed formula for both the vertical single load condition and the horizontal and vertical combined load condition. The results show that the buckling critical value calculated by using the design yield stress in the proposed equation is more conservative than the 95% lower confidence limit of the actual buckling load affected by the scatter of material properties and others.
