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Uesawa, Shinichiro; Ono, Ayako; Koizumi, Yasuo; Shibata, Mitsuhiko; Yoshida, Hiroyuki
Dai-55-Kai Nihon Dennetsu Shimpojiumu Koen Rombunshu (USB Flash Drive), 8 Pages, 2018/05
no abstracts in English
Liu, W.
Dai-20-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu, p.391 - 392, 2015/06
Subcooled flow boiling is a boiling that begins and develops even though the mean enthalpy of liquid phase is lower than saturation. This forced convective boiling is one of the most efficient ways for the removal of high heat flux. It is widely used in the high heat flux components such as nuclear reactor cores, accelerator targets and fusion reactor components. The thermal outputs of these systems are restricted by Critical Heat Flux(CHF). Because of the importance of the CHF, lots of researches, including both experimental and mechanistic modelling, have been performed. However, the CHF prediction for rod bundles still remains unsolved. As the first step for the CHF prediction in rod bundles, in this paper, we tried to predict the CHF in annulus, which is the most basic flow geometry simplified from a rod bundle. We performed the CHF prediction by using liquid sublayer dryout model, combined with Nouri single phase velocity distribution correlation for annulus. The results show that the CHF in annulus can be predicted in an accuracy of about 
20%.
Sugiyama, Tomoyuki; Fuketa, Toyoshi
Journal of Nuclear Science and Technology, 41(11), p.1083 - 1090, 2004/11
Times Cited Count：10 Percentile：55.72(Nuclear Science & Technology)The effect of cladding surface pre-oxidation on the rod coolability under reactivity initiated accidents was investigated. NSRR tests on irradiated fuel rods have shown higher rod coolability than that of fresh rods, which arose from suppressed DNB and early quench at the surface. To identify the dominant factor, possible factors such as pellet cracking and so on, were assessed. The most probable factor, the cladding pre-oxidation, was examined by pulse irradiation tests on fresh rods with three cladding surface conditions, no oxide layer, 1
m and 10m-thick oxide layers. Temperature measurements showed increased thresholds for DNB and quench at the pre-oxidized surface, leading to a reduced film boiling duration. The shifts of the critical and minimum heat flux points could be caused by the surface wettability increase. In the present tests, the wettability change was probably dominated by the chemical potential change at the surface due to pre-oxidation. The test results indicate the effects do not depend on the oxide layer thickness, but on the presence of the oxide layer.
Kureta, Masatoshi; Akimoto, Hajime
Nuclear Technology, 143(1), p.89 - 100, 2003/07
Times Cited Count：10 Percentile：56.43(Nuclear Science & Technology)no abstracts in English
Kureta, Masatoshi; Akimoto, Hajime
Nihon Kikai Gakkai Rombunshu, B, 69(682), p.1469 - 1476, 2003/06
no abstracts in English
Monde, Masanori*; Mitsutake, Yuichi*; Ishida, Kenji*; Hino, Ryutaro
JAERI-Tech 2003-013, 56 Pages, 2003/03
no abstracts in English
Kureta, Masatoshi; Hibiki, Takashi*; Mishima, Kaichiro*; Akimoto, Hajime
International Journal of Heat and Mass Transfer, 46(7), p.1171 - 1181, 2003/03
Times Cited Count：13 Percentile：49.26(Thermodynamics)no abstracts in English
Nakano, Yoshihiro; Ishikawa, Nobuyuki; Nakatsuka, Toru; Iwamura, Takamichi
JAERI-Conf 2002-012, 219 Pages, 2002/12
JAERI-Conf-2002-012.pdf:17.4MB
no abstracts in English
Kureta, Masatoshi
JAERI-Conf 2002-012, p.47 - 52, 2002/12
no abstracts in English
Sugiyama, Tomoyuki; Fuketa, Toyoshi
IAEA-TECDOC-1320, p.102 - 110, 2002/11
This report discusses effect of cladding surface pre-oxidation on fuel rod coolability during reactivity initiated accident (RIA) conditions. NSRR irradiated fuel experiments had shown cladding surface temperature lower than fresh fuel experiments. One possible speculation for the temperature difference is that oxide layer at the cladding outer surface enhanced heat transfer. To verify the speculation, pulse irradiation tests were performed on fuel rods with three different surface conditions: without oxide layer, with 1m-thick and 10m-thick oxide layer. Transient records of the cladding surface temperature showed the critical heat flux and the minimum heat flux increased for the oxidized fuel rods. These effects depend on presence of the oxide layer, not on the thickness of the layer, because no difference existed between results from 1m and 10m rods.
Kureta, Masatoshi; Akimoto, Hajime
International Journal of Heat and Mass Transfer, 45(20), p.4107 - 4115, 2002/09
Times Cited Count：44 Percentile：80.92(Thermodynamics)no abstracts in English
Kureta, Masatoshi; Akimoto, Hajime; Yamamoto, Kazuhiko*; Okada, Hiroyuki*
Proceedings of International Congress on Advanced Nuclear Power Plants (ICAPP) (CD-ROM), 7 Pages, 2002/00
no abstracts in English
Kinoshita, Hidetaka; Terada, Atsuhiko*; Kaminaga, Masanori; Hino, Ryutaro
JAERI-Tech 2001-061, 43 Pages, 2001/10
JAERI-Tech-2001-061.pdf:5.21MB
no abstracts in English
Ezato, Koichiro; Suzuki, Satoshi; Sato, Kazuyoshi; Taniguchi, Masaki; Hanada, Masaya; Araki, Masanori; Akiba, Masato
Fusion Engineering and Design, 56-57, p.291 - 295, 2001/10
Times Cited Count：14 Percentile：68.97(Nuclear Science & Technology)no abstracts in English
Kureta, Masatoshi; Akimoto, Hajime
Nihon Kikai Gakkai Rombunshu, B, 67(662), p.2550 - 2557, 2001/10
no abstracts in English
Okubo, Tsutomu; Iwamura, Takamichi; Akimoto, Hajime; Araya, Fumimasa; Onuki, Akira; Yamamoto, Kazuhiko*
Dai-7-Kai Doryoku Enerugi Gijutsu Shimpojiumu Koen Rombunshu (00-11), p.250 - 253, 2000/11
no abstracts in English
Okubo, Tsutomu; Araya, Fumimasa
Proceedings of International Workshop on Current Status and Future Directions in Boiling Heat Transfer and Two-Phase Flow, p.177 - 181, 2000/00
no abstracts in English
Kureta, Masatoshi; Akimoto, Hajime
Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7) (CD-ROM), 8 Pages, 1999/00
no abstracts in English
Kureta, Masatoshi; Akimoto, Hajime
Proc. of 6th Int. Conf. on Nucl. Eng. (CD-ROM), 13 Pages, 1998/00
no abstracts in English
