Safety Analysis of Pressurized Water Reactor (PWR) Type Nuclear Reactor Against Cooling System Failure
Keywords:
Pressurized Water Reactor (PWR), Cooling System Failure Nuclear Safety, Emergency Core Cooling Systems (ECCS), Probabilistic Risk Assessment (PRA)Abstract
This research investigates the safety of Pressurized Water Reactors (PWRs) with a specific focus on the potential risks associated with cooling system failure. The cooling system in PWRs is critical for maintaining reactor temperature and preventing overheating, yet its failure can lead to severe consequences, including core damage and radiation release. Using a combination of probabilistic risk assessment (PRA), failure mode analysis, and simulation modeling, this study examines various failure modes of the cooling system, evaluates the effectiveness of existing safety measures such as emergency core cooling systems (ECCS) and backup cooling systems, and explores the role of human factors in reactor safety. The research also compares its findings with historical incidents like the Three Mile Island and Fukushima Daiichi accidents to contextualize the risks and highlight improvements in modern reactor design. The results emphasize the importance of redundancy, reliability, and emerging technologies in mitigating the risks of cooling system failures. Based on these findings, the study offers recommendations for enhancing the resilience of PWR cooling systems, suggesting both technical improvements and safety protocol updates. This research contributes to the ongoing efforts to improve nuclear reactor safety, ensuring that PWRs can operate efficiently while minimizing the risks to public health and the environment.
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