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Dongyeol Yeo
Dongyeol Yeo
Other namesDong Yeol Yeo
Korea Atomic Energy Research Institute (KAERI)
No verified email
Title
Cited by
Cited by
Year
Modeling film boiling within chimney-structured porous media and heat pipes
DY Yeo, HC No
International Journal of Heat and Mass Transfer 124, 576-585, 2018
162018
Modeling heat transfer through chimney-structured porous deposit formed in pressurized water reactors
DY Yeo, HC No
International Journal of Heat and Mass Transfer 108, 868-879, 2017
162017
Modeling heat transfer through corrosion product deposits on fuel rods in pressurized water reactors
DY Yeo, HC No
Nuclear Engineering and Design 342, 308-319, 2019
112019
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, HC No
International Journal of Heat and Mass Transfer 141, 554-568, 2019
72019
Modeling crust fracture and water ingression through crust during top-flooding strategy for corium cooling
DY Yeo, HC No
Nuclear Engineering and Design 342, 219-230, 2019
62019
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, 2013
52013
Effect of porous media on heat removal capability during normal and severe accident conditions of PWR
DY Yeo
한국과학기술원, 2018
32018
Modeling of annular gap thickness formed by interaction between corium and water in lower head of reactor vessel
MW Song, HC No, J Kim, M Kim, D Yeo, SH Yoon, HJ Yoon
Nuclear Engineering and Design 369, 110841, 2020
22020
A simple model for the quench front propagation in a highly superheated particle bed
DY Yeo, HC No
International Journal of Heat and Mass Transfer 136, 644-654, 2019
12019
Development of a two-phase flow model in MAMBA for Crud-Induced Localized Corrosion Modeling Capability
AJ Yeo, Dongyeol, Huxford, V Petrov, A Manera
The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics …, 2022
2022
Application of Machine Learning for Online Discovery of Component Degradation Dynamics
D Yeo, V Petrov, A Manera
The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics …, 2022
2022
Modeling of in-vessel gap cooling and its validation against LAVA, ALPHA, and LMP200 experiments
MW Song, D Yeo, HC No
Nuclear Engineering and Design 374, 111028, 2021
2021
A Meso-scale Two-phase Mixture Model for the Prediction of Boiling and Dryout in CRUD
D Yeo, AJ Huxford, A Manera
CASL Virtual Meeting, 448-450, 2020
2020
Evaluation of Gap Size Formed by Interaction between Melt and Water in RPV Lower Head
MW Song, D Yeob, HC NO
2020
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
2019
A Zero-Dimensional Model for Dryout Heat Flux of Debris Bed Considering Interfacial Friction Between Two Phases
DY Yeo, HC No
ANS annual meeting 2019, 2019
2019
A Model for Growth and Fracture of Crust Before Water Ingression
DY Yeo, HC No
ANS Annual meeting 2018, 2018
2018
A Dryout Model of CRUD
DY Yeo, HC No
ANS Annual meeting 2018, 2018
2018
Modeling Heat Transfer through CRUD
DY Yeo, HC NO
KNS annual meeting 2017, 2017
2017
Understanding of CHF enhancement mechanisms with millimeter-scale fin structures
JY Choi, HC No, DY Yeo
2015
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