Published November 2000
| Version v1
Journal article
Experimental investigations on the four-loop test facility ROCOM
Creators
- 1. Forschungszentrum Rossendorf e.V. (FZR), Dresden (Germany)
Description
For the analysis of the core behaviour during boron dilution transients and main steam line breaks, coupled neutron kinetic/thermal hydraulic codes are necessary. These codes must contain models of the coolant mixing on its way from the inlet nozzles to the core entrance, because the reactivity insertion strongly depends on the distribution of temperature and boron concentration at the core inlet. To model the coolant mixing the ROCOM test facility was built, a fluid dynamic 1:5 scaled model of the Konvoi reactor. The experimental results at steady state flow conditions are presented in a survey form. (orig.)
Abstract (German)
Zur Analyse des Kernverhaltens waehrend sogenannter Borverduennungstransienten und Frischdampflecksszenarios sind gekoppelte thermohydraulisch-neutronenkinetische Computercodes notwendig. Diese gekoppelten Codesysteme muessen leistungsfaehige Modelle enthalten, welche die Vermischung von Temperatur- bzw. Borsaeure im Kuehlmittel vom Eintrittsstutzen ueber den Downcomer bis zum Kerneintritt moeglichst genau wiedergeben koennen, da die Leistungsentwicklung des Kerns stark von diesen Parametern am Kerneintritt abhaengt. Zur Modellierung der Vermischung wurde die Versuchsanlage ROCOM als fluidynamisches 1:5 skaliertes Modell des Konvoi-Reaktortyps aufgebaut. Die erzielten Ergebnisse zur Kuehlmittelvermischung bei konstanten Schleifendurchsaetzen werden in einer Uebersichtsdarstellung beschrieben. (orig.)Additional details
Publishing Information
- Journal Title
- Kerntechnik (1987)
- Journal Volume
- 65
- Journal Issue
- 5-6
- Journal Page Range
- p. 212-215
- ISSN
- 0932-3902
- CODEN
- KERNEU
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 32009971
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BORON; CONCENTRATION RATIO; COOLANT LOOPS; DESIGN BASIS ACCIDENTS; DILUTION; HYDRODYNAMIC MODEL; MIXING; NEUTRON TRANSPORT THEORY; PWR TYPE REACTORS; REACTIVITY INSERTIONS; STEAM LINES; TEMPERATURE DISTRIBUTION; TEST FACILITIES
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; ELEMENTS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; MATHEMATICAL MODELS; PARTICLE MODELS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SEMIMETALS; STATISTICAL MODELS; THERMAL REACTORS; THERMODYNAMIC MODEL; TRANSPORT THEORY; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 7 refs.