| In this article, the experiment platform of the control system of one 300kw once-through steam generator(SG), which is a part of the naval vessel nuclear power laboratory-the tenth five-year-constructing-project in HEU "211" project is designed. This once-through SG represents the developing direction in the future. Because of its high boiling heat transfer coefficient, compact structure and good maneuverability, it has become the main research object in experimental simulation of control system of nuclear power SG.This design is based on the model of Japan MRX and the Russia reactor of ABV-6M, both of which are advanced in the world in design of integral nuclear reactor .This thesis has carried through the thermal hydraulic design , structure design of helical coil type SG and once-through tube SG separately with the same inlet parameters . At same time , this paper carries out the design and Calculation of the whole secondary loop system , which is mainly composed of SG .This paper also includes the design and Calculation of thermal hydraulic and structure of SG which consume the overheated water temperature and high pressure , the calculation and type chosen of the desecrator deoxidize equipment, the design and type chosen of the water processor, the design of the plane arrangement of the whole system . This work provides the platform to the study for the stability in control system of once-through SG and the study for the coordinated control of relatedsystems . In addition, it provides the experimental equipments to further study of heat transfer model of the once-through SG.
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