| The 21st century is the century of the ocean. The underwater vehicle will play an important and active role in many fields, such as protecting the nation's territory and resources of the ocean, speeding up the development of the brink-science and the sophisticated technology, and highlighting the nation's status in the world. The capability and functions' improvement for the underwater vehicle makes a higher requirement in the propulsion system, so it is badly needed in the studying of the propulsion system for the underwater vehicle. This project comes from the 211 research project, and it is financed by the foundational research fund of science application in ship industry for the national defence.In this paper, the development and new technique in the ship propulsion system are studied, and a novel concept of nuclear powered propulsion system is excogitated which can be used in underwater vehicles. This new type of propulsion system is consisted of minitype fast reactor, alkali-metal thermal-to-electric conversion (AMTEC) device, steam-guide spray-water thruster, superconducting magneto-hydrodynamic (MHD) propulsor and so on. Heat is produced by the minitype fast reactor in the system and then AMTEC device directly transform the heat into electricity power, at same time,sodium heat pipes control the ratio of thermal to electricity finally the vehicle is propelled by the MHD propulsor together with steam-guide spray-water thruster. There is no traditional mechanism noise in this system, and the energy efficiency is increased. The system is quiet, safey, and easy to control.So it will fit the development direction of the future ship propulsion system.As a main part of the new type nuclear-powered propulsion system, the conceptual design of small sodium-cooled fast reactor used Beryllium as reflect layer is finished by 321 division of power and nuclear engineering colledge of Harbin engineering university and Theoreticl Division of Fast Reactor China Institute of Atmomic Energy. The paper will present the design firstly, and analyse characteristics of the minitype fast reactor's core and todiscuss the possibility and security using the reactor in this novel propulsion system secondly.To make these works done, a physical model and thermal-hydraulic model are setup. A code FRTRANS is developed as analyse means based on these models. The code is programmed with FORTRAN language. It can calculate the core physical and thermal hydraulic parameters under the conditions of steady state operation and transient state operation such as reactivity insertion accident (RIA), loss of flow accident (LOFA), coolant inlet temperature transient and so on. The function of reactor shutdown system can be simulated by the code to calculate the operating parameters after accidental shutdown. The models and calculate results of the code are proved correctly by comparison with NKF and DINROS calculating China Experimental Fast Reactor'core performance. As a result, the code can be used as a tool for core analyse of fast reactor and similar.Finally, the steady state analysis and transient analysis of MFR core are made by FRTRANS. Passive safety is discussed in RIA and LOFA. And then the function of shutdown system is discussed. Sentivity of reactivity feedback coefficients is analysed too. Three suggestions are made to improve the conceptual design of reacor according to above work.A new domain of ship propulsion system is spread by putting forward the concept of the novel nuclear-powered propulsion system. FRTRANS code fills the vacancy of fast reactor transient analysis code.
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