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Journal Articles

Prediction of heater surface temperature change at subcooled flow boiling DNB

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.

Journal Articles

CHF experiments under steady-state and transient conditions for tight lattice core with non-uniform axial power distribution

Iwamura, Takamichi; Watanabe, Hironori; Okubo, Tsutomu; Araya, Fumimasa; Murao, Yoshio

Journal of Nuclear Science and Technology, 30(5), p.413 - 424, 1993/05

 Times Cited Count:2 Percentile:29.78(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Accident simulation tests for high conversion light water reactor using a high pressure water loop

Iwamura, Takamichi; Watanabe, Hironori; Araya, Fumimasa; Okubo, Tsutomu; Murao, Yoshio

JAERI-M 92-050, 46 Pages, 1992/03

JAERI-M-92-050.pdf:1.24MB

no abstracts in English

JAEA Reports

Critical heat flux experiments for high conversion light water reactor, 3; Heated length: 0.5$$sim$$1.0m, P/D: 1.126$$sim$$1.2, number of rods: 4$$sim$$7

Iwamura, Takamichi; Okubo, Tsutomu; *; ; Murao, Yoshio

JAERI-M 90-044, 158 Pages, 1990/03

JAERI-M-90-044.pdf:2.81MB

no abstracts in English

Journal Articles

Transient burnout under rapid flow reduction condition

Journal of Nuclear Science and Technology, 24(10), p.811 - 820, 1987/10

 Times Cited Count:4 Percentile:44.89(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Study of Transient Burnout under Flow Reduction Condition

JAERI-M 86-135, 89 Pages, 1986/09

JAERI-M-86-135.pdf:2.43MB

no abstracts in English

JAEA Reports

Study of Transient Burnout Characteristics under Flow Reduction Condition

;

JAERI 1290, 42 Pages, 1984/03

JAERI-1290.pdf:2.2MB

no abstracts in English

Journal Articles

Burnout characteristics under flow reduction condition

;

Journal of Nuclear Science and Technology, 19(6), p.438 - 448, 1982/00

 Times Cited Count:9 Percentile:68.89(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Flow Reduction Transient Burnout in a Vertical Tube,1

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JAERI-M 8774, 138 Pages, 1980/03

JAERI-M-8774.pdf:3.38MB

no abstracts in English

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