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• Using compressed air as energy to deal with LOCA of marine nuclear power plant. • Coordinated control of safety injection system with IFCU. • Safety injection model of marine nuclear power plant is established and simulated. In case of a large or medium LOCA accident of marine nuclear power plant, the loop pressure drops rapidly. In case of power failure of the whole ship at this time, the active safety injection system will lose its function because the safety injection pump needs AC power, and the core is at risk of melting. A passive marine safety injection system based on high-pressure compressed gas is designed for the superposition of large and medium LOCA accidents and the whole ship's power failure accidents, including the safety injection subsystem of medium and low pressure and the safety injection subsystem of recirculation. The energy required for safety injection is provided by the potential energy of compressed gas, the pressure head is provided by the technology of gas-liquid booster pump, and the collection signals and valves are controlled by the technology of intelligent fluid control unit with small power consumption. The power supply used in the system is provided by DC 24 V battery. The mathematical and physical models of accumulator, gas storage tank, gas-liquid booster pump, reactor body and its pipeline are established for the designed passive safety injection system. The operation and safety characteristics of medium pressure safety injection, low pressure safety injection and recycling safety injection under LOCA accident conditions are simulated. The safety injection time and flow rate of three safety injection pressures are simulated by medium pressure safety injection, the safety injection time and peak temperature are simulated by low pressure safety injection, and the pressure and system temperature are simulated by recirculation safety injection. The simulation results show that the marine passive safety injection system designed under LOCA accident conditions can meet the requirements of core cooling. [ABSTRACT FROM AUTHOR]

Li, W. and Yu, H., 2020. Radiation solution method of marine nuclear power plant based on 3D neutron transport equation. In: Yang, Y.; Mi, C.; Zhao, L., and Lam, S. (eds.), Global Topics and New Trends in Coastal Research: Port, Coastal and Ocean Engineering. Journal of Coastal Research, Special Issue No. 103, pp. 535–538. Coconut Creek (Florida), ISSN 0749-0208. With the wide application of nuclear energy in marine nuclear power plant, the nuclear safety analysis of marine nuclear power reactor has become inevitable, and has been gradually concerned. Radiation safety criterion is an important index of safety analysis of nuclear power plant. Because of the characteristics of the reactor, its radiation protection management has higher and more strict requirements, which makes strengthening radiation protection become an important task of the reactor. The radiation solution method of marine nuclear power plant based on 3D neutron transport equation is proposed. Firstly, the program mathematical model of dose field analysis of marine nuclear power reactor cabin is constructed to obtain the radiation dose field of marine nuclear power reactor cabin. Then, based on the obtained nuclear radiation measurement field information, the radiation solution of the marine nuclear power plant is realized by the discrete solution method based on the 3D neutron transport equation. It is verified that the method has high accuracy and credibility for radiation calculation of an offshore nuclear power plant. [ABSTRACT FROM AUTHOR]