Maximum Pressure drop values in the main components of VVER-1000 due to DEBLOCA in different locations
Dina Ali Amer Ph.D. Student, National Research Nuclear University “MEPhI”, Moscow, Russia Teacher Assistant, Alexandria University, Egypt Dina.email@example.com Nikonov S.P. NRNU “MEPhI”, Moscow, Russia SPNikonov@mephi.ru
29th Symposium of AER on VVER Reactor Physics and Reactor Safety (2019, Energoland, Mochovce NPP, Slovakia)
reactor dynamics and safety analysis
In this paper, the propagation of shock pressure waves in emergency situations on the equipment of the circuit for reactor VVER
-1000, is consider. Here we study the situation of instant rupture in the pipelines of the first circuit. The calculation considers six different locations for LOCA
) and showing the consequential drop in the pressure difference for the main components: core and reactor. This emergency situation is included in the list of different types of reports necessary for VVER
safety justification. As a model for investigation we chose the 3rd unit of Kalinin NPP
-1000, model 320). All thermohydraulic and physics data for this are taken from the international stander problem Kalinin-3. For the calculations, the code of improved evaluation ATHLET
was used, which is included in the AC2 software package, officially obtained by the national research Nuclear University of MEPhI on the basis of a license agreement with Gesellschaft fur Anlagen-und Reaktorsicherheit (GRS
) GmbH, Germany. The ATHLET
code is certified in Russia for calculations of stationary and transient regimes at reactors with water coolant.
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