Wettability and CHF limits of Accident-Tolerant nuclear fuel cladding materials in light water reactor conditions

GY Su, TA Moreira, D Lee, A Jena, G Wang… - Applied Thermal …, 2022 - Elsevier
We present the results of experimental investigations aimed at evaluating the thermal–
hydraulic performance of chromium-coated zircaloy, ie, one of the most promising accident …

Progress in multiphase computational fluid dynamics

RT Lahey Jr, E Baglietto, IA Bolotnov - Nuclear Engineering and Design, 2021 - Elsevier
This paper is primarily concerned with the development of three dimensional (3-D)
multiphase computational fluid dynamics models for use in Pressurized Water Nuclear …

[HTML][HTML] Benchmark DEBORA: Assessment of MCFD compared to high-pressure boiling pipe flow measurements

G Bois, P Fillion, F François, A Burlot, ABH Ali… - International Journal of …, 2024 - Elsevier
A benchmark activity on two-fluid simulations of high-pressure boiling upward flows in a pipe
is performed by 12 participants using different MCFD (Multiphase Computational Fluid …

Numerical investigation of flow boiling characteristics in narrow rectangular channels using two-fluid Eulerian CFD model covering a wide range of pressures

J Han, W He, Y Liu, D Gao, C Zhao, H Bo - Applied Thermal Engineering, 2024 - Elsevier
Narrow channel heat exchange technology is one of the key technologies for the
development of integrated small modular reactors (SMR). The 'wall heat flux …

Bubble departure and sliding in high-pressure flow boiling of water

A Kossolapov, MT Hughes, B Phillips… - Journal of Fluid …, 2024 - cambridge.org
Bubble growth, departure and sliding in low-pressure flow boiling has received considerable
attention in the past. However, most applications of boiling heat transfer rely on high …

Experimental investigation and modeling of falling film heat transfer on partial dry-out condition

P Zhang, R Chen, GH Su, W Tian, S Qiu - Applied Thermal Engineering, 2023 - Elsevier
Falling film heat transfer has been applied for decay heat removal in more and more nuclear
reactors, in which the coolant feed rate is set small to prolong the effective cooling time …

Assessment of State-of-the-art multiphase CFD modeling for subcooled flow boiling in reactor applications

M Pham, G Bois, F Francois, E Baglietto - Nuclear Engineering and Design, 2023 - Elsevier
Abstract Multiphase Computational Fluid Dynamics (M-CFD) has the potential to provide
high fidelity simulation of complex boiling phenomena in Light Water Reactors (LWRs) …

Investigation of bubble interaction in a temporal and spatial heat flux partitioning model for subcooled flow boiling

S Yang, B Ren, L Yang, C Chen, Q Lu, Z Wei… - International Journal of …, 2025 - Elsevier
CFD methodology for subcooled flow boiling is significantly affected by the heat flux
partitioning model, which plays a crucial role in predicting the mass source term generated …

Multiphase CFD-based critical heat flux predictions for single-element heaters at CANDU reactor conditions

RA Brewster, J Feng, K Podila, G Waddington… - … Engineering and Design, 2024 - Elsevier
This paper uses Eulerian multiphase computational fluid dynamics (MCFD) simulations to
predict the critical heat flux in a simplified CANDU test geometry for typical pressurized …

Mechanistic model of wall heat transfer for vertical subcooled boiling flow

ML Doan, J Bak, Y Ko, JJ Jeong, B Yun - International Communications in …, 2025 - Elsevier
Nucleate boiling rate is significantly affected by heat flux partitioning from the heated wall
during subcooled boiling flow. Therefore, precisely modeling wall heat flux partitioning is …