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Search Results: Records 1-20 displayed on this page of 32

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Journal Articles

Heat transfer coefficient modeling for downward saturated boiling flows in vertical pipes

Wada, Yuki; Shibamoto, Yasuteru; Hibiki, Takashi*

International Journal of Heat and Mass Transfer, 249, p.127219_1 - 127219_16, 2025/10

https://doi.org/10.1016/j.ijheatmasstransfer.2025.127219
 Times Cited Count：2 Percentile：64.77(Thermodynamics)

Journal Articles

Heat transfer characteristics of downward saturated boiling flow in vertical round pipes

Wada, Yuki; Shibamoto, Yasuteru; Hibiki, Takashi*

International Journal of Heat and Mass Transfer, 239, p.126598_1 - 126598_18, 2025/04

https://doi.org/10.1016/j.ijheatmasstransfer.2024.126598
 Times Cited Count：7 Percentile：41.20(Thermodynamics)

Journal Articles

Evaluation on driving force of natural circulation in downcomer for passive residual heat removal system in JAERI passive safety reactor JPSR

Kunii, Katsuhiko; Iwamura, Takamichi; Murao, Yoshio

Journal of Nuclear Science and Technology, 34(1), p.21 - 29, 1997/01

https://doi.org/10.3327/jnst.34.21
 Times Cited Count：1 Percentile：14.48(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Conceptual design of the JAERI passive safety reactor and its thermal-hydraulic characteristics

Murao, Yoshio; Araya, Fumimasa; Iwamura, Takamichi; Okumura, Keisuke

Transactions of the American Nuclear Society, 71, p.527 - 529, 1995/00

no abstracts in English

Journal Articles

Conceptual design of JAERI passive safety reactor (JPSR) and its thermal-hydraulic characteristics

Murao, Yoshio; Araya, Fumimasa; Iwamura, Takamichi; Okumura, Keisuke

10th Proc. of Nuclear Thermal Hydraulics, 0, p.3 - 12, 1994/00

no abstracts in English

Journal Articles

Experimental study of differences in CHF between upflow and downflow in vertical rectangular channels; Effect of subcooling

Kaminaga, Masanori; Sudo, Yukio

Nihon Kikai Gakkai Rombunshu, B, 58(553), p.2799 - 2804, 1993/09

https://doi.org/10.1299/kikaib.58.2799

no abstracts in English

Journal Articles

A New CHF correlation scheme proposed for vertical rectangular channels heated from both sides in nuclear research reactors

Sudo, Yukio; Kaminaga, Masanori

J. Heat Transfer, 115, p.426 - 434, 1993/05

https://doi.org/10.1115/1.2910695
 Times Cited Count：65 Percentile：93.85(Thermodynamics)

no abstracts in English

Journal Articles

Test results of the DPC-TJ; Thermal and hydraulic performances

Sugimoto, Makoto; Kato, Takashi; Kawano, Katsumi; Hiyama, Tadao; ; ; ; ; ; Okuno, Kiyoshi; et al.

Teion Kogaku, 27(3), p.239 - 244, 1992/00

https://doi.org/10.2221/jcsj.27.239

no abstracts in English

Journal Articles

Experimental study of the critical heat flux in a narrow vertical rectangular channel

Kaminaga, Masanori; Sudo, Yukio; Murayama, Yoji;

Heat Transfer-Jpn. Res., 20(1), p.72 - 85, 1991/03

no abstracts in English

Journal Articles

A New CHF correlation scheme proposed for vertical rectangular channels heated from both sides in nuclear research reactors

Kaminaga, Masanori; Sudo, Yukio

Proc. of the 1st JSME/ASME Joint Int. Conf. on Nuclear Engineering,Vol. 1, p.73 - 79, 1991/00

no abstracts in English

Journal Articles

Safety criterion for burnout of the plate-type fuel in pressurized conditions

; Kaminaga, Masanori; ; Ando, Hiroei; Sudo, Yukio; Saito, Minoru;

Proc. of the Asian Symp. on Research Reactor, p.1 - 8, 1991/00

no abstracts in English

Journal Articles

Heat transfer characteristics in narrow vertical rectangular channels heated from both sides

Sudo, Yukio; ; Kaminaga, Masanori

JSME Int. J., Ser. II, 33(4), p.743 - 748, 1990/00

no abstracts in English

Journal Articles

Combined forced and free convective heat transfer characteristics in narrow vertical rectangular channel heated from both sides

Sudo, Yukio; Kaminaga, Masanori;

Journal of Nuclear Science and Technology, 24(5), p.355 - 364, 1987/05

https://doi.org/10.3327/jnst.24.355
 Times Cited Count：7 Percentile：59.29(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Dynamic Behavior of Pipe under Loss of Coolant Accident

Ueda, Shuzo

JAERI-M 87-027, 179 Pages, 1987/03

JAERI-M-87-027.pdf:5.43MB

no abstracts in English

JAEA Reports

Evaluation Report on CCTF Core-II Reflood Test C2-3(Run 61); Investigation of Initial Downcomer Water Accumulation Velocity Effects

; ; ; ; ; Murao, Yoshio

JAERI-M 86-185, 95 Pages, 1987/01

JAERI-M-86-185.pdf:2.02MB

no abstracts in English

JAEA Reports

Core Heat Transfer Experiment for JRR-3 to BE Upgraded at 20MWt (PartII:Experimental Study on the Condition of Onset of Nucleate Boiling (ONB) and Departure from Nucleate Boiling (DNB) Heat Flux in a Vertical Rectangular Channel)

Sudo, Yukio; ; ; ; Kaminaga, Masanori

JAERI-M 85-126, 95 Pages, 1985/09

JAERI-M-85-126.pdf:2.43MB

no abstracts in English

Journal Articles

Experimental study of incipient nucleate boiling in narrow vertical rectangular channel simulating subchannel of upgraded JRR-3

Sudo, Yukio; ; ; Kaminaga, Masanori

Journal of Nuclear Science and Technology, 23(1), p.73 - 82, 1985/00

https://doi.org/10.3327/jnst.23.73
 Times Cited Count：38 Percentile：94.59(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Experimental study of differences in single-phase forced-convection heat transfer characteristics between upflow and downflow for narrow rectangular channel

Sudo, Yukio; ; ; ; Kaminaga, Masanori

Journal of Nuclear Science and Technology, 22(3), p.202 - 212, 1985/00

https://doi.org/10.3327/jnst.22.202
 Times Cited Count：40 Percentile：95.57(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Characteristics of countercurrent gas-liquid two-phase flow in vertical tubes

;

Journal of Nuclear Science and Technology, 19(12), p.985 - 996, 1982/00

https://doi.org/10.3327/jnst.19.985
 Times Cited Count：44 Percentile：95.46(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Transient analysis of blowdown thrust force under PWR・LOCA conditions

; ;

Nihon Genshiryoku Gakkai-Shi, 24(9), p.723 - 733, 1982/00

https://doi.org/10.3327/jaesj.24.723
 Times Cited Count：5 Percentile：52.60(Nuclear Science & Technology)

no abstracts in English

32 (Records 1-20 displayed on this page)