Nuclear reactor with cooling apparatus and method

A nuclear reactor arrangement for a nuclear power generation plant, comprising:

• a reactor container having a first space for housing a gas disposed in an upper portion thereof and a second space disposed in a lower portion thereof;
• an internal structure arranged in the reactor container, said second space being separated from the first space by the internal structure;
• a reactor core for heating a power transfer fluid to generate electric energy;
• a pressure vessel surrounding the reactor core and arranged in said second space;
• wherein the internal structure includes a pressure suppression chamber surrounding the pressure vessel, the prsesure suppression chamber comprising a liquid phase portion holding cooling water and a vapor phase portion interfacing the liquid phase portion;
• vent passages for supplying a condensed steam, discharged into the second space from the pressure vessel, into the liquid phase portion of the pressure suppression chamber;
• a first gas guide structure forming a downward path for supplying the gas from the first space into the vapor phase portion;
• a second gas guide structure forming an upward path for supplying the gas, after being heated by the cooling water in the liquid phase portion, into the first space from the vapor phase portion;
• a duct arranged outside of the reactor container for cooling a wall of the reactor container;
• and
• means for producing power for circulating said gas.

A nuclear reactor arrangement for a nuclear power generation plant, comprising:

• a reactor container having a first space for housing a gas disposed in an upper portion thereof and a second space disposed in a lower portion thereof;
• an internal structure arranged in the reactor container, said second space being separated from the first space by the internal structure;
• a reactor core for heating a power transfer fluid to generate electric energy;
• a pressure vessel surrounding the reactor core and arranged in said second space;
• wherein the internal structure includes a pressure suppression chamber surrounding the pressure vessel, the pressure suppression chamber comprising a liquid phase portion holding cooling water and a vapor phase portion interfacing the liquid phase portion;
• vent passages for supplying a condensed steam, discharged into the second space from the pressure vessel, into the liquid phase portion of the pressure suppression chamber;
• a first gas guide structure forming a downward path for supplying the gas from the first space into the vapor phase portion;
• a second gas guide structure forming an upward path for supplying the gas, after being heated by the cooling water in the liquid phase portion, into the first space from the vapor phase portion;
• a duct arranged outside of the reactor container for cooling a wall of the reactor container;
• and
• wherein said first and second gas guide structures positively guide the gas to flow in respective predetermined guide paths in the event of an accident causing disruption of the reactor operations with said gas effecting a cooling circulation powered by decay heat from the reactor core.