Pressurized water reactor and high-temperature gas cooled reactor-based hybrid thermodynamic cycle system

Abstract

The invention discloses a pressurized water reactor and high-temperature gas cooled reactor-based hybrid thermodynamic cycle system, which belongs to the technical field of nuclear power energy. The hybrid thermodynamic cycle system comprises a steam generator, a steam turbine, a moisture separator re-heater, a condenser, a condensate pump, a gland steam condenser, low-pressure heaters, a deaerator, a water-feeding pump and high-pressure heaters which are connected according to a thermodynamic cycle process. Steam super-heater pressure shells of two modular high-temperature gas cooled reactors connected in parallel are connected between the steam generator and a high-pressure cylinder in a secondary circuit of a pressurized water reactor nuclear power station. Saturated steam generated by the steam generator performs heat exchange with high-temperature helium in steam super-heaters, and superheated steam flows out of the steam super-heaters and is converged to enter the high-pressure cylinder for working. Therefore, the system is favorable for greatly improving the cycle thermal efficiency of the two loops of the conventional pressurized water reactor, can improve the running security of the steam turbine, and has high economic benefit.

Description

technical field [0001] The invention belongs to the technical field of nuclear power energy, and in particular relates to a hybrid thermodynamic circulation system based on a pressurized water reactor and a high-temperature gas-cooled reactor designed for the structural design of a secondary circuit system of a pressurized water reactor nuclear power plant. Background technique [0002] The layout of the secondary circuit system of the pressurized water reactor nuclear power plant is as follows: figure 1 As shown, its main equipment includes: steam generator, steam turbine, steam-water separation reheater, condenser, condensate pump, shaft seal cooler, low-pressure heater, deaerator, feed water pump and high-pressure heater. In the full power operation state, the saturated steam generated by the steam generator 1 enters the high-pressure cylinder 2 from the main steam pipeline to expand and do work, and part of the steam is pumped from different stages of the high-pressure c...

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Problems solved by technology

[0004] From the thermodynamic cycle process of the above-mentioned PWR nuclear power plant, it can be seen that the steam parameters of the secondary loop of the PWR nuclear power plant are restricted by the parameters of the primary loop, and its temperature and pressure values ​​are usually low, which obviously reduces the cycle thermal efficiency of the entire secondary loop; in addition, the high-pressure cylinder It works completely in the state of wet steam, and the water brush of the final blade is serious, which greatly reduces the efficiency and safety of the high-pressure cylinder

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