Experiments at the mixing test facility ROCOM for benchmarking of CFD codes
- 1. Forschungszentrum Dresden-Rossendorf e.V., Institute of Safety Research, P.O. Box 510119, D-01314 Dresden (Germany)
- 2. Eidgenoessische Technische Hochschule Zuerich, Department of Mechanical and Process Engineering, ETH-Zentrum, CH-8092 Zurich (Switzerland)
Description
For the validation of computational fluid dynamics (CFD) codes, experimental data on fluid flow parameters with high resolution in time and space are needed. Rossendorf Coolant Mixing Model (ROCOM) is a test facility for the investigation of coolant mixing in the primary circuit of pressurized water reactors. This facility reproduces the primary circuit of a German KONVOI-type reactor. All important details of the reactor pressure vessel are modelled at a linear scale of 1:5. The facility is characterized by flexible possibilities of operation in a wide variety of flow regimes and boundary conditions. The flow path of the coolant from the cold legs through the downcomer until the inlet into the core is equipped with high-resolution detectors, in particular, wire mesh sensors in the downcomer of the vessel with a mesh of 64 x 32 measurement positions and in the core inlet plane with one measurement position for the entry into each fuel assembly, to enable high-level CFD code validation. Two different types of experiments at the ROCOM test facility have been proposed for this purpose. The first proposal concerns the transport of a slug of hot, under-borated condensate, which has formed in the cold leg after a small break LOCA, towards the reactor core under natural circulation. The propagation of the emergency core cooling water in the test facility under natural circulation or even stagnant flow conditions should be investigated in the second type of experiment. The measured data can contribute significantly to the validation of CFD codes for complex mixing processes with high relevance for nuclear safety
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2007.02.053Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2007.02.053;
- PII
- S0029-5493(07)00350-0;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 238
- Journal Issue
- 3
- Journal Page Range
- p. 566-576
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 39049086
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- C CODES; COMPUTERIZED SIMULATION; COOLANTS; ECCS; FLUID FLOW; FLUID MECHANICS; FUEL ASSEMBLIES; LOSS OF COOLANT; NATURAL CONVECTION; PRESSURE VESSELS; PWR TYPE REACTORS; RADIATION PROTECTION; REACTOR CORES; RESOLUTION; TEST FACILITIES; VALIDATION
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; CONTAINERS; CONVECTION; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; HEAT TRANSFER; MASS TRANSFER; MECHANICS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SIMULATION; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2007 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.