Communication Dans Un Congrès Année : 2023

COAL experiments investigating the reflooding of a 7 X 7 rod bundle during a Loss Of coolant Accident: Effect of a partially blocked area with ballooned rods

Résumé

During a loss of the coolant of the primary circuit (LOCA) in a pressurized water reactor, the drying of the fuel assemblies may lead to the fuel temperature increase and deformation of the fuel rod claddings. In addition to the restriction of the flow area, the fragmented irradiated fuel relocation within the ballooned zone leads to an increase of the local residual power. The COAL experiments will focus on the coolability issue of a partially deformed fuel assembly during water injection with the safety systems using a 7x7 bundle of electrically heated rods. These experiments are part of the PERFROI project launched by IRSN with the support of the french "Agence Nationale pour la Recherche" (ANR), EDF and the US-NRC. The effect of the flow blockage {intact geometry up to long ballooning (100 to 300 mm) with different blockage ratios (80 to 90%)} will be evaluated for various power, mass flow rates and different pressures representative to Large (LBLOCA at 0.3 MPa) and Medium break size (MBLOCA : 0.5 to 3 MPa) configuration. Relocation of fragmented fuel in the balloons are taken into account by a local increase of the power by a factor of 1.5. This paper presents the thermal hydraulics parameters and the main results of the experiments performed in a facility of the STERN Laboratories (Canada). The presence of the balloons increases significantly the Peak Cladding Temperature. These results will be used to improve and validate the heat exchange models of thermal hydraulics codes dealing with the complex reflooding processes in such configuration.
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Dates et versions

irsn-04200520 , version 1 (08-09-2023)

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  • HAL Id : irsn-04200520 , version 1

Citer

Georges Repetto, Quentin Grando, Stephane Eymery, Fortman R, Richard van Lochem, et al.. COAL experiments investigating the reflooding of a 7 X 7 rod bundle during a Loss Of coolant Accident: Effect of a partially blocked area with ballooned rods. 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20), American Nuclear Society, Aug 2023, Washington, United States. ⟨irsn-04200520⟩

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