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No: 218
Conference: Nuclear Energy for New Europe 2009
Title: Simulation of primary to secondary leak transient in VVER-1000
Theme: Thermal Hydraulics
Author(s): Eugenio Coscarelli, Alessandro Del Nevo, Francesco D'Auria
Contact : Eugenio Coscarelli
E-mail: e.coscarelli@ing.unipi.it
Address: University of Pisa, San Piero a Grado Nuclear Research Group (GRNSPG)
56122 Pisa
Country: Italy
 
The present paper deals with the assessment of CATHARE2 code against a primary to secondary leak transient conducted in the scaled facility PSB-VVER. It is an Integral Test Facility (ITF), full height, full pressure, low power and scaled 1:300, installed at the Electrogorsk Research and Engineering Centre, Russia. The experiment is the fourth out of five experiments part of the OECD/NEA PSB-VVER Project validation matrix. The objectives of the test are the investigation of the thermal-hydraulic (TH) response of the VVER-1000 primary system following a primary to secondary side accident and the availability of experimental data aimed at the validation of thermal-hydraulic codes. Indeed, the test was designed and executed to obtain the experimental data addressing a scenario and phenomena not covered by the OECD/NEA VVER validation matrix. The experiment is a “Primary to Secondary Side Leak” with a BRU-A failure (the valve remained open in fully position) in the SG connected with the broken loop. The calculations have been performed using CATHARE2V2.5_1, its accuracy has been evaluated by qualitative and quantitative analysis reported in the present document. The quantitative analysis has been performed adopting a method developed at University of Pisa, which has capabilities in quantifying the errors in code predictions related to the measured experimental signal; the Fast Fourier Transform (FFT) is used aiming to have an integral representation of the code calculation discrepancies (i.e. error between measured and calculated time trends) in the frequency domain.