Integral and separate effects test facilities to support water cooled small modular reactors: A review

PK Bhowmik, CEE Perez, JD Fishler, SAB Prieto… - Progress in Nuclear …, 2023 - Elsevier
This study reviews previous experimental facilities and test programs relevant to water-
cooled reactor system design and analysis to meet regulatory compliances. This study aims …

Development of ANN structural optimization framework for data-driven prediction of local two-phase flow parameters

ND Nguyen - Progress in Nuclear Energy, 2022 - Elsevier
In this paper, a workflow of ANN-based model development for data-driven prediction of the
local two-phase flow parameters has been proposed. To effectively construct an ANN-based …

Preliminary study of coupling CFD code FLUENT and system code RELAP5

W Li, X Wu, D Zhang, G Su, W Tian, S Qiu - Annals of Nuclear Energy, 2014 - Elsevier
The present paper discusses a coupling strategy of the 3D (three-dimensional)
computational fluid dynamics (CFD) code ANSYS-FLUENT with the best estimate 1D (one …

Three dimensional thermal hydraulic characteristic analysis of reactor core based on porous media method

R Chen, M Tian, S Chen, W Tian, GH Su, S Qiu - Annals of Nuclear Energy, 2017 - Elsevier
Thermal-hydraulic performance in the reactor core was an essential factor in the nuclear
power plant design. In this study, we analyzed the three-dimensional (3-D) thermal-hydraulic …

Assessment of CFD codes used in nuclear reactor safety simulations

BL Smith - Nuclear Engineering and Technology, 2010 - koreascience.kr
Following a joint OECD/NEA-IAEA-sponsored meeting to define the current role and future
perspectives of the application of Computational Fluid Dynamics (CFD) to nuclear reactor …

Comparison of Reduced-Basis techniques for the model order reduction of parametric incompressible fluid flows

P German, M Tano, JC Ragusa, C Fiorina - Progress in Nuclear Energy, 2020 - Elsevier
The applicability of two Reduced-Basis techniques to parametric laminar and turbulent
incompressible fluid-flow problems in nuclear engineering is studied in this work. The …

A hybrid domain overlapping method for coupling System Thermal Hydraulics and CFD codes

A Huxford, VC Leite, E Merzari, L Zou, V Petrov… - Annals of Nuclear …, 2023 - Elsevier
A hybrid multiscale coupling methodology based on a domain overlapping approach has
been developed for coupling System Thermal Hydraulics (STH) and Computational Fluid …

System thermalhydraulics for design basis accident analysis and simulation: Status of tools and methods and direction for future R&D

D Bestion - Nuclear Engineering and Design, 2017 - Elsevier
Abstract System thermalhydraulic investigations of Design Basis Accident require several
tools and methods including the Process Identification and Ranking Table, the scaling …

Extension of CFD codes application to two-phase flow safety problems

D Bestion - Nuclear Engineering and Technology, 2010 - koreascience.kr
This paper summarizes the results of a Writing Group on the Extension of CFD codes to two-
phase flow safety problems, which was created by the Group for Analysis and Management …

From the direct numerical simulation to system codes-perspective for the multi-scale analysis of LWR thermalhydraulics

D Bestion - Nuclear Engineering and Technology, 2010 - koreascience.kr
A multi-scale analysis of water-cooled reactor thermalhydraulics can be used to take
advantage of increased computer power and improved simulation tools, including Direct …