| Nuclear power has been confirmed and widely recognized as a safe, clean and efficient energy. The huge damage of the nuclear accident results in enough attention to nuclear safety. C3high pressure cooler as a cooling equipment of reactor coolant is to ensure seal performance of main pump in the nuclear reactor coolant system and the safety of nuclear power plant working. It plays an important role in the nuclear power plant.C3helical-coil cooler researched in this paper is an important auxiliary equipment of the main pump in the nuclear reactor coolant system. Firstly we have a research in cooler structure and flow heat transfer characteristics according to the existingtheoretical formula. We make assumptions and analysis on the flow and heat transfer way in cooler in the theory calculation process. According to the existing calculation formula and structural features of the cooler itself, we have the reasonable selection and correction. However, the complexity of the tube side, shell side and export section structure of cooler results in having no appropriate calculation model for this part by existing calculationtheoretical formula. The error between theoretical calculation and actual calculation is larger. Then we have a calculation simulation, we find the result that reasonable real structure form of simulation reduces outlet temperature of tube side fluid effectively through the compare between simulation and theoretical calculation results, but there is still a lot of optimization space. Through the analysis of the structure of the cooler, we confirm that the regulation parts of parallel line is the core component of flow heat transfer equipment and we carry on the two kinds of structure forms of optimization. Corresponding conditions of the structure form â… effectively reduce the tube side temperature7℃above. The change of structure form â…¡ reduce the tube side outlet temperature about10℃.The change of structure form has significant effect on improving heat transfer performance of the equipment. In order to further understand each point pressure distribution of circumferential wall when "cylindrical " incoming flow flow around adjustment part, we do the relevant experimental validation study, so as to verify the feasibility of controlling flow distribution within adjustment part by trepanning on circumferential different position of adjustment part. |