High temperature gas cooled reactor steam generation system

A high temperature gas cooled reactor steam generation system comprising:

• a nuclear reactor that has helium gas as a primary coolant and heats the primary coolant by heat generated by a nuclear reaction that decelerates neutrons by a graphite block;
• a steam generator that has water as a secondary coolant and heats the secondary coolant by the primary coolant via the nuclear reactor to generate steam;
• a primary coolant discharging unit that circulates the primary coolant between the nuclear reactor and the steam generator;
• a steam turbine that is operated by the steam from the steam generator;
• a generator that generates electricity according to an operation of the steam turbine;
• pressure control means including a pressure difference calculation unit that includes a primary coolant pressure detection unit disposed at an inlet of the primary coolant discharging unit and configured to detect a pressure of the primary coolant and a secondary coolant pressure detection unit disposed at an outlet of the steam generator and configured to detect a pressure of the secondary coolant and to calculate a pressure difference between the primary coolant and the secondary coolant based on the detected pressures;
• and
• pressure adjustment means including a primary coolant storage unit configured to store the helium gas therein and configured to set a pressure of the secondary coolant in the steam generator to be lower than a pressure of the primary coolant in the nuclear reactor based on the pressure difference and a primary coolant recovery and supply setting unit configured to control the primary coolant storage unit to recover or supply the primary coolant based on the pressure difference calculated in the pressure difference calculation unit.