Dongyeol Yeo
机构: Korea Atomic Energy Research Institute (KAERI)
每年引用次数
引用次数
引用: 73
H-指数: 5
I10-指数 : 3
出版物: 26
Modeling of in-vessel gap cooling and its validation against LAVA, ALPHA, and LMP200 experiments
Hee Cheon No , Moon Won Song , Dongyeol Yeo
Nuclear Engineering and Design 374 111028
2021
Modeling of annular gap thickness formed by interaction between corium and water in lower head of reactor vessel
Moon Won Song , Hee Cheon NO , Jegon Kim , Minju Kim
Nuclear Engineering and Design 369 110841
1
2020
A model for growth and fracture of crust before water ingression
Dongyeol Yeo , Hee-Cheon No
2018 Iron and Steel Technology Conference and Exposition 1265 -1267
2018
A dryout model of crud
Dongyeol Yeo , Hee-Cheon No
2018 Transactions of the American Nuclear Society, ANS 2018 and Embedded Topical Meeting Nuclear Fuels and Structural Materials 1281 -1282
2018
Transient Analysis of Corium Coolability Considering Water Ingression into Debris Bed and Corium-to-Vessel Gap
Moon Won Song , Dongyeol Yeo , Jegon Kim , Seunghyun Yoon
Parametric study of the fuel salt drain system design of K-MSR
Dongyeol Yeo , Chan Lee , Gyeong-Hoi Koo
2024
Application of Machine Learning for Online Discovery of Component Degradation Dynamics
Dongyeol Yeo , Victor Petrov , Annalisa Manera
The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19) 35385 -35385
2022
A Meso-scale Two-phase Mixture Model for the Prediction of Boiling and Dryout in CRUD
Dongyeol Yeo , Aaron J. Huxford , Annalisa Manera
CASL Virtual Meeting 448 -450
2020
Preliminary Core Cavity Design of a Micro Molten Salt Reactor (MSR) Using CFD Code
Yong Hwan Yoo , Wooseong Park , Taewoo Kim , Dongyeol Yeo
Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 8-10, 2024
2024
Modeling heat transfer through chimney-structured porous deposit formed in pressurized water reactors
DY Yeo , Hee-Cheon No
International Journal of Heat and Mass Transfer 108 868 -879
6
2017
Modeling film boiling within chimney-structured porous media and heat pipes
DY Yeo , Hee-Cheon No
International Journal of Heat and Mass Transfer 124 576 -585
4
2018
A zero-dimensional dryout heat flux model based on mechanistic interfacial friction models for two-phase flow regimes with channel flow in a packed bed
DY Yeo , Hee-Cheon No
International Journal of Heat and Mass Transfer 141 554 -568
2
2019
Modeling crust fracture and water ingression through crust during top-flooding strategy for corium cooling
DY Yeo , Hee-Cheon No
Nuclear Engineering and Design 342 219 -230
3
2019
A simple model for the quench front propagation in a highly superheated particle bed
DY Yeo , Hee-Cheon No
International Journal of Heat and Mass Transfer 136 644 -654
2019
Corrigendum to “Modeling crust fracture and water ingression through crust during top-flooding strategy for corium cooling” [Nucl. Eng. Des. 342 (2019) 219–230]
DY Yeo , HC NO ,
Nuclear Engineering and Design 345 252
2019
Analysis of CHF enhancement by heater surface fin structure ranging from micrometer-fin scale to centimeter-fin scale
J Choi , HC No , DY Yeo
Proceedings of ICAPP
5
2013
Evaluation of Gap Size Formed by Interaction between Melt and Water in RPV Lower Head
Moon Won Song , Dongyeol Yeob , Hee Cheon NO
2020
A Preliminary Thermal Analysis and Modeling Study of MSRE Freeze Valve for K-MSR Valve Development
Chan Leea , Dongyeol Yeob , Gyeong-Hoi Koob
Modeling Heat Transfer through CRUD
Dong Yeol Yeoa , Hee Cheon NOa
2017
Development of a two-phase flow model in MAMBA for Crud-Induced Localized Corrosion Modeling Capability
Aaron J. Yeo , Dongyeol , Huxford , Victor Petrov
The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19) 35384 -35384
2022