Thermal-hydraulic modelling of LOCA accident using CONTAIN 2.0 code
by Molood Abbasi; Mohammad Rahgoshay
International Journal of Nuclear Energy Science and Technology (IJNEST), Vol. 7, No. 3, 2013

Abstract: This paper has modelled one of the accidents in the Pressurised Water Reactor (PWR) reactor containment that is known as Loss of Coolant Accident (LOCA) in its worst condition that is called Large Break LOCA (LB LOCA) with the CONTAIN 2.0 code. Specific type of the LB LOCA is Double-Ended Cold Leg (DECL) break that means guillotine break in the cold leg pipe. The coolant is lost when a LOCA occurs and the fluid of primary loop leaks to the containment and increases pressure and temperature in the containment. This modelling is performed in the VVER-1000 reactor containment. The analysis includes average pressure in the containment and temperature distribution in the sample cells in a short time (during 200 seconds). The results are compared with the existing reports that used the ANGAR code. Results show that the CONTAIN 2.0 code is an adaptable tool for analysis of nuclear events such as LOCA.

Online publication date: Sat, 20-Sep-2014

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