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

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

Numerical investigation on performance of moisture separator: Experimental validation, applications and new findings

(2020) Huang Zhang et al.   ANNALS OF NUCLEAR ENERGY

Numerical simulation of temperature heterogeneity inside the AP1000 upper plenum and hot leg

(2020) Lianfa Wang et al.   NUCLEAR ENGINEERING AND DESIGN

CFD simulation on the flow characteristics in the PWR lower plenum with different internal structures

(2020) Mingjun Wang et al.   NUCLEAR ENGINEERING AND DESIGN

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

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

3D fluid-solid coupling simulation for plate-type nuclear fuel assemblies under the irradiation condition

(2020) Haoyu Liao et al.   PROGRESS IN NUCLEAR ENERGY

The development of high fidelity Steam Generator three dimensional thermal hydraulic coupling code: STAF-CT

(2020) Xiaohan Zhao et al.   Nuclear Engineering and Technology

Thermal Hydraulic and Neutronics Coupling Analysis for Plate Type Fuel in Nuclear Reactor Core

(2020) Linrong Ye et al.   Science and Technology of Nuclear Installations

A baseline closure concept for simulating bubbly flow with phase change: A mechanistic model for interphase heat transfer coefficient

(2019) Yixiang Liao et al.   NUCLEAR ENGINEERING AND DESIGN

Numerical study on the turbulent mixing in channel with Large Eddy Simulation (LES) using spectral element method

(2019) Haoran Ju et al.   NUCLEAR ENGINEERING AND DESIGN

Numerical research on thermal mixing characteristics in a 45-degree T-junction for two-phase stratified flow during the emergency core cooling safety injection

(2019) Tangtao Feng et al.   PROGRESS IN NUCLEAR ENERGY

Numerical study on the thermal stratification characteristics of AP1000 pressurizer surge line

(2019) Mingjun Wang et al.   ANNALS OF NUCLEAR ENERGY

Passive decay heat removal system design for the integral inherent safety light water reactor (I2S-LWR)

(2019) Mingjun Wang et al.   ANNALS OF NUCLEAR ENERGY

Numerical study on the single bubble rising behaviors under rolling conditions

(2019) Chong Chen et al.   NUCLEAR ENGINEERING AND DESIGN

Local effect model development for the steam generator three dimensional thermal hydraulics analysis code

(2019) Xi Wang et al.   ANNALS OF NUCLEAR ENERGY

Full-scale numerical study on the flow characteristics and mal-distribution phenomena in SG steam-water separation system of an advanced PWR

(2019) Di Fang et al.   PROGRESS IN NUCLEAR ENERGY

Full-scale numerical study on the thermal-hydraulic characteristics of steam-water separation system in an advanced PWR UTSG. Part two: Droplets separation process

(2019) Di Fang et al.   PROGRESS IN NUCLEAR ENERGY

Droplet phase change model and its application in wave-type vanes of steam generator

(2018) Fulong Zhao et al.   ANNALS OF NUCLEAR ENERGY

Prediction of blowdown of a pressure relief valve using response surface methodology and CFD techniques

(2018) Jian Zhang et al.   APPLIED THERMAL ENGINEERING

Numerical modeling of an in-vessel flow limiter using an immersed boundary approach

(2018) Michel Belliard   NUCLEAR ENGINEERING AND DESIGN

CFD investigation on thermal hydraulics of the passive residual heat removal heat exchanger (PRHR HX)

(2018) Jian Ge et al.   NUCLEAR ENGINEERING AND DESIGN

Numerical Study of Integral Inherently Safe Light Water Reactor in Case of Inadvertent DHR Operation Based on the Multiscale Method

(2018) Mingjun Wang et al.   NUCLEAR TECHNOLOGY

Study on the coolant mixing phenomenon in a 45° T junction based on the thermal-mechanical coupling method

(2018) Mingjun Wang et al.   APPLIED THERMAL ENGINEERING

A Multiscale Approach Simulating Boiling in a Heated Pipe Including Flow Pattern Transition

(2018) T. Höhne et al.   NUCLEAR TECHNOLOGY

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

(2018) Yapei Zhang et al.   APPLIED THERMAL ENGINEERING

Three-dimensional study on the hydraulic characteristics under the steam generator (SG) tube plugging operations for AP1000

(2018) Xiaohan Zhao et al.   PROGRESS IN NUCLEAR ENERGY

A self-consistent, physics-based boiling heat transfer modeling framework for use in computational fluid dynamics

(2017) Lindsey Gilman et al.   INTERNATIONAL JOURNAL OF MULTIPHASE FLOW

Large-scale large eddy simulation of nuclear reactor flows: Issues and perspectives

