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Benchmarking of Computational Fluid Dynamics Codes for Reactor Vessel Design

Results of a Coordinated Research Project


English IAEA-TECDOC-1908 ¦ 978-92-0-107420-1

72 pages ¦ 74 figures ¦ € 18.00 ¦ Date published: 2020

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This publication provides a description of the Rossendorf coolant mixing (ROCOM) test facility, used to provide benchmark experiments related to the phenomena of pressurized thermal shock (PTS) and boron dilution, the calculation results using computational fluid dynamics (CFD) codes and methods, and the conclusions drawn from comparison of CFD results with experimental measurements. The aim of this benchmarking was to provide CFD practitioners with two high quality datasets of relevance to reactor transients inside a pressurized water reactor pressure vessel with different configurations and involving mixed convection, stratification, jet impingement and unsteady (inverse) plumes. The focus of the benchmarking was on the three main regions of the cold domain of the primary circuit, i.e. the cold leg, the downcomer and the core entry region. The work was carried out within the framework of an IAEA coordinated research project on application of computational fluid dynamics codes to nuclear power plant design.

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CRP, Coordinated Research Project, OFEL, Omni Flow Experimental Loop, Rod-Bundle Experiment, Flow-Mixing Experiment, Heat-Transfer Experiment, Statistics, Kaeri Bundle Benchmarks, CFD, Computational Fluid Dynamics, CHF, Critical Heat Flux, DES, Detached Eddy Simulation, NPP, Nuclear Power Plant, WCR, Water Cooled Reactor, PWR, Pressurized Water Reactor, Bundle Benchmark, Benchmark, Kaeri, Experiment, Safety, Reactor

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