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Hidaka, Akihide; Maruyama, Yu; Nakamura, Hideo
Proceedings of 6th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operations and Safety (NUTHOS-6) (CD-ROM), 15 Pages, 2004/00
Severe accident studies showed that Direct Containment Heating issue was resolved for PWRs because a creep rupture at pressurizer surge line would occur prior to the melt-through of Reactor Pressure Vessel during station blackout (TMLB'). However, it was recently concerned that, if the secondary system is depressurized during TMLB', the creep rupture at SG U-tubes would occur earlier than the surge line. This pressure- and temperature-induced SG U-tube rupture (PTI-SGTR) is not preferable because of the increase in offsite consequences. The SCDAP/RELAP5 analyses by USNRC showed that the surge line would fail earlier than the U-tubes. However, the analyses used a coarse nodilization for steam mixing at the SG inlet plenum that could affect the temperature of U-tubes. To investigate the effect of steam mixing, an analysis was performed with MELCOR1.8.4. The analysis showed that the surge line would fail earliest during TMLB' while the U-tubes could fail earliest during TMLB' with secondary system depressurization. Further investigation is needed for occurrence conditions of PTI-SGTR.
; Kukita, Yutaka
Journal of Nuclear Science and Technology, 33(9), p.696 - 702, 1996/09
Times Cited Count:1 Percentile:14.78(Nuclear Science & Technology)no abstracts in English
; Kukita, Yutaka; *
The 3rd JSME/ASME Joint Int. Conf. on Nuclear Engineering (ICONE),Vol. 1, 0, p.131 - 136, 1995/00
no abstracts in English
Maruyama, Yu; Igarashi, Minoru*; Nakamura, Naohiko; Hashimoto, Kazuichiro; Sugimoto, Jun
The 3rd JSME/ASME Joint Int. Conf. on Nuclear Engineering, Vol. 3, 0, p.1247 - 1251, 1995/00
no abstracts in English
Hashimoto, Kazuichiro; Nakamura, Naohiko; Igarashi, Minoru*; Maruyama, Yu; Sugimoto, Jun
The 3rd JSME/ASME Joint Int. Conf. on Nuclear Engineering, Vol. 3, 0, p.1241 - 1246, 1995/00
no abstracts in English
Kumamaru, Hiroshige; Kukita, Yutaka
Int. Conf. on New Trends in Nuclear System Thermohydraulics,Vol. 1, 0, p.119 - 126, 1994/00
no abstracts in English
; Kukita, Yutaka; Yonomoto, Taisuke; *
Nuclear Technology, 96, p.202 - 214, 1991/11
Times Cited Count:10 Percentile:72.86(Nuclear Science & Technology)no abstracts in English
Kukita, Yutaka; Nakamura, Hideo; *; *; *; Anoda, Yoshinari; Kumamaru, Hiroshige; Suzuki, Mitsuhiro; ; Yonomoto, Taisuke; et al.
JAERI-M 91-040, 122 Pages, 1991/03
no abstracts in English
Katayama, Jiro; Nakamura, Hideo; Kukita, Yutaka
Proc. of the Int. Conf. on Multiphase Flows 91-TSUKUBA,Vol. 1, p.7 - 10, 1991/00
no abstracts in English
*; Anoda, Yoshinari; Kukita, Yutaka
The OECD/LOFT Project; Achievements and Significant Results, p.145 - 163, 1991/00
no abstracts in English
Kukita, Yutaka; *; *; *; Anoda, Yoshinari; Kumamaru, Hiroshige; Suzuki, Mitsuhiro; ; Yamamoto, Nobuo; Nakamura, Hideo; et al.
JAERI-M 90-039, 122 Pages, 1990/03
no abstracts in English
Kukita, Yutaka; *; *; Anoda, Yoshinari; Kumamaru, Hiroshige; Suzuki, Mitsuhiro; ; Yamamoto, Nobuo; Nakamura, Hideo; Yonomoto, Taisuke; et al.
JAERI-M 89-225, 117 Pages, 1990/01
no abstracts in English
JAERI-M 8860, 160 Pages, 1980/05
no abstracts in English
*
JAERI-M 7505, 162 Pages, 1978/02
no abstracts in English
*
JAERI-M 7239, 177 Pages, 1977/09
no abstracts in English