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          Abstract
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          Abstract
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          Abstract
          Articles in press have been peer-reviewed and accepted, which are not yet assigned to volumes /issues, but are citable by Digital Object Identifier (DOI).
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          Abstract
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          Abstract
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          Abstract
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          Abstract PDF
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          Abstract
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          Abstract PDF
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          Abstract PDF
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          Abstract
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          Abstract
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          Abstract
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          Abstract
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          Abstract PDF
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          Abstract
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          Abstract
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          Abstract PDF
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          Abstract
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          Abstract
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          Abstract
          Study on Application Characteristic of Hot-pressing B4C Block in ITER Diagnostic Equatorial Port 12
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          DOI: 10.7538/yzk.2023.youxian.0793
          Abstract
          Study on Interface Wetting Mechanism between High-temperature Liquid Sodium and Stainless Steel
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          Abstract
          Research Progress on Critical Heat Flux of Fuel Assemblies in Small Modular Reactors
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          Abstract
          Study on Vibration Response Mechanism of Tube Bundle for Helical Coil Steam Generator
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          Abstract
          Phase Evolution in Dissolution Reactions between Power Reactor High Level Liquid Waste Calcines and Basic Glass
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          Abstract
          Comparative Study of P507-impregnated Polystyrene and Polyacrylate Resins for Separation of Yb/Lu
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          Abstract PDF
          Research on Behavior of Natural Circulation of Coolant in Primary Circuit System of Pool Type Fast Reactor
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          Abstract
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          DOI: 10.7538/yzk.2024.youxian.0310
          Abstract PDF
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          Abstract
          Research on Structure Design Method and Performance Analysis of Arc Plates Capacitive Drum Position Detector
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          Abstract
          Research on Loading and Extrapolation Criticality Experiment Technology of New Heat Pipe Reactor
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          Abstract
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          Abstract PDF
          Numerical Simulation Study on Swirl Vane Separator under Rolling Motion Condition
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          Abstract PDF
          Study on Optimization Methods for Miniaturization and Lightweight Design of Micro Lead-bismuth Cooled Reactor
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          Abstract
          Numerical Simulation of Multi-field Coupled Corrosion Behavior of Core Cladding in Lead-bismuth Fast Reactor
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          Abstract
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          Abstract
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          Abstract
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          Abstract
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