[863] 2010 – Del Nevo A., Adorni M., D’Auria F., Melikhov O. I., Elkin I. V., Schekoldin V. I., Zakutaev M. O., Zaitsev S. I., Benčík M., “Enlargement of the Assessment Database for Advanced Computer Codes in Relation to the VVER Technology: Benchmark on LB-LOCA Transient in PSB-VVER Facility – final results”, 8th Int. Conf. on Nuclear Option in Countries with Small and Medium Electricity Grids, Dubrovnik (Hr), pages 1-12, May 16-20, 2010
Abstract
The VVER-1000 (Water-cooled, Water-moderated Energy Reactor, 1000 Mwe type) experimental simulator PSB installed at the Elektrogorsk research center in Moscow region (Russia), was extensively adopted to enlarge the database of experiments available for code validation in the area of phenomena expected during accidents in VVER-1000. In the present paper focus is given to the large break Loss of Coolant Accident simulation. In relation to any Integral Test Facility (ITF) like PSB, analysis is needed to optimize the simulation and to achieve test conditions which are the most close to the conditions expected tin the prototype NPP: this is part of scaling analysis.