Abstract

Objectives: To study the transient response of a VVER-1200 based nuclear power plant parameters and safety systems during a Large-break Loss of Coolant Accident (LBLOCA) for two distinct cases; one in which SCRAM is initiated and the other one in which SCRAM is not initiated due to malfunction of the system. Method: Personal Computer Transient Analyzer (PCTRAN) has been used to obtain transient response of the plant for 300 seconds during these accidents. A break of 0.1 m2 size in the hot leg of the primary coolant circuit has been considered in this work. It has also been assumed that off-site AC power supply is completely cut-off for both cases. Findings: Results show that for Loss of Coolant Accident followed by SCRAM, core thermal power drops to only 5% of the normal operating power within 5seconds. The peak fuel and cladding temperature is recorded to be slightly higher than 1800o C and 610o C respectively, showing no failure for any of the two. Maximum pressures inside reactor core structure and reactor containment building are recorded to be 162 bar and 3.5 bar respectively, which are within design limits. However, for Loss of Coolant Accident with no SCRAM, core thermal power is recorded to be around 80% of the normal operating value after 300 seconds. Peak fuel and cladding temperatures are recorded to be around 2100o C and 650o C respectively, low enough to avoid failure. Maximum pressure inside reactor core structure is recorded to be 162 bar but pressure inside containment building has risen to around 13.5 bar after 300 seconds time. Applications: PCTRAN is one of the most reliable simulation tools for analyzing a nuclear facility. The results obtained from this study may be used as a reference for designing different components and safety systems of VVER-1200 based nuclear power plants so that the risk of a severe accident is minimized. Keywords: Loss of Coolant Accident, Safety Systems, Transient Response, VVER-1200

Highlights

  • Nuclear power plants are believed to be green energy sources due to very low Carbon footprint[1]

  • It may be observed that Containment Vent Valve (CVV) is closed as radioactive coolant came in direct contact with air inside the Reactor Containment Building (RCB)

  • SCRAM is initiated within 7.5 seconds from the initiation of Loss of Coolant Accident (LOCA), the power generated in the reactor core is reduced considerable

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Summary

Introduction

Nuclear power plants are believed to be green energy sources due to very low Carbon footprint[1]. Island accident in 1979, neither radioactive emission to the atmosphere nor any casualty was recorded It was the first time people got concerned about the safety of a nuclear power plant. This followed by Chernobyl nuclear accident in 1986 which caused death of around 31. The large-scale radioactive contamination due to this accident, both in seawater and soil, has created concern among many researchers[5, 6]. Due to these accidents with long-term consequences, many global communities have continued advocating against nuclear energy. Due to widespread awareness programs running in different countries, the view of common people has become somewhat positive towards nuclear power in recent times[7, 8]

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