Development of the VESUVIUS Code for Steam Explosion Analysis : Part 1 : Molten Jet Breakup Modeling

スポンサーリンク

概要

著者

関連論文

Evaluation Methods for Corrosion Damage of Components in Cooling Systems of Nuclear Power Plants by Coupling Analysis of Corrosion and Flow Dynamics (II) : Evaluation of Corrosive Conditions in PWR Secondary Cooling System
Evaluation Methods for Corrosion Damage of Components in Cooling Systems of Nuclear Power Plants by Coupling Analysis of Corrosion and Flow Dynamics (I) : Major Targets and Development Strategies of the Evaluation Methods
Deterministic Trigger Model for the VESUVIUS Steam Explosion Code
Development of the VESUVIUS Code for Steam Explosion Analysis : Part 2 : Verification of Jet Breakup Modeling
Development of the VESUVIUS Code for Steam Explosion Analysis : Part 1 : Molten Jet Breakup Modeling
Reflux Condensation Heat Transfer of Steam-Air Mixture under Turbulent Flow Conditions in a Vertical Tube
Evaluation of Reflux Condensation Heat Transfer of Steam-Air Mixtures under Gas-Liquid Countercurrent Flow in a Vertical Tube
Prediction of Dryout Heat Flux Using Film Flow Model
Critical Power Analysis with Mechanistic Models for Nuclear Fuel Bundles,(I) Models and Verifications for Boiling Water Reactor Application
Analysis on Pipe Rupture of Steam Condensation Line at Hamaoka-1, (II) Hydrogen Combustion and Pipe Deformation
Analysis on Pipe Rupture of Steam Condensing Line at Hamaoka-1, (I) Accumulation of Non-condensable Gas in a Pipe
Severe Accident Analysis Code SAMPSON Improvement for IMPACT Project(Special Issue on International Conference on Power and Energy System)

もっと見る

スポンサーリンク