中文

王心安

Personal Information
Name (Pinyin): wxa
School/Department: 核科学与技术学院
Degree: Doctoral Degree in Engineering
Professional Title: Lecturer
Status: Employed

Recommended MA Supervisor

Paper Publications

Current position: Home > Scientific Research > Paper Publications

Numerical investigation on the core thermal hydraulic behavior of pool-type sodium-cooled fast reactor (SFR),
Numerical investigation for the heat transfer mechanisms between subchannels of bare rod bundles cooled by liquid sodium,
Generating Hexahedral Mesh for Wire-wrapped Fuel Assembly With RBF Mesh Deformation Method,
Hybrid medium model for conjugate heat transfer modeling in the core of sodium-cooled fast reactor,
Numerical Analysis of Steam Generator Tube Rupture Accident Phenomenon in Lead-Bismuth Cooled Reactor Using Input Parameter Range Evaluation Methodology,
Thermal Hydraulic and Neutronics Coupling Analysis for Plate Type Fuel in Nuclear Reactor Core,
A coupling analysis method of the thermal hydraulics and neutronics based on inverse distance weighted method,
一种适用于钠冷快堆绕丝棒束组件热工水力特性分析的多孔介质模型,

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