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After the Fukushima disaster, interest in the evaluation of severe accidents in nuclear power plants and off-site consequences has significantly increased. Because experimental studies are difficult to conduct, computational methods play a substantial role in accident analysis. In this study, a severe accident in the Bushehr pressurized water reactor power plant caused by a station blackout with a...
The presented analysis carried out for the safety assessment of the Passive Residual Heat Removal System of secondary side (PRS), one of the Severe Accident Mitigating System of K-2/K-3 Nuclear power plants. Preliminary analysis of the PRS is carried out using computer code MELCOR, which is a thermal hydraulic code that models the progression of severe accidents in light water nuclear power plants...
The Fukushima accident that happened on March 11, 2011 has raised the possibility of severe accidents in an SFP under beyond design basis external events (BDBEEs) that might lead to a loss of all safety functions and need a way to cope effectively with such an event through a SFP risk and accident management. From a SFP safety point of view, the low decay heat of the fuel assemblies and large water...
Containment threats during severe accidents may arise due to fuel-coolant interactions, hydrogen combustion, molten core-concrete interactions, and long-term pressure and temperature loading. The objective of the paper is to bring out important issues in the assessment of containment integrity during severe accidents for PWR and PHWR. The issues are identified by extensive review and synthesis of...
Severe accident analysis of a reactor is an important aspect in evaluation of source term. This in turn helps in emergency planning and Severe Accident Management (SAM). The use of the severe accident management guideline (SAMG) is required for accident situation which is not handled adequately through the use of Emergency Operating Procedures (EOP), thus leading to a partial or a total core melt...
The Pressurised Heavy Water Reactor (PHWR) contains both inherent and engineered safety features that help the reactor become resistant to severe accident and its consequences. However in case of a low frequency severe accident, despite the safety features, procedural action should be in place to mitigate the accident progression. Usually for all these designs the Emergency Operating Procedures (EOPs)...
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