Circulating heat and power cogeneration system for stair type heat supplying supercritical carbon dioxide used for sodium-cooled fast reactor

Abstract

The invention discloses a circulating heat and power cogeneration system for stair type heat supplying supercritical carbon dioxide used for a sodium-cooled fast reactor, and belongs to the technicalfield of efficient utilization of clean energy. The system aims at solving the problems that a traditional heat and power cogeneration system is lower in thermal circulating efficiency and cannot achieve stair type heat supplying, and hidden safety danger exists in sodium-water actuating medium heat conduction. A first loop absorbs heat of a heat source through a sodium-sodium heat exchanger, theheat is exchanged to a second loop through a sodium-carbon dioxide heat exchanger, and a second loop low-temperature heat regenerator achieves switching between a simple circulating form and a partialcooling circulating form, thereby utilizing heat for power generation or achieving stair type heat supplying in the power generation process. The circulating heat and power cogeneration system for stair type heat supplying supercritical carbon dioxide used for the sodium-cooled fast reactor adopts a novel circulating actuating medium for replacing a water-steam actuating medium used by an existing experiment reactor, the efficiency of an original system is reached or exceeded, switchable nuclear piling heat and power cogeneration is achieved, the sodium piling characteristics are reasonably utilized, running parameters of the actuating medium are combined, and the safety of a nuclear piling system is significantly improved.

Description

technical field [0001] The invention relates to a cogeneration system of heat and power, in particular to a cascade heating supercritical carbon dioxide cycle cogeneration system for sodium-cooled fast reactors, and belongs to the technical field of efficient utilization of clean energy. Background technique [0002] The sodium-cooled fast reactor in the new generation of nuclear power is currently a relatively comprehensive development and a key development reactor type that has been verified to be reliable through experiments. The conventional island of the sodium-cooled fast reactor currently mainly uses steam-water working medium, but due to the low temperature of the steam (about 480 ℃), leading to low thermal cycle efficiency. In addition, the sodium-water reaction will produce sodium hydroxide, a highly corrosive substance, and hydrogen, an explosive gas, which will affect the safety of the nuclear reactor. Once the pipeline of the sodium-water heat exchanger leaks, t...

AI Technical Summary

Problems solved by technology

[0004] The purpose of the present invention is to provide a cascade heating supercritical carbon dioxide cycle combined heat and power system for sodium-cooled fast reactors, to solve the problem of l

Images