Review of thermal-hydraulic issues and studies of lead-based fast reactors
Y Zhang, C Wang, Z Lan, S Wei, R Chen, W Tian… - … and Sustainable Energy …, 2020 - Elsevier
The lead-based reactor is one of the fourth-generation nuclear energy systems with
excellent development prospects. It has attracted much attention because of its unique …
excellent development prospects. It has attracted much attention because of its unique …
The multiscale thermal‐hydraulic simulation for nuclear reactors: A classification of the coupling approaches and a review of the coupled codes
K Zhang - International Journal of Energy Research, 2020 - Wiley Online Library
Simulation is becoming increasingly important in the safety analysis of nuclear reactors
nowadays. The physical phenomena in a nuclear power plant happen on three classified …
nowadays. The physical phenomena in a nuclear power plant happen on three classified …
Improved numerical algorithm and experimental validation of a system thermal-hydraulic/CFD coupling method for multi-scale transient simulations of pool-type …
A Toti, J Vierendeels, F Belloni - Annals of Nuclear Energy, 2017 - Elsevier
The paper describes the development and validation of a coupling methodology between
the best-estimate system thermal-hydraulic code RELAP5-3D and the CFD code FLUENT …
the best-estimate system thermal-hydraulic code RELAP5-3D and the CFD code FLUENT …
[HTML][HTML] Review of researches on coupled system and CFD codes
J Long, B Zhang, BW Yang, S Wang - Nuclear Engineering and Technology, 2021 - Elsevier
At present, most of the widely used system codes for nuclear safety analysis are one-
dimensional, which cannot effectively simulate the flow field of the reactor core or other …
dimensional, which cannot effectively simulate the flow field of the reactor core or other …
Coupled system thermal-hydraulic/CFD analysis of a protected loss of flow transient in the MYRRHA reactor
A Toti, J Vierendeels, F Belloni - Annals of Nuclear Energy, 2018 - Elsevier
Within the MYRRHA (Multi-purpose hYbrid Research Reactor for High-tech Applications)
project, the Belgian Nuclear Research Centre SCK• CEN is developing and designing a …
project, the Belgian Nuclear Research Centre SCK• CEN is developing and designing a …
Extension and application on a pool-type test facility of a system thermal-hydraulic/CFD coupling method for transient flow analyses
A Toti, J Vierendeels, F Belloni - Nuclear Engineering and Design, 2018 - Elsevier
The development of multi-scale modeling capabilities through the use of coupled system
thermal-hydraulic and CFD codes is addressed in this paper, which presents the extension …
thermal-hydraulic and CFD codes is addressed in this paper, which presents the extension …
Validation of ANSYS CFX for gas and liquid metal flows with conjugate heat transfer within the European project THINS
A Papukchiev, S Buchholz - Nuclear Engineering and Design, 2017 - Elsevier
Within the FP7 European project THINS (Thermal Hydraulics of Innovative Nuclear
Systems), numerical tools for the simulation of the thermal-hydraulics of next generation …
Systems), numerical tools for the simulation of the thermal-hydraulics of next generation …
The 33rd German CFD Network of Competence Meeting: 20 years of advances in the numerical 3D simulation of reactor relevant flows
A Papukchiev, B Schramm - Kerntechnik, 2023 - degruyter.com
Abstract The 33rd German CFD Network of Competence Meeting was held in March 2022 at
the Gesellschaft für Anlagen-und Reaktorsicherheit (GRS) gGmbH in Garching, Germany. In …
the Gesellschaft für Anlagen-und Reaktorsicherheit (GRS) gGmbH in Garching, Germany. In …
Validation of coupled ATHLET-OpenFOAM simulation on a large-scale single-and two-phase flow experiment
Z Yang, J Herb, A Papukchiev - Kerntechnik, 2024 - degruyter.com
Abstract System thermal-hydraulics (STH) codes are successfully used in the last decades
for design and analysis of the physical behavior of nuclear power plants (NPPs). These …
for design and analysis of the physical behavior of nuclear power plants (NPPs). These …
Experimental Validation of ANSYS CFX for Transient Flows With Heat Transfer in a Tubular Heat Exchanger
A Papukchiev - Journal of Nuclear Engineering and …, 2020 - asmedigitalcollection.asme.org
Within the European SESAME project, extensive experimental work was performed and
complemented by the development, application, and validation activities of thermal …
complemented by the development, application, and validation activities of thermal …