Verification of the CFD code FLUENT by post test calculation of the ROCOM experiment T665521
- 1. TUEV Nord SysTec GmbH und Co. KG, Hamburg (Germany)
Description
During the last years one focus of German PWR safety analysis was boron dilution events with the potential of reactivity transients. Coolant with a low boron concentration could be collected in localized areas of the reactor coolant system e.g. by separation of borated reactor coolant into highly concentrated and diluted fractions (inherent dilution) which can occur during reflux- condenser heat transfer after a small break loss of coolant accident with a limited availability of the emergency core cooling systems. The TUeV NORD SysTec was charged by German supervisory authorities with the assessment of the safety analyses of boron dilution events presented by the utilities. These analyses are based on the simulation of boron dilution and transport processes in conjunction with a number of dedicated experiments. The analyses shall demonstrate that boron dilution events cannot lead to recriticality of the core. Hence the boron concentration at the core inlet has to be determined. TUeV NORD SysTec applies the CFD code FLUENT for the investigation of boron dilution events in pressurized water reactors. To affirm the FLUENT abilities for the simulation of boron dilution events a validation against the ROCOM experiment T6655-21 with density driven coolant mixing was performed. This validation proves that FLUENT is able to simulate appropriately the effects of boron transport and dilution such as streaks of coolant with lower density in the downcomer. Deficits were identified in the simulation of fluid layering in the primary coolant pipe, which have fortunately a rather small influence on the predicted core inlet concentration. Therefore, the boron concentration in the reactor core can be determined with sufficient accuracy to solve the safety issue whether the core gets critical or not. (orig.)
Additional details
Additional titles
- Original title (German)
- Validierung des CFD codes FLUENT anhand der Nachrechnung des ROCOM Experimentes T665521
Publishing Information
- Journal Title
- Atw. Internationale Zeitschrift fuer Kernenergie
- Journal Volume
- 50
- Journal Issue
- 5
- Journal Page Range
- p. 323-331
- ISSN
- 1431-5254
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 36061306
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BORON; COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; DATA PROCESSING; F CODES; FINITE ELEMENT METHOD; FROUDE NUMBER; MESH GENERATION; MIXING; PRESSURE VESSELS; PWR TYPE REACTORS; REACTOR CORES; REYNOLDS NUMBER; TRACER TECHNIQUES; VALIDATION
- Descriptors DEC
- CALCULATION METHODS; COMPUTER CODES; CONTAINERS; DIMENSIONLESS NUMBERS; ELEMENTS; ENRICHED URANIUM REACTORS; EVALUATION; ISOTOPE APPLICATIONS; MATHEMATICAL SOLUTIONS; NUMERICAL SOLUTION; POWER REACTORS; PROCESSING; REACTOR COMPONENTS; REACTORS; SEMIMETALS; SIMULATION; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS