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Journal Articles

Observation of dry patch behavior on copper heat transfer surface and measurement of surface temperature distribution in nucleate pool boiling

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

Journal Articles

Critical heat flux prediction for subcooled flow boiling in annulus

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 $$pm$$20%.

JAEA Reports

Energy confinement and transport of H-mode plasmas in tokamak

Urano, Hajime

JAERI-Research 2004-027, 131 Pages, 2005/02

JAERI-Research-2004-027.pdf:5.69MB

no abstracts in English

Journal Articles

Effect of cladding surface pre-oxidation on rod coolability under reactivity initiated accident conditions

Sugiyama, Tomoyuki; Fuketa, Toyoshi

Journal of Nuclear Science and Technology, 41(11), p.1083 - 1090, 2004/11

 Times Cited Count:8 Percentile:47.67(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$$mu$$m and 10$$mu$$m-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.

Journal Articles

Critical power correlation for axially uniformly heated tight-lattice bundles

Kureta, Masatoshi; Akimoto, Hajime

Nuclear Technology, 143(1), p.89 - 100, 2003/07

 Times Cited Count:10 Percentile:40.74(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Critical power in axially uniformly-heated tight-lattice rod bundles

Kureta, Masatoshi; Akimoto, Hajime

Nippon Kikai Gakkai Rombunshu, B, 69(682), p.1469 - 1476, 2003/06

no abstracts in English

Journal Articles

Study on point of net vapor generation by neutron radiography in subcooled boiling flow along narrow rectangular channels with short heated length

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:7 Percentile:61.85(Thermodynamics)

no abstracts in English

Journal Articles

ELM energy and particle losses and their extrapolation to burning plasma experiments

Loarte, A.*; Saibene, G.*; Sartori, R.*; Becoulet, M.*; Horton, L.*; Eich, T.*; Herrmann, A.*; Laux, M.*; Matthews, G.*; Jachmich, S.*; et al.

Journal of Nuclear Materials, 313-316, p.962 - 966, 2003/03

 Times Cited Count:98 Percentile:1.57(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Summary of the 5th Workshop on the Reduced Moderation Water Reactor; March 8, 2002, JAERI, Toaki

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

Journal Articles

Critical heat flux experiments in tight lattice core

Kureta, Masatoshi

JAERI-Conf 2002-012, p.47 - 52, 2002/12

no abstracts in English

Journal Articles

Effect of cladding pre-oxidation on rod coolability during reactivity accident conditions

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 1$$mu$$m-thick and 10$$mu$$m-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 1$$mu$$m and 10$$mu$$m rods.

Journal Articles

Critical heat flux correlation for subcooled boiling flow in narrow channels

Kureta, Masatoshi; Akimoto, Hajime

International Journal of Heat and Mass Transfer, 45(20), p.4107 - 4115, 2002/09

 Times Cited Count:30 Percentile:24.57(Thermodynamics)

no abstracts in English

Journal Articles

Fast measurement of ELM heat and particle fluxes, and plasma flow in the scrape-off layer of the JT-60U tokamak

Asakura, Nobuyuki; Sakurai, Shinji; Naito, Osamu; Itami, Kiyoshi; Miura, Yukitoshi; Higashijima, Satoru; Koide, Yoshihiko; Sakamoto, Yoshiteru

Plasma Physics and Controlled Fusion, 44(5A), p.A313 - A321, 2002/05

 Times Cited Count:22 Percentile:39.72(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Critical heat flux experiment for Reduced-Moderation Water Reactor (RMWR)

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

JAEA Reports

Study on critical heat flux in narrow rectangular channel with repeated-rib roughness, 1; Experimental facility and preliminary experiments

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

Journal Articles

Critical heat flux test on saw-toothed fin duct under one-sided heating conditions

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:5 Percentile:58.69(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Critical heat flux of subcooled boiling in high-heat-load narrow channels

Kureta, Masatoshi; Akimoto, Hajime

Nippon Kikai Gakkai Rombunshu, B, 67(662), p.2550 - 2557, 2001/10

no abstracts in English

Journal Articles

Impurity injection to plasmas with improved plasma confinement

Itami, Kiyoshi; Tamai, Hiroshi; Sakurai, Shinji; Kubo, Hirotaka; Konoshima, Shigeru; Asakura, Nobuyuki

Purazuma, Kaku Yugo Gakkai-Shi, 77(10), p.1027 - 1034, 2001/10

no abstracts in English

JAEA Reports

The 3rd technological meeting of Tokai reprocessing plant

Maki, Akira; ; Taguchi, Katsuya; ; Shimizu, Ryo; Shoji, Kenji;

JNC-TN8410 2001-012, 185 Pages, 2001/04

JNC-TN8410-2001-012.pdf:9.61MB

"The third technological meeting of Tokai Reprocessing plant (TRP)" was held in JNFL Rokkasyo site on March 14$$^{th}$$, 2001. The technical meetings have been held in the past two times. The first one was about the present status and future plan of the TRP and second one was about safety evaluation work on the TRP. At this time, the meeting focussed on the corrosion experrience, in-service inspection technology and future maintenance plan. The report contains the proceedings, transparancies and questionnaires of the meeting are contained.

86 (Records 1-20 displayed on this page)