Simulation Study On Severe Accident Mitigation Strategy Of Floating Nuclear Power Platform IP200-F

Floating nuclear power platform is one of the hot trends in the future development of nuclear power.However,severe accident analysis for the small integrated pressurized water reactor(IPWR)mainly used in floating nuclear power platform is still lacking.Due to the different characteristics of IPWR,the study of its severe accident phenomenon should be cautious.Based on the analysis of the severe accident process,identify the weak links of the nuclear power platform,identify the mechanism that may cause hidden dangers to key safety functions,formulate appropriate accident management strategies,and form systematic severe accident management guidelines to ensure the most possible The safety of personnel and the environment under conditions is a necessary condition for the power nuclear power platform to operate well in the end.In this paper,IP200-F is taken as the research object,and the special safety facilities and containment system are reconsidered according to the use background of its floating platform.This paper takes the small integrated pressurized water reactor IP200-F as the research object.According to the use background of its floating platform,the special safety facilities and containment system are reconsidered,and the larger containment and more safety measures are adopted than the ordinary marine nuclear power system.To improve accident response capabilities.Use the modular severe accident analysis program MAAP to model the IP200-F main system and the special safety facilities.After the steady state verification of the whole system,the loss-of-coolant accident(LOCA)and the station black-out(SBO)accidents are caused without active mitigation measures.The transient process is analyzed,and the process of the entire system in a typical low-pressure state accident and a high-pressure state accident are discussed separately.Analyze the obtained data,propose reasonable mitigation strategies for severe accidents,and then verify the entry conditions of the severe accident management guidelines(SAMG)and the effects that can be achieved by investing different mitigation measures at different time nodes in the accident sequence.The results show that CET=923K has different time characteristics in the two accident scenarios.For LOCA accident sequence,CET=923K is very suitable as SAMG entry criterion,but for SBO accident sequence,the time point of CET=923K is earlier than the core damage point,so there is still room to perform EOP.The mitigation strategy of IP200-F severe accidents is verified by simulation.Compared with the large-scale distributed nuclear power system,in the application background of floating nuclear power platform,the reactor cabin and RCS form a more closely connected whole,and the control of the state of the RPV is achieved by intervening in the reactor cabin conditions.It is more in line with the accident characteristics of floating nuclear power platforms.It provides a reference for the safety assessment of IPWR and the subsequent comprehensive development of SAMG for floating nuclear power platforms.