ICONE11-36176 CONTAINMENT PRESSURE SUPPRESSION SYSTEM WITH FUNCTIONS OF WATER INJECTION AND NONCONDENSABLE GAS CONFINEMENT

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FEMAXI-6 Code Verification with MOX Fuels Irradiated in Halden Reactor
Study on Characteristics of Void Reactivity Coefficients for High-Conversion-Type Core of FLWR for MA Recycling
Core Heat Transfer Coefficients Immediately Downstream of the Rewetting Front during Anticipated Operational Occurrences for BWRs
Transport Mechanism of Thermohydraulic Instability in Natural Circulation Boiling Water Reactors during Startup
ROSA/AP600 Testing : Facility Modifications and Initial Test Results
ICONE11-36099 CRITICAL POWER CHARACTERISTICS OF TIGHT LATTICE BUNDLES
A Concept of Passive Safety Pressurized Water Reactor System with Inherent Matching Nature of Core Heat Generation and Heat Removal
ICONE11-36176 CONTAINMENT PRESSURE SUPPRESSION SYSTEM WITH FUNCTIONS OF WATER INJECTION AND NONCONDENSABLE GAS CONFINEMENT
Conceptual Design of Innovative Water Reactor for Flexible Fuel Cycle (FLWR) and its Recycle Characteristics
Estimates of Collective Doses from a Hypothetical Accident of a Nuclear Submarine
In-pile Experiment in JMTR on the Radiation Induced Surface Activation (RISA) Effect on Flow-boiling Heat Transfer
Core Heat Transfer Coefficients Immediately Downstream of the Rewetting Front during Anticipated Operational Occurrences for BWRs
A106 Safety System of a Submersible Compact Reactor SCR for Under-sea Research Vessel(Nuclear power-1/combustion)
Effect of Decontamination Factor on Core Neutronic Design of Light Water Reactors Using Recovered Uranium Reprocessed by Advanced Aqueous Method
Conceptual Design Study of 180MWt Small-Sized Reduced-Moderation Water Reactor Core
Application of PSA Methodology to Design Improvement of JAERI Passive Safety Reactor(JPSR)
Transient Analysis for Design of Primary Coolant Pump Adopted to JAERI Passive Safety Reactor JPSR
Evaluation on Driving Force of Natural Circulation in Downcomer for Passive Residual Heat Removal System in JAERI Passive Safety Reactor JPSR
Experiments of Two-phase Flow Dynamics of Marine Reactor Behavior under Heaving Motion
ICONE11-36470 CONCEPT OF PASSIVE SAFE SMALL REACTOR FOR DISTRIBUTED ENERGY SUPPLY SYSTEM
Effects by Sea Wave on Thermal Hydraulics of Marine Reactor System
H317 DESIGN OF ONE-THROUGH STEAM GENERATOR OF MARINE REACTOR MRX TO COUNTER FLOW INSTABILITY(Heat transfer with phase change)
Correlation among FBR core characteristics for various fuel compositions
A simple mass and heat balance model for estimating plant conditions during the Fukushima Dai-ichi NPP accident
Analysis of System Thermal Hydraulic Responses for Passive Safety Injection Experiment at ROSA-IV/Large Scale Test Facility. Using JAERI Modified Version of RELAP5/MOD2 Code.:Using JAERI Modified Version of RELAP5/MOD2 Code
Assessment of current safety evaluation analysis on reflood behavior during PWR-LOCA by using CCTF data.
Experimental study of ECC water injection rate effects on reflood phase of PWR-LOCA.
Experimental study of initial downcomer water accumulation velocity effects on reflood phase of PWR-LOCA.
Assessment of core thermo-hydrodynamic models of REFLA-1D code with CCTF data for reflood phase of PWR-LOCA.
Experimental study of system behavior during reflood phase of PWR-LOCA using CCTF.
Effect of loop seal on reflood phenomena in PWR.
CHF Experiments under Steady-State and Transient Conditions for Tight Lattice Core with Non-Uniform Axial Power Distribution.
Experimental Study on Difference in Reflood Core Heat Transfer among CCTF, FLECHT-SET and Predicted with FLECHT Correlation.
Burnout characteristics under flow reduction condition.
Response to Severe Changes of Load on the Reactor System of Nuclear Ship Mutsu.
Initial thermal-hydraulic behaviors under simultaneous ECC water injection into cold leg and upper plenum in a PWR-LOCA.
Air-Water Two-Phase Cross Flow Resistance in Rod Bundle
Experimental study of two-dimensional thermal-hydraulic behavior in core during reflood phase of PWR LOCA.
Visual study of flow behavior in upper plenum during simulated reflood phase of PWR-LOCA.

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