The invention relates generally to the nuclear energy field, and more particularly to systems for passive heat removal from the pressurized water reactor through the steam generator (SG PHRS), and is designed for reactor cooling by natural circulation of the coolant (water) in the system circuit. The technical result of the invention is increase of heat removal efficiency, coolant flow stability in the circuit and, consequently, system operation reliability. The system for passive heat removal includes at least one coolant (water) circulation circuit comprising a steam generator and a section heat exchanger located above the steam generator in the cooling water supply tank and connected to the steam generator by means of the inlet pipeline and the outlet pipeline. The heat exchanger includes an upper header and a lower header interconnected by heat-exchange tubes, startup valves with different nominal bores are installed on the outlet pipeline. In addition, the heat exchanger is divided into parallel sections based on the assumption that L/D ‰¤ 20, where L is the half-section length, D is the header bore. The inlet pipeline and the outlet pipeline sections of the circulation circuit are designed as a set of branched parallel pipelines that are individually connected to each of the above heat exchanger sections.