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Uesawa, Shinichiro; Koizumi, Yasuo; Yoshida, Hiroyuki
Proceedings of 9th International Conference on Multiphase Flow (ICMF 2016) (CD-ROM), 6 Pages, 2016/05
Liu, W.; Podowski, M. Z.*
Nihon Kikai Gakkai Netsu Kogaku Konfarensu 2015 Koen Rombunshu (CD-ROM), 2 Pages, 2015/10
This paper gives prediction to the transient heat transfer at Departure of Nucleate Boiling (DNB) point for subcooled flow boiling. The prediction is carried out by solving the heat conduction equations in cylindrical coordinates with convective boundary condition, which changes with the change of the heat transfer mode on the heated surface. DNB is assumed to happen at the complete dryout of liquid sublayer trapped between the heated wall and an elongated vapor clot, during the passing time of the vapor clot. Important parameters including initial thickness of the liquid sublayer, vapor clot length, vapor clot velocity and void fraction etc., are calculated from the Liu - Nariai model. The initial heater surface temperature is derived from the Jens-Lottes correlation. The transient changes of liquid sublayer thickness, surface temperature at DNB are reported. No obvious temperature jumping is observed at DNB. To predict temperate excursion at Critical Heat Flux (CHF), more simulations to the transient boiling and film boiling processes are needed.
Koizumi, Yasuo; Takahashi, Kazuki*
Proceedings of 15th International Heat Transfer Conference (IHTC 2014) (USB Flash Drive), 13 Pages, 2014/08
Pool nucleate boiling heat transfer experiments were performed for water at 0.101 MPa to examine the elementary process of the nucleate boiling. Heat transfer surface was made from a copper printed circuit board. Direct current was supplied to heat it up. The Bakelite plate of the backside of a copper layer was taken off at the center portion of the heat transfer surface to expose the back side of the copper layer. The instantaneous variation of the backside temperature of the heat transfer surface was measured with an infrared radiation camera. Bubble behavior was recorded with a high speed video camera. In the isolated bubble region, surface temperature was uniform during waiting time. When boiling bubble generation started, a large dip in the surface temperature distribution was formed under the bubble. After the bubble left from the heat transfer surface, the surface temperature distribution returned to former uniform distribution. Surface temperature was not affected by the bubble generation beyond 1.8 mm from the center of the bubble. In the intermediate and high heat flux region, the variation of surface temperature and heat flux did not become large even though the heat flux increased. The heat flux variation was close to that at the isolated boiling region.
Shibamoto, Yasuteru; Yonomoto, Taisuke; Nakamura, Hideo; Nishikizawa, Tomotoshi
Proceedings of 4th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-4), p.210 - 214, 2004/11
no abstracts in English
Masaki, Kei; Taniguchi, Masaki; Miyo, Yasuhiko; Sakurai, Shinji; Sato, Kazuyoshi; Ezato, Koichiro; Tamai, Hiroshi; Sakasai, Akira; Matsukawa, Makoto; Ishida, Shinichi; et al.
Fusion Engineering and Design, 61-62, p.171 - 176, 2002/11
Times Cited Count:19 Percentile:74.68(Nuclear Science & Technology)A flat carbon fiber composite tile mock-up with screw tubes, which have helical fins like a nut, was fabricated aiming at further improvement of the heat removal performance of the cost-effectively manufactured divertor target for JT-60SC (modified JT-60 as a superconducting coil tokamak). The heat removal performance of the mock-up was successfully demonstrated on the JAERI Electron Beam Irradiation Stand. The estimated heat transfer coefficient of the screw tube at the non-boiling region was roughly 3 times higher than that of the smooth tube. This corresponds to 1.5 times that of the swirl tube. A heat cycle test of 10 MW/m2 showed that the mock-up with the screw tubes could withstand for 1400 cycles. These results indicate that the divertor target plate with the flat carbon fiber composite tile and the screw tube can be a promising candidate for the JT-60SC divertor target.
Mishima, Kaichiro*; Saito, Yasushi*
JAERI-Tech 2002-014, 83 Pages, 2002/03
no abstracts in English
Kaminaga, Fumito*
JAERI-Tech 2002-012, 68 Pages, 2002/03
no abstracts in English
Iguchi, Tadashi; Ito, Hideo; Kiuchi, Toshio; Watanabe, Hironori; Kimura, Mamoru*; Anoda, Yoshinari
JAERI-Data/Code 2001-013, 502 Pages, 2001/03
no abstracts in English
Onuki, Akira; Akimoto, Hajime
Journal of Nuclear Science and Technology, 36(11), p.1021 - 1029, 1999/11
Times Cited Count:1 Percentile:13.15(Nuclear Science & Technology)no abstracts in English
Onuki, Akira;
Proc. of 5th Int. Topical Meeting on Nuclear Thermal Hydraulics,Operations and Safety, 00(00), p.1 - 6, 1997/04
no abstracts in English
Araki, Masanori; Ogawa, Masuro; Kunugi, Tomoaki; Sato, Kazuyoshi;
Int. J. Heat Mass Transfer, 39(14), p.3045 - 3055, 1996/00
Times Cited Count:72 Percentile:94.22(Thermodynamics)no abstracts in English
S.Navarro-Valenti*; S.H.Kim*; V.Georgevich*; R.P.Taleyarkhan*; Fuketa, Toyoshi; Soyama, Kazuhiko; Ishijima, Kiyomi; Kodaira, Tsuneo
NUREG/CP-0142 (Vol. 4), 0, p.2957 - 2976, 1996/00
no abstracts in English
Onuki, Akira; ; Murao, Yoshio
JAERI-M 93-139, 85 Pages, 1993/07
no abstracts in English
Onuki, Akira; ; Murao, Yoshio
JAERI-M 93-138, 55 Pages, 1993/07
no abstracts in English
; Onuki, Akira; *; Murao, Yoshio
JAERI-M 93-032, 190 Pages, 1993/03
no abstracts in English
Kumamaru, Hiroshige; Kukita, Yutaka
ANS Proc. 1991 National Heat Transfer Conf., Vol. 5, p.22 - 29, 1991/00
no abstracts in English
Onuki, Akira; ; Murao, Yoshio
Journal of Nuclear Science and Technology, 27(6), p.535 - 546, 1990/06
no abstracts in English
G.Xu*; Kumamaru, Hiroshige; Tasaka, Kanji
JAERI-M 89-178, 35 Pages, 1989/11
no abstracts in English
; ; ; ; ; Abe, Yutaka; Murao, Yoshio
NUREG/CP-0082 Vol.4, p.429 - 444, 1987/00
no abstracts in English
JAERI-M 86-075, 35 Pages, 1986/05
no abstracts in English