MARUYAMA Yu | Japan Atomic Energy Agency

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著作論文

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
Evaluation of Containment Failure Probability by Ex-Vessel Steam Explosion in Japanese LWR Plants
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
A New Model for Onset of Net Vapor Generation in Fast Transient Subcooled Boiling
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
A simple mass and heat balance model for estimating plant conditions during the Fukushima Dai-ichi NPP accident

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