Numerical study on the effects of guide thimble on critical heat flux in a 5 × 5 fuel assembly

Progress in rod bundle CHF in the past 40 years

(2021) Bao-Wen Yang et al.   NUCLEAR ENGINEERING AND DESIGN

LES and URANS study on turbulent flow through 3 × 3 rod bundle with spacer grid and mixing vanes using spectral element method

(2021) Haoran Ju et al.   ANNALS OF NUCLEAR ENERGY

Large eddy simulation on the turbulent mixing phenomena in 3×3 bare tight lattice rod bundle using spectral element method

(2020) Haoran Ju et al.   Nuclear Engineering and Technology

Two-phase bubbly flow simulation using CFD method: A review of models for interfacial forces

(2020) Irfan Khan et al.   PROGRESS IN NUCLEAR ENERGY

Investigation on the critical heat flux in typical 5 by 5 rod bundle at conditions prototypical of PWR based on CFD methodology

(2020) Rui Zhang et al.   APPLIED THERMAL ENGINEERING

Recent progress of CFD applications in PWR thermal hydraulics study and future directions

(2020) Mingjun Wang et al.   ANNALS OF NUCLEAR ENERGY

A Simple Model to Identify Dryout Location: Validation and Computational Fluid Dynamics Predictions

(2020) Harish Pothukuchi et al.   HEAT TRANSFER ENGINEERING

CFD modeling of critical heat flux in flow boiling: Validation and assessment of closure models

(2019) Harish Pothukuchi et al.   APPLIED THERMAL ENGINEERING

Studies on the subcooled boiling in a fuel assembly with 5 by 5 rods using an improved wall boiling model

(2018) Tenglong Cong et al.   ANNALS OF NUCLEAR ENERGY

Direct numerical simulation of reactor two-phase flows enabled by high-performance computing

(2018) Jun Fang et al.   NUCLEAR ENGINEERING AND DESIGN

CFD prediction of critical heat flux in vertical heated tubes with uniform and non-uniform heat flux

(2018) Quan Li et al.   NUCLEAR ENGINEERING AND DESIGN

Effects of interaction models on upward subcooled boiling flow in annulus

(2018) Xiang Zhang et al.   PROGRESS IN NUCLEAR ENERGY

Numerical investigation on mixing performance in rod bundle with spacer grid based on anisotropic turbulent mixing model

(2018) Xiang Li et al.   INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER

Numerical prediction of CHF based on CFD methodology under atmospheric pressure and low flow rate

(2018) Yapei Zhang et al.   APPLIED THERMAL ENGINEERING

Investigation on the critical heat flux in a 2 by 2 fuel assembly under low flow rate and high pressure with a CFD methodology

(2018) Rui Zhang et al.   ANNALS OF NUCLEAR ENERGY

Numerical investigation of the boiling crisis for helical cruciform-shaped rods at high pressures

(2016) Koroush Shirvan   INTERNATIONAL JOURNAL OF MULTIPHASE FLOW

Computational multi-fluid dynamics predictions of critical heat flux in boiling flow

(2016) S. Mimouni et al.   NUCLEAR ENGINEERING AND DESIGN

Prediction of CHF in vertical heated tubes based on CFD methodology

(2015) Rui Zhang et al.   PROGRESS IN NUCLEAR ENERGY

CFD analysis on subcooled boiling phenomena in PWR coolant channel

(2015) Rui Zhang et al.   PROGRESS IN NUCLEAR ENERGY

Applications of ANNs in flow and heat transfer problems in nuclear engineering: A review work

(2012) Tenglong Cong et al.   PROGRESS IN NUCLEAR ENERGY

CHF experiment and CFD analysis in a 2×3 rod bundle with mixing vane

(2009) Byung Soo Shin et al.   NUCLEAR ENGINEERING AND DESIGN