Sushmita Barua - Academia.edu (original) (raw)

Uploads

Papers by Sushmita Barua

Research paper thumbnail of A COMPARISON OF SIMULATION ANALYSIS OF SAFETY SYSTEMS AND SEVERE ACCIDENT PROGRESSION FOR VVER-1200 AND AP-1000 FOLLOWING LOCA IN HOTLEG BY PCTRAN

Proceedings of the International Conference on Mechanical Engineering and Renewable Energy 2021 (ICMERE 2021) 12 – 14 December 2021, Chattogram, Bangladesh., 2021

For generating electricity in nuclear power plants (NPP), the nuclear reactor plays a vital role.... more For generating electricity in nuclear power plants (NPP), the nuclear reactor plays a vital role. VVER-1200 and AP-1000 reactors are generation III+ reactors which are considered for this research work. This paper presents the change of various thermal hydraulics parameters VVER-1200 and AP-1000 on transient state of Loss of Coolant Accident (LOCA) in hot leg. The simulation is carried out by Personal Computer Transient Analyzer (PCTRAN) to analyze the transient state for 300 seconds. A break of 0.1m 2 size in the hot leg of the primary coolant circuit has been considered in this research work for both the reactors. It is observed that reactor thermal power falls below 5% of steady state power within 5s followed by SCRAM, containment pressure rises 1.5 to 2.5 bar, void increases till 40% after 300 seconds, RCS pressure is noticed consecutively a bit lower than 20 bar after 100 seconds for both types of reactors and no major damage is noticed. Achieved results can be effective to evaluate nominal value of different parameters of several safety components of VVER-1200 and AP-1000 and mitigate the risk of severe accidents.

Research paper thumbnail of A COMPARISON OF SIMULATION ANALYSIS OF SAFETY SYSTEMS AND SEVERE ACCIDENT PROGRESSION FOR VVER-1200 AND AP-1000 FOLLOWING LOCA IN HOTLEG BY PCTRAN

Proceedings of the International Conference on Mechanical Engineering and Renewable Energy 2021 (ICMERE 2021) 12 – 14 December 2021, Chattogram, Bangladesh., 2021

For generating electricity in nuclear power plants (NPP), the nuclear reactor plays a vital role.... more For generating electricity in nuclear power plants (NPP), the nuclear reactor plays a vital role. VVER-1200 and AP-1000 reactors are generation III+ reactors which are considered for this research work. This paper presents the change of various thermal hydraulics parameters VVER-1200 and AP-1000 on transient state of Loss of Coolant Accident (LOCA) in hot leg. The simulation is carried out by Personal Computer Transient Analyzer (PCTRAN) to analyze the transient state for 300 seconds. A break of 0.1m 2 size in the hot leg of the primary coolant circuit has been considered in this research work for both the reactors. It is observed that reactor thermal power falls below 5% of steady state power within 5s followed by SCRAM, containment pressure rises 1.5 to 2.5 bar, void increases till 40% after 300 seconds, RCS pressure is noticed consecutively a bit lower than 20 bar after 100 seconds for both types of reactors and no major damage is noticed. Achieved results can be effective to evaluate nominal value of different parameters of several safety components of VVER-1200 and AP-1000 and mitigate the risk of severe accidents.

Log In