<p>Compared with the land-based nuclear power plant, the ship nuclear power platform has the advantages of good flexibility, environmental protection, safety and economy. In this paper, the complete accident analysis calculation model of the ship nuclear power platform is established by using the developed accident analysis system code SACO,&nbsp;which is coupled with ocean conditions.&nbsp; Combined with the accident progress of loss of main feedwater ATWS under ocean conditions, and on the basis of considering the reasonable assumption of the accident boundary, the loss of main feedwater ATWS accident under ocean conditions is analyzed. The accident sequence of loss of main feedwater ATWS is given, and the changes of the key thermal safety parameters such as the reactor power, heat removal from the active residual heat removal system, primary circuit pressure, pressurizer water volume, average reactor coolant temperature, peak temperatures of the fuel pellet and cladding are analyzed in detail. The results show that the active residual heat removal system, reactor core reactivity feedback and design of the pressurizer safety valve could limit the primary circuit pressure and other key parameters without exceeding the safety limit value in the case of loss of main feedwater ATWS accident for ship nuclear power platform.</p>

Loss of Main Feedwater ATWS Accident Analysis for Ship Nuclear Power Platform

Paper Proceedings: https://asmedigitalcollection.asme.org/ICONE/ICONE28/volume/85246

2021 28th International Conference on Nuclear Engineering (ICONE28)

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