동향

Nuclear Technology Vol.127, No.2, AUG. 1999


A MELCOR-Based Model to Calculate Vapor Natural Circulation in pressurized Water Reactor High-Pressure Severe Accidents Modeling of the Rim Effect on Thermal Behavior of High-Burnup UO2 Fuel A Condensation Experiment in the Presence of Noncondensables in a Vertical Tube of a Passive Containment Cooling Syatem and Its Assessment with RELAP5/MOD3.2 Core Damage Serverity Evaluation for Pressurized Water Reactors by Use of Fuzzy Logic Algorithms Conceivable Limits for Thermal Reactor Spent-Fuel Recycling Matrix Diffusion of simple Cations, Anions, and Neutral Species in Fractured Evaluation of the Effect of Temperature on Potassium Clinoptilolite Ion Exchange Design of the European Spallation Source Liquid-Metal Target Using Computational Fluid Dynamics An Electrocatalyed Process for Leaching of Plutonium from Active Gauntles and Subsequent Separation by Solvent Extraction
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