Substantiation of the parameters and layout solutions for an energy conversion unit with a gas-turbine cycle in a nuclear power plant with htgr

Light is shed on questions concerning the application of a direct closed gas-turbine cycle for generating electricity in a nuclear power plant with HTGR. This makes it possible to use such reactor systems for generating electricity and(or) producing hydrogen from water and combine high electricity-generation efficiency of 47-50% with high safety. It is shown that it is advantageous to use a recovery gas cycle with recovery efficiency of at least 95% and intermediate cooling of helium in a compressor. The choice of the configuration of the reactor system is substantiated. The heat-exchange equipment of the gas-turbine cycle should have unique characteristics when placed in vessels with limited size and for operation at high temperatures (up to 600C) and with a large pressure drop (up to 5 MPa). Approaches to solving the problems studied are elucidated on the basis of a modular helium reactor with a GT-MGR gas turbine.