Thermotechnical design method suitable for sodium water once-through steam generator

Abstract

The invention discloses a thermotechnical design method of a sodium water once-through steam generator. The method comprises the following steps: determining thermal parameters of the sodium water once-through steam generator and geometrical parameters except the length of a heat transfer tube; establishing a steam generator single-tube model, and setting the initial pressure and temperature of the steam generator; obtaining the fluid temperature of each fluid control body by using a power grid method; dividing a heat exchange area to calculate a heat exchange coefficient and a heat exchange amount, and solving a wall temperature according to an energy balance relation of heat conduction and convective heat exchange; solving the length of each fluid control body on the heat transfer pipe according to the heat balance equation and the heat transfer equation; calculating the pressure drop of each fluid control body to obtain new pressure distribution. The invention relates to a universalthermal design calculation method for a sodium-water once-through steam generator. The method is convenient to operate, high in universality, flexible to use and high in precision, the thermal designcalculation requirement of the sodium-water once-through steam generator can be met, and a software basis can be provided for independent design of the sodium-cooled fast reactor in China.

Description

technical field [0001] The invention belongs to the technical field of thermal hydraulic design of fast neutron reactor steam generators, and in particular relates to a thermal design method suitable for sodium-water once-through steam generators. Background technique [0002] Sodium-cooled fast reactor (SFR), as one of the limited research and development cores of the fourth-generation nuclear energy system, has the advantages of improving the utilization rate of uranium and transmuting long-lived radioactive waste. To date, there are more than 400 years of reactor operating experience based on experimental, prototype and demonstration sodium-cooled fast reactors around the world. The sodium-water once-through steam generator (OTSG) is a key component of the sodium-cooled fast reactor nuclear power plant, which is of great significance to the safe operation of the nuclear power plant. The steam generator is the boundary between sodium and water, and it transfers the heat g...

AI Technical Summary

Problems solved by technology

Existing thermal design procedures for sodium-water once-through steam generators are either only applicable to integral steam generators or only to modular steam generators

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