Experimentation, modelling and simulation of water droplets impact on ballooned sheath of PWR core fuel assemblies in a LOCA situation
Creators
- Lelong, Franck
- Universite Henri Poincare - Nancy 1, 24-30 rue Lionnois - BP 60120, 54003 Nancy Cedex (France)
- Laboratoire d'energetique et de Mecanique Theorique et Appliquee - LEMTA, 2 Avenue de la Foret de Haye, BP160, 54504 Vandoeuvre les Nancy (France)
- Institut de Radioprotection et de Surete Nucleaire - IRSN, BP 3- 13115 Saint-Paul-Lez-Durance Cedex (France)
Description
In a pressurized water reactor (PWR), during a Loss Of Coolant Accident (LOCA), liquid water evaporates and the fuel assemblies are not cooled anymore; as a consequence, the temperature rises to such an extent that some parts of the fuel assemblies can be deformed resulting in 'ballooned regions'. When reflooding occurs, the cooling of these partially blocked parts of the fuel assemblies will depend on the coolant flow that is a mixture of overheated vapour and under-saturated droplets. The aim of this thesis is to study the heat transfer between droplets and hot walls of the fuel rods. In this purpose, an experimental device has been designed in accordance with droplets and wall features (droplet velocity and diameter, wall temperature) representative of LOCA conditions. The cooling of a hot Nickel disk, previously heated by induction, is cooled down by a stream of monodispersed droplet. The rear face temperature profiles are measured by infrared thermography. Then, the estimation of wall heat flux is performed by an inverse conduction technique from these infrared images. The effect of droplet dynamical properties (diameter, velocity) on the heat flux is studied. These experimental data allow us to validate an analytical model of heat exchange between droplet and hot slab. This model is based on combined dynamical and thermal considerations. On the one hand, the droplet dynamics is considered through a spring analogy in order to evaluate the evolution of droplet features such as the spreading diameter when the droplet is squeezed over the hot surface. On the other hand, thermal parameters, such as the thickness of the vapour cushion beneath the droplet, are determined from an energy balance. In the short term, this model will be integrated in a CFD code (named NEPTUNE-CFD) to simulate the cooling of a reactor core during a LOCA, taking into account the droplet/wall heat exchange. (author)
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43127273.pdf
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Additional details
Additional titles
- Original title (French)
- Experimentation, modelisation et simulation de l'impact de gouttes d'eau sur le gainage gonfle des assemblages d'un coeur de REP en situation d'APRP
Identifiers
Publishing Information
- Imprint Pagination
- 186 p.
- Report number
- FRNC-TH--8179
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 43127273
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S97: MATHEMATICAL METHODS AND COMPUTING;
- Resource subtype / Literary indicator
- Thesis
- Descriptors DEI
- COMPUTERIZED SIMULATION; DROPLETS; FUEL ASSEMBLIES; FUEL RODS; HEAT FLUX; HEAT TRANSFER; LOSS OF COOLANT; MATHEMATICAL MODELS; N CODES; PWR TYPE REACTORS; REACTOR ACCIDENT SIMULATION; REACTOR COOLING SYSTEMS; TEMPERATURE DISTRIBUTION; THERMAL HYDRAULICS; WALL EFFECTS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; ENERGY SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID MECHANICS; FUEL ELEMENTS; HYDRAULICS; MECHANICS; PARTICLES; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 50 refs.; Available from the INIS Liaison Officer for France, see the 'INIS contacts' section of the INIS website for current contact and E-mail addresses: http://www.iaea.org/inis/contacts/