Heat transfer in transition domain on film boiling in case of forced convection
Description
The design of reactor safety installations is based on the assumption, that nucleate boiling changes immediately to film boiling or vice versa, if hypothetical emergencies like LOCA (loss of coolant accident) or ATWS (anticipated transient without scram) occur. Between nucleate and film boiling, however, a 'transition boiling' region exists with better heat transfer conditions than in the film boiling region. The report presents experimental and theoretical studies on transition boiling. Such data are suitable to improve computer codes which simulate LOCA and ATWS emergencies and prove the effectiveness of safety installations. The experiments are carried out under steady-state thermal and hydrodynamic conditions, to promote a better understanding of the basic physical mechanisms of heat transfer in the transition region. Measurements with temperature-controlled heat transfer surfaces are required to permit stabilized evaporation in the transition region. A vertical tube of 14 mm inner diameter is used as test section, to simulate approximately the size of flow channels in BWR and PWR reactors. The experiments are carried out with refrigerant R114. Methods for scaling of the results to transition boiling heat transfer of water are presented. (orig.)
Availability note (English)
Available from Stuttgart Univ. (Germany, F.R.). Inst. fuer Technische Thermodynamik und Thermische Verfahrenstechnik.Abstract (German)
Bei der sicherheitstechnischen Auslegung von Kernreaktoren nimmt man an, dass waehrend eines Vorgangs wie LOCA (loss of coolant accident) oder ATWS (anticipated transient without scram) Blasensieden unmittelbar in Filmsieden uebergeht oder umgekehrt. Zwischen Blasen- und Filmsieden existiert jedoch ein Uebergangsgebiet (Transition Boiling) in dem der Waermeuebergang besser ist als im Filmsiedebereich. Es wird ueber experimentelle und theoretische Untersuchungen zum Waermeuebergang im Bereich des Uebergangssiedens berichtet. Derartige Daten ermoeglichen die Verbesserung von Rechenprogrammen, die Stoerfallablaeufe beschreiben und die Wirksamkeit von Schutz- und Gegenmassnahmen nachweisen. Die Versuche werden unter stationaeren thermo- und hydrodynamischen Bedingungen durchgefuehrt, um die grundlegenden physikalischen Vorgaenge des Waermeuebergangs im Uebergangsbereich besser studieren zu koennen. Messungen im Uebergangsbereich muessen mit temperaturkontrollierten Heizflaechen durchgefuehrt werden, um den Verdampfungsvorgang zu 'stabilisieren'. Als Messstrecke dient ein senkrechtes Rohr mit 14 mm Innendurchmesser. Damit werden ungefaehr die Abmessungen der Stroemungskanaele in SW- und DW-Reaktoren simuliert. Als Versuchsfluid wird das Kaeltemittel R114 verwendet. Methoden zur Umrechnung der Versuchsdaten auf die Bedingungen in Wasserstroemungen werden mitgeteilt. (orig.)Additional details
Additional titles
- Subtitle (English)
- Final report
- Original title (German)
- Waermeuebertragung im Uebergangsbereich zum Filmsieden (Transition Boiling) bei erzwungener Konvektion
- Original subtitle (German)
- Abschlussbericht.
- Augmented title (English)
- FILMDI; DAMVER
Publishing Information
- Imprint Pagination
- 527 p.
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 19078021
- Subject category
- S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature, Computer Program Description
- Descriptors DEI
- ATWS; BWR TYPE REACTORS; COMPUTER CODES; COMPUTER PROGRAM DOCUMENTATION; CRITICAL HEAT FLUX; D CODES; ECCS; ERRORS; F CODES; FILM BOILING; FLOW RATE; FORCED CONVECTION; FREONS; HEAT TRANSFER; LOSS OF COOLANT; MEASURING METHODS; PHASE TRANSFORMATIONS; PWR TYPE REACTORS; REACTOR CHANNELS; STEAM QUALITY; THERMOCOUPLES; TRANSITION BOILING; TWO-PHASE FLOW; VOIDS
- Descriptors DEC
- ACCIDENTS; BOILING; CONVECTION; DESIGN BASIS ACCIDENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; HEAT FLUX; MEASURING INSTRUMENTS; ORGANIC COMPOUNDS; ORGANIC HALOGEN COMPOUNDS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract BMFT 150370