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Nuclear Thermal Hydraulics

1st ed. 2016., 2016

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Core design study on rock-like oxide fuel light water reactor and improvements of core characteristics

Journal of nuclear materials, 1999-08, Vol.274 (1), p.139-145

1999

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Summary of ROSA-IV LSTF first-phase test program — Integral simulation of PWR small-break LOCAs and transients

Nuclear engineering and design, 1991-10, Vol.131 (1), p.101-111

1991

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Plutonium rock-like fuel burning in LWR

Progress in nuclear energy (New series), 1998, Vol.32 (3), p.539-546

1998

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Phase and velocity distributions and holdup in high-pressure steam/water stratified flow in a large diameter horizontal pipe

International journal of multiphase flow, 1987, Vol.13 (2), p.145-159

1987

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Secondary-Side Depressurization during PWR Cold-Leg Small Break LOCAs Based on ROSA-V/LSTF Experiments and Analyses

Journal of nuclear science and technology, 1998-12, Vol.35 (12), p.905-915

1998

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Experimental investigation on similarity between velocity and density profiles in density-stratified countercurrent flow in reactor horizontal leg

Nuclear engineering and design, 2000-09, Vol.201 (1), p.83-98

2000

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Neutron Radiography Flow Visualization of Liquid Metal Injected into an Empty Vessel and a Vessel Containing Saturated Water

Nuclear technology, 2001-01, Vol.133 (1), p.119-132

2001

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Water Flow Simulation Test on Flow-Induced Oscillation of Thermowell in Prototype Fast Breeder Reactor “MONJU”

JSME International Journal Series B Fluids and Thermal Engineering, 2001, Vol.44(4), pp.688-694

2001

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Thermal–hydraulic characteristics of a next-generation reactor relying on steam generator secondary side cooling for primary depressurization and long-term passive core cooling

Nuclear engineering and design, 1998-09, Vol.185 (1), p.83-96

1998

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Core Liquid Level Responses Due to Secondary-Side Depressurization during PWR Small Break LOCA

Journal of nuclear science and technology, 1998-02, Vol.35 (2), p.113-119

1998

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ROSA-III Base Test Series for a Large Break Loss-of-Coolant Accident in a Boiling Water Reactor

Nuclear technology, 1982-05, Vol.57 (2), p.179-191

1982

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Recirculation Pump Discharge Line Break Tests at ROSA-III for a Boiling Water Reactor

Nuclear technology, 1985-08, Vol.70 (2), p.189-203

1985

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Visualization of Simulated Molten-Fuel Behavior in a Pressure Vessel Lower Head Using High-Frame-Rate Neutron Radiography

Nuclear technology, 1999-02, Vol.125 (2), p.213-224

1999

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Bernoulli’s Equation (Mechanics of Ideal Fluids)

Nuclear Thermal Hydraulics, 2016, p.89-97

2016

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Analyses of ROSA-III Break Area Spectrum Experiments on a Boiling Water Reactor Loss-of-Coolant Accident

Nuclear technology, 1985-12, Vol.71 (3), p.628-643

1985

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Two-Phase Flow

Nuclear Thermal Hydraulics, 2016, p.173-191

2016

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Thermal Hydraulics Inside the Reactor

Nuclear Thermal Hydraulics, 2016, p.375-410

2016

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Series Aims and Scopes

Nuclear Thermal Hydraulics, 2016, Vol.4

2016

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Laminar Flow and Turbulent Flow (The Similarity Rule)

Nuclear Thermal Hydraulics, 2016, p.143-151

2016

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Reactor Thermal Design

Nuclear Thermal Hydraulics, 2016, p.411-426

2016

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Gas Turbine Cycles and Steam Cycles

Nuclear Thermal Hydraulics, 2016, p.49-63

2016

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Reactor Heat Production

Nuclear Thermal Hydraulics, 2016, p.209-241

2016

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Convective Heat Transfer

Nuclear Thermal Hydraulics, 2016, p.273-313

2016

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Flow Oscillations

Nuclear Thermal Hydraulics, 2016, p.193-205

2016

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Nuclear Thermal Hydraulics

Core design study on rock-like oxide fuel light water reactor and improvements of core characteristics

Summary of ROSA-IV LSTF first-phase test program — Integral simulation of PWR small-break LOCAs and transients

Plutonium rock-like fuel burning in LWR

Phase and velocity distributions and holdup in high-pressure steam/water stratified flow in a large diameter horizontal pipe

Secondary-Side Depressurization during PWR Cold-Leg Small Break LOCAs Based on ROSA-V/LSTF Experiments and Analyses

Experimental investigation on similarity between velocity and density profiles in density-stratified countercurrent flow in reactor horizontal leg

Neutron Radiography Flow Visualization of Liquid Metal Injected into an Empty Vessel and a Vessel Containing Saturated Water

Water Flow Simulation Test on Flow-Induced Oscillation of Thermowell in Prototype Fast Breeder Reactor “MONJU”

Thermal–hydraulic characteristics of a next-generation reactor relying on steam generator secondary side cooling for primary depressurization and long-term passive core cooling

Core Liquid Level Responses Due to Secondary-Side Depressurization during PWR Small Break LOCA

ROSA-III Base Test Series for a Large Break Loss-of-Coolant Accident in a Boiling Water Reactor

Recirculation Pump Discharge Line Break Tests at ROSA-III for a Boiling Water Reactor

Visualization of Simulated Molten-Fuel Behavior in a Pressure Vessel Lower Head Using High-Frame-Rate Neutron Radiography

Bernoulli’s Equation (Mechanics of Ideal Fluids)

Analyses of ROSA-III Break Area Spectrum Experiments on a Boiling Water Reactor Loss-of-Coolant Accident

Two-Phase Flow

Thermal Hydraulics Inside the Reactor

Series Aims and Scopes

Laminar Flow and Turbulent Flow (The Similarity Rule)

Reactor Thermal Design

Gas Turbine Cycles and Steam Cycles

Reactor Heat Production

Convective Heat Transfer

Flow Oscillations

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