Investigation of accident management procedures related to loss of feedwater and station blackout in PSB-VVER integral test facility

• Published in: Nuclear engineering and design Vol. 250; pp. 633 - 645
• Main Authors: Bucalossi, A., Del Nevo, A., Moretti, F., D’Auria, F., Elkin, I.V., Melikhov, O.I.
• Format: Journal Article
• Language: English
• Published: Elsevier B.V 01.09.2012
• ISSN: 0029-5493; 1872-759X
• DOI: 10.1016/j.nucengdes.2012.06.027

► Four integral test facility experiments related to VVER-1000 reactor. ► TH response of the VVER-1000 primary system following total loss of feedwater and station blackout scenarios. ► Accident management procedures in case of total loss of feedwater and station blackout. ► Experimental data represent an improvement of existing database for TH code validation. VVER 1000 reactors have some unique and specific features (e.g. large primary and secondary side fluid inventory, horizontal steam generators, core design) that require dedicated experimental and analytical analyses in order to assess the performance of safety systems and the effectiveness of possible accident management strategies. The European Commission funded project “TACIS 2.03/97”, Part A, provided valuable experimental data from the large-scale (1:300) PSB-VVER test facility, investigating accident management procedures in VVER-1000 reactor. A test matrix was developed at University of Pisa (responsible of the project) with the objective of obtaining the experimental data not covered by the OECD VVER validation matrix and with main focus on accident management procedures. Scenarios related to total loss of feed water and station blackout are investigated by means of four experiments accounting for different countermeasures, based on secondary cooling strategies and primary feed and bleed procedures. The transients are analyzed thoroughly focusing on the identification of phenomena that will challenge the code models during the simulations.