Inderscience Publishers

Inderscience Publishers

Thermal–hydraulic modelling of LOCA accident using CONTAIN 2.0 code


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.

Keywords: CONTAIN 20 code, LB LOCA, DECL, double–ended cold leg, containment, VVER–1000 reactors, nuclear reactors, nuclear energy, nuclear power, modelling, nuclear accidents, pressurised water reactors, PWR, loss of coolant, temperature distribution, nuclear safety

Customer comments

No comments were found for Thermal–hydraulic modelling of LOCA accident using CONTAIN 2.0 code. Be the first to comment!