(2017) Elia Merzari et al.   NUCLEAR ENGINEERING AND DESIGN

CFD investigation and assessment of wall heat flux partitioning model for the prediction of high pressure subcooled flow boiling

(2016) Janani Srree Murallidharan et al.   INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER

Steady-state CFD simulations of an EPR™ reactor pressure vessel: A validation study based on the JULIETTE experiments

(2016) R. Puragliesi et al.   NUCLEAR ENGINEERING AND DESIGN

Perspectives on CFD analysis in nuclear reactor regulation

(2016) Christopher Boyd   NUCLEAR ENGINEERING AND DESIGN

Development and preliminary validation of a steam generator 3D thermohydraulics analysis code STAF

(2016) Tenglong Cong et al.   NUCLEAR ENGINEERING AND DESIGN

Development of CFD methodology for investigating thermal-hydraulic characteristics in a PWR dome

(2015) W.C. Cheng et al.   NUCLEAR ENGINEERING AND DESIGN

Steady and transient solutions of neutronics problems based on finite volume method (FVM) with a CFD code

(2015) Jian Ge et al.   PROGRESS IN NUCLEAR ENERGY

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

Preliminary study of coupling CFD code FLUENT and system code RELAP5

(2014) Wei Li et al.   ANNALS OF NUCLEAR ENERGY

Modeling subcooled flow boiling in vertical channels at low pressures – Part 1: Assessment of empirical correlations

(2014) S.C.P. Cheung et al.   INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER

CMFD and the critical-heat-flux grand challenge in nuclear thermal–hydraulics – A letter to the Editor of this special issue

(2014) G. Yadigaroglu   INTERNATIONAL JOURNAL OF MULTIPHASE FLOW

Special Issue of the 4th Workshop on the CFD for Nuclear Reactor Safety (CFD4NRS-4)

(2014) Chul-Hwa Song et al.   NUCLEAR ENGINEERING AND DESIGN

Development of CUPID-SG for the analysis of two-phase flows in PWR steam generators

(2014) Hyungrae Kim et al.   PROGRESS IN NUCLEAR ENERGY

Effects of the slots on the performance of swirl-vane separator

(2013) Zhenqin Xiong et al.   NUCLEAR ENGINEERING AND DESIGN

CFD analysis with fluid–structure interaction of opening high-pressure safety valves

(2012) A. Beune et al.   COMPUTERS & FLUIDS

CFD analysis for full vessel upper plenum in Maanshan Nuclear Power Plant

(2012) C.Y. Wu et al.   NUCLEAR ENGINEERING AND DESIGN

Characteristics of critical heat flux under rolling condition for flow boiling in vertical tube

(2012) Jin-Seok Hwang et al.   NUCLEAR ENGINEERING AND DESIGN

Numerical research of turbulent heat transfer in rectangular channels in ocean environment

(2011) B. H. Yan et al.   HEAT AND MASS TRANSFER

CFD analysis of PWR core top and reactor vessel upper plenum internal subdomain models

(2011) Min-Tsung Kao et al.   NUCLEAR ENGINEERING AND DESIGN

Large Eddy Simulation and the effect of the turbulent inlet conditions in the mixing Tee

(2011) Jean-Marc Ndombo et al.   NUCLEAR ENGINEERING AND DESIGN

Numerical simulation of bubble behaviors in subcooled flow boiling under swing motion

(2011) Jing-hua Wei et al.   NUCLEAR ENGINEERING AND DESIGN

Experimental and theoretical study on single-phase natural circulation flow and heat transfer under rolling motion condition

(2009) Si-chao Tan et al.   APPLIED THERMAL ENGINEERING

Simulation of turbulent and thermal mixing in T-junctions using URANS and scale-resolving turbulence models in ANSYS CFX

(2009) Th. Frank et al.   NUCLEAR ENGINEERING AND DESIGN

The inhomogeneous MUSIG model for the simulation of polydispersed flows

(2008) Eckhard Krepper et al.   NUCLEAR ENGINEERING AND DESIGN

Overview of accident analysis in nuclear research reactors

(2008) Tewfik Hamidouche et al.   PROGRESS IN NUCLEAR ENERGY

Analysis of the hot gas flow in the outlet plenum of the very high temperature reactor using coupled RELAP5-3D system code and a CFD code

(2007) Nolan Anderson et al.   NUCLEAR ENGINEERING AND DESIGN

Flow and pressure drop fluctuations in a vertical tube subject to low frequency oscillations

(2007) Rajashekhar Pendyala et al.   NUCLEAR ENGINEERING AND DESIGN