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CFD Simulation of Thermal-Hydraulic Benchmark V1000CT-2 Using ANSYS CFX
Author
Source
Science and Technology of Nuclear Installations
Issue
Vol. 2009, Issue 2009 (31 Dec. 2009), pp.1-7, 7 p.
Publisher
Hindawi Publishing Corporation
Publication Date
2009-03-30
Country of Publication
Egypt
No. of Pages
7
Main Subjects
Engineering Sciences and Information Technology
Abstract EN
Plant measured data from VVER-1000 coolant mixing experiments were used within the OECD/NEA and AER coupled code benchmarks for light water reactors to test and validate computational fluid dynamic (CFD) codes.
The task is to compare the various calculations with measured data, using specified boundary conditions and core power distributions.
The experiments, which are provided for CFD validation, include single loop cooling down or heating-up by disturbing the heat transfer in the steam generator through the steam valves at low reactor power and with all main coolant pumps in operation.
CFD calculations have been performed using a numerical grid model of 4.7 million tetrahedral elements.
The Best Practice Guidelines in using CFD in nuclear reactor safety applications has been used.
Different advanced turbulence models were utilized in the numerical simulation.
The results show a clear sector formation of the affected loop at the downcomer, lower plenum and core inlet, which corresponds to the measured values.
The maximum local values of the relative temperature rise in the calculation are in the same range of the experiment.
Due to this result, it is now possible to improve the mixing models which are usually used in system codes.
American Psychological Association (APA)
Hoehne, Thomas. 2009. CFD Simulation of Thermal-Hydraulic Benchmark V1000CT-2 Using ANSYS CFX. Science and Technology of Nuclear Installations،Vol. 2009, no. 2009, pp.1-7.
https://search.emarefa.net/detail/BIM-501898
Modern Language Association (MLA)
Hoehne, Thomas. CFD Simulation of Thermal-Hydraulic Benchmark V1000CT-2 Using ANSYS CFX. Science and Technology of Nuclear Installations No. 2009 (2009), pp.1-7.
https://search.emarefa.net/detail/BIM-501898
American Medical Association (AMA)
Hoehne, Thomas. CFD Simulation of Thermal-Hydraulic Benchmark V1000CT-2 Using ANSYS CFX. Science and Technology of Nuclear Installations. 2009. Vol. 2009, no. 2009, pp.1-7.
https://search.emarefa.net/detail/BIM-501898
Data Type
Journal Articles
Language
English
Notes
Includes bibliographical references
Record ID
BIM-501898