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Showing results 1 to 11 of 11
Issue Date
Title / Author(s) / Citation
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2016-02
Development of Three-ring Conductance Sensor Based on FPCB for Measuring Liquid Film Thickness under Non-isothermal Condition
이규병
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2017-02
Extension of the Component Thermal-Hydraulics Analysis code CUPID toward Sub-channel Scale Analysis of PWR Reactor Core
윤석종
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2017-08
Experimental Measurement and Force Balance Analysis of Sliding Vapor Bubble Behavior on a Horizontal Tube
김유나
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2018-08
Improvement of Subchannel Scale Analysis Capability of CUPID with Grid-directed Cross Flow and Fuel Rod Models
김슬빈
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2019-08
Numerical Simulation of Structure Phase Change under High Heat Flux Condition Coupled with Nuclear System Analysis Code
최희수
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link
2019-08
CFD 해석을 기반으로 한 CUPID 부수로 단위 해석 모듈의 지지격자-유도 횡류 모델 개선
이재호
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link
2020
Establishment and Validation of Reactor Core Simulator for Subchannel Thermal-hydraulic and Neutron Transport Coupled Analysis
최유연
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link
2021
Coupling between subchannel module of CUPID and fuel code FINIX for multi-physics transient analysis of PWR core
박장근
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link
2021-02
Thermal-Structural Analysis of Micro Reactor Core Using Coupled OpenFOAM and Heat Pipe Code
정명진
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2021-02
해양원전 안전해석을 위한 MARS-KS motion model의 다차원 유동 해석능력 구현
박상욱
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2022
Thermal-hydraulic analysis of a floating nuclear reactor under ocean conditions using MARS-KS moving reactor model
서형주
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link
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