Abstract
The high temperature gas-cooled reactor pebble-bed module (HTR-PM) being built by the Institute of Nuclear and New Energy Technology of Tsinghua University in China is a typical Generation IV nuclear power system. The subcritical steam generators in HTR-PM can be replaced by the supercritical steam generators to work with the current reactors and a supercritical steam turbine to improve the thermal efficiency, which is being presented in the third technical phase of the HTR-PM program in China. The supercritical high temperature gas-cooled reactor pebble-bed module system scheme is proposed based on HTR-PM. A supercritical steam generator with helically coiled tubes is designed. Parameters of the geometry and the design conditions are listed in detail. The heat transfer performance of the supercritical steam generator is analyzed, and the heat flux, the temperature variation and the heat transfer coefficient along the tube are shown. The effects of the transverse and longitudinal pitches between the tubes in the supercritical steam generator are very important. The tube length, tube bundle height, and the deviation of the tube length in various layers are compared with various transverse and longitudinal pitches and the optimal relative transverse and longitudinal pitches are illustrated.
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