Containment pressure analysis methodology duringa lbloca with cocosys code
International Journal of Development Research
Containment pressure analysis methodology duringa lbloca with cocosys code
Received 10th August, 2018; Received in revised form 15th September, 2018; Accepted 24th October, 2018; Published online 30th November, 2018.
Copyright © 2018, Dayane Faria Silva et al. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
During a nuclear power plant basic design accident, the containment integrity is a determining factor for the accident severity. The pressure and temperature conditions inside the containment in case of a Large Break Loss of Coolant Accident (LBLOCA) must be verified. This paper presents a containment pressure and temperature analysis methodology of a Brazilian PWR, Angra 2, using a code that simulates guillotine rupture - RELAP5 - and the COCOSYS code, which analyzes the containment pressure from the accident conditions. The Angra 2 containment behavior results during the design basis accidents studied - primary cooling system cold and hot legs guillotine ruptures - were satisfactory when compared to those presented in the Final Safety Analysis Report (FSAR / A2) and the pressure distributions were below the containment design pressure value (6.3bar).
