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Showing results 1 to 22 of 22

Issue Date	Title / Author(s) / Citation	File
2000	후기 재관수 동안 KNGR 강수부 내 수력현상에 대한 실험 연구 조형규	link
2004	Scaling analysis for the multidimensional phenomena of the ECC bypass during an LBLOCA with the direct vessel injection 조형규	link
2006	공간구조 분석을 위한 각도가중 ERAM 모델의 구축 및 적용 조형규	link
2013-08	Experiment on Critical Heat Flux under Rolling Condition for 황진석	view file
2013-08	Enhancement and Optimization on Cooling Performance of Gas-based Fusion Reactor Blanket using Binary 박일웅	view file
2015-02	Evaluation of Long Term Core Cooling Capability Considering LOCA-generated Debris 서정관	view file
2016-02	Experimental Study for Development of Wall and Interfacial Friction Models in Two-dimensional Film Flow 양진화	view file
2016-02	Development of Three-ring Conductance Sensor Based on FPCB for Measuring Liquid Film Thickness under Non-isothermal Condition 이규병	view file
2017-02	Extension of the Component Thermal-Hydraulics Analysis code CUPID toward Sub-channel Scale Analysis of PWR Reactor Core 윤석종	view file
2017-08	Experimental Measurement and Force Balance Analysis of Sliding Vapor Bubble Behavior on a Horizontal Tube 김유나	view file
2018-08	Improvement of Subchannel Scale Analysis Capability of CUPID with Grid-directed Cross Flow and Fuel Rod Models 김슬빈	view file
2019-02	선박용 원자로 열수력 해석을 위한 MARS-KS 동적운동모델 개선 범희관	view file
2019-08	Numerical Simulation of Structure Phase Change under High Heat Flux Condition Coupled with Nuclear System Analysis Code 최희수	view file link
2019-08	CFD 해석을 기반으로 한 CUPID 부수로 단위 해석 모듈의 지지격자-유도 횡류 모델 개선 이재호	view file link
2020	Establishment and Validation of Reactor Core Simulator for Subchannel Thermal-hydraulic and Neutron Transport Coupled Analysis 최유연	view file link
2020	Development of mechanistic boiling heat partitioning model for horizontal tube under natural convection 김재순	view file link
2021	Coupling between subchannel module of CUPID and fuel code FINIX for multi-physics transient analysis of PWR core 박장근	view file link
2021	Experimental investigation of critical heat flux on a single heater rod under inclined and rolling conditions 김건우	view file link
2021	Modelling of Liquid Film Off-take in Reactor Vessel Upper Downcomer Based on High-fidelity Experiment and Simulation 최치진	view file link
2021-02	해양원전 안전해석을 위한 MARS-KS motion model의 다차원 유동 해석능력 구현 박상욱	view file link
2021-02	Thermal-Structural Analysis of Micro Reactor Core Using Coupled OpenFOAM and Heat Pipe Code 정명진	view file link
2022	Thermal-hydraulic analysis of a floating nuclear reactor under ocean conditions using MARS-KS moving reactor model 서형주	view file link

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