ICONE11-36452 EXPERIMENTAL STUDY ON COOLING LIMIT UNDER FLOW INSTABILITY IN BOILING FLOW CHANNEL

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Experiments on the Release of Gaseous Iodine from Gamma-Irradiated Aqueous CsI Solution and Influence of Oxygen and Methyl Isobutyl Ketone (MIBK)
Core Heat Transfer Coefficients Immediately Downstream of the Rewetting Front during Anticipated Operational Occurrences for BWRs
Modeling for Evaluation of Debris Coolability in Lower Plenum of Reactor Pressure Vessel
Unit Sphere Concept for Macroscopic Triggering of Large-scale Vapor Explosions
A Simple Evaluation Method of the Molten Fuel Amount in a Premixing Region of Fuel-Coolant Interactions
ICONE11-36609 Steady Streaming Associated with Forced Oscillation of Overlaid Immiscible Fluids
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A New Model for Onset of Net Vapor Generation in Fast Transient Subcooled Boiling
ICONE11-36298 SYSTEM PRESSURE EFFECT ON DENSITTY-WAVE INSTABILITY : SIMPLIFIED MODEL ANALYSIS AND EXPERIMENTS
ROSA/AP600 Testing : Facility Modifications and Initial Test Results
Small-scale Experiment on Subcooled Water Jet Injection into Molten Alloy by Using Fluid Temperature-Phase Coupled Measurement and Visualization
Internal-Shear Mode Instabilities on High-Speed Liquid Jet, (II) : Experimental Analysis of Curved Target Flow
Internal-Shear Mode Instabilities on High-Speed Liquid Jet, (I) : Characteristics of Linear Solutions
ICONE11-36288 OPTICAL MEASUREMENT OF WAVES ON HIGH-SPEED LITHIUM JET SIMULATING IFMIF TARGET FLOW
In-pile Experiment in JMTR on the Radiation Induced Surface Activation (RISA) Effect on Flow-boiling Heat Transfer
Interfacial Friction Factor for High-Pressure Steam/Water Stratified-Wavy Flow in Horizontal Pipe
ICONE11-36452 EXPERIMENTAL STUDY ON COOLING LIMIT UNDER FLOW INSTABILITY IN BOILING FLOW CHANNEL
Core Heat Transfer Coefficients Immediately Downstream of the Rewetting Front during Anticipated Operational Occurrences for BWRs
Experiment and Modeling for Solvent Leaching from Paint Matrix Considering Equilibrium
Reliability of Core Exit Thermocouple for Accident Management Action during SBLOCA and Abnormal Transient Tests at ROSA/LSTF
Performance of Core Exit Thermocouple for PWR Accident Management Action in Vessel Top Break LOCA Simulation Experiment at OECD/NEA ROSA Project
ICONE11-36363 A MELCOR CODE ANALYSIS OF AEROSOL BEHAVIOR IN ABWR CONTAINMENT WITH PCCS IN CASE OF TQUX SCENARIO
A simple mass and heat balance model for estimating plant conditions during the Fukushima Dai-ichi NPP accident
Assessment of current safety evaluation analysis on reflood behavior during PWR-LOCA by using CCTF data.
Experimental study of initial downcomer water accumulation velocity effects on reflood phase of PWR-LOCA.
Effect of loop seal on reflood phenomena in PWR.
Experimental Study on Difference in Reflood Core Heat Transfer among CCTF, FLECHT-SET and Predicted with FLECHT Correlation.
Core radial power profile effect on system and core cooling behavior during reflood phase of PWR-LOCA with CCTF data.
System pressure effect on system and core cooling behavior during reflood phase of PWR LOCA.
Water accumulation phenomena in upper plenum during reflood phase of PWR-LOCA by using CCTF data.
Experimental study on reflood behavior in PWR with upper plenum injection type ECCS by using CCTF.
Visual study of flow behavior in upper plenum during simulated reflood phase of PWR-LOCA.
Effect of decay heat level on reflood phenomena during PWR-LOCA.
Void fraction in simulated PWR fuel bundle during reflood phase.
Assessment of core radial power profile effect model for REFLA code by using CCTF data.
Pressure drop through broken cold leg during reflood phase of loss-of-coolant accident of pressurized water reactor.

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