UB Paderborn / Katalog / Suche / in CDI

JSME international journal. Ser. 2, Fluids engineering, heat transfer, power, combustion, thermophysical properties, 1990/11/15, Vol.33(4), pp.743-748

1990

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Effect of channel length on critical heat flux under conditions of high subcooling and high velocity in short heated channels

Heat transfer. Japanese research, 1998, Vol.27 (7), p.509-521

Sudo, Yukio

1998

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Present status of the High Temperature Engineering Test Reactor (HTTR)

Nuclear engineering and design, 1991-12, Vol.132 (1), p.85-93

1991

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Critical heat flux under conditions of high subcooling and high velocity at atmospheric pressure

Heat transfer. Japanese research, 1997, Vol.26 (1), p.16-29

Sudo, Yukio

1997

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Fuel temperature analysis method for channel-blockage accident in HTTR

Nuclear engineering and design, 1994-09, Vol.150 (1), p.69-80

1994

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Study of injected water subcooling effect on falling water limitation in countercurrent two-phase flow in vertical channels

Heat transfer. Japanese research, 1996, Vol.25 (1), p.25-38

Sudo, Yukio

1996

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Analytical study on characteristics of critical heat flux under high subcooling and high velocity conditions

Heat transfer. Japanese research, 1995, Vol.24 (8), p.701-716

SUDO, Y

1995

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Evaluation of Local Power Distribution with Fine-mesh Core Model for High Temperature Engineering Test Reactor (HTTR)

Journal of nuclear science and technology, 1994-01, Vol.31 (1), p.62-72

1994

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Design and safety consideration in the High-Temperature engineering Test Reactor (HTTR)

Energy (Oxford), 1991, Vol.16 (1), p.449-458

1991

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Performance of passive heat removal by an air-cooling panel from a high-temperature gas-cooled reactor

Heat transfer, Asian research, 2002-12, Vol.31 (8), p.665-677

2002

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Improvement of Critical Heat Flux Correlation for Research Reactors using Plate-Type Fuel

Experimental measurement of frictional law under CCFL in porous debris: Festschrift Edition celebrating the 70th Birthday of Prof. Bal Raj Sehgal. Invited Papers on Core mel accidents in LWRs State of the art of Coolability of Porous Debris

Evaluation of core thermal and hydraulic characteristics of HTTR

Parameter Effects on Downcomer Penetration of ECC Water in PWR-LOCA

Evaluation of Hot Spot Factors for Thermal and Hydraulic Design of HTTR

Analytical Study on Thermal-Hydraulic Behavior of Transient from Forced Circulation to Natural Circulation in JRR-3

Experimental Study of Incipient Nucleate Boiling in Narrow Vertical Rectangular Channel Simulating Subchannel of Upgraded JRR-3

Critical heat flux at high velocity channel flow with high subcooling

Prediction of Dryout Heat Flux for Particle Bed Simulating Degraded Core in LWR Severe Core Damage Accidents

Experimental Study of Differences in Single-Phase Forced-Convection Heat Transfer Characteristics between Upflow and Downflow for Narrow Rectangular Channel

Heat Transfer Calculation of Simulated Heater Rods throughout Reflood Phase in Postulated PWR-LOCA Experiments

Effects of Partial Flow Blockage on Core Heat Transfer in Forced-Feed Reflood Tests

Effects of Radial Core Power Profile on Core Thermo-Hydraulic Behavior during Reflood Phase in PWR-LOCAs

Experimental Study of Upper Core Quench in PWR Reflood Phase

Experimental and Numerical Studies on Performance of Passive Decay Heat Removal by a Water Cooling Panel from a High-Temperature Gas-Cooled Reactor

Heat Transfer Characteristics in Narrow Vertical Rectangular Channels Heated from Both Sides

Effect of channel length on critical heat flux under conditions of high subcooling and high velocity in short heated channels

Present status of the High Temperature Engineering Test Reactor (HTTR)

Critical heat flux under conditions of high subcooling and high velocity at atmospheric pressure

Fuel temperature analysis method for channel-blockage accident in HTTR

Study of injected water subcooling effect on falling water limitation in countercurrent two-phase flow in vertical channels

Analytical study on characteristics of critical heat flux under high subcooling and high velocity conditions

Evaluation of Local Power Distribution with Fine-mesh Core Model for High Temperature Engineering Test Reactor (HTTR)

Design and safety consideration in the High-Temperature engineering Test Reactor (HTTR)

Performance of passive heat removal by an air-cooling panel from a high-temperature gas-cooled reactor

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