b"Engineer Innovation | Power DistributionDesign of a Sodium-Water Reaction Pressure Relief System of Prototype Generation-IV Sodium-Cooled Fast ReactorBy Sun Hee Park and Ji-Woong Han, Korea Atomic Energy Research InstituteWith the growing level of carbonHowever, one of the dangers of thisclosed loop intermediate heat transfer dioxide (CO ) in the atmosphere, ittype of reactor is how reactive sodiumsystem (IHTS) is circulated between the 2important to understand the biggestis with water and air. A sodium-waterprimary heat transfer system and the contributors and investigate options forreaction is an explosive exothermicsteam generator, never contacting air reduction. One of the largest sources ofreaction that generates hydrogen gasor water. carbon dioxide is power generation, anthat could result in a pressure increase area that will only continue to grow asin the system. This increase in pressureIt is however possible to have a steam the worlds population does the same.puts the integrity of the entire systemgenerator tube break or leak, which Among the many potential emergingat risk. Under normal operation this iscould cause a high pressure wave with technologies, nuclear energy is wellnever a concern as the sodium of thecorrosive reaction products created and positioned to contribute as a low emission supply of energy. Over the lastAtmosphere Nitrogen Supplyfew years, several countries have beenSystemexploring options for the nextV6generation of nuclear reactors. OneV3option currently in development by theHot Sodium Main SteamKorea Atomic Energy Research Institute (KAERI) is the Sodium-cooled FastArgon Process C1Reactor (SFR). SystemSince its establishment in 1959, KAERIAtmospherehas been the only research institute inC6Korea dedicated to nuclear energy.L1 Steam GeneratorOver the past 60 years, it hasL4accelerated developments in nuclearC4technology and made significant achievements, including theAtmosphereCold Sodiumlocalization of PHWR and PWR reactors, the design of a Nuclear Steam SupplyV1 L6 Feed WaterSystem (NSSS) - applied to Uljin Units 3C5 C2& 4 - and the design and constructionV4 V5 V2of the multi-purpose research reactorL3 L5 AtmosphereHANARO. As the first research instituteL2 L7 L8 L9of science and technology in Korea and one of the world's best centers ofC3 C7nuclear research, KAERI is building a safe society centered on people and theFigure 1. Schematic diagram of a SWRPRS. C1: Hot leg rupture disk, C2: Cold leg rupture disk, C3: environment. Sodium dump tank, C4: Back pressure rupture disk, C5: Gas-liquid separator, C6: Hydrogen igniter, C7: Water dump tank. L1: Hot leg sodium dump line, L2: Cold leg sodium dump line, L3: What makes the SFR unique is that itGas-liquid separator connection line, L4: Back pressure rupture disk gas vent line, L5: Cold leg uses molten sodium as the reactorsodium dump line, L6: Feedwater supply line, L7: Small diameter SG water dump line, L8: Large coolant. This allows for a much higherdiameter SG water dump line, L9: WDT gas vent line. V1: Cold leg sodium dump line isolation valve, V2: Feed water isolation line valve, V3: Main steam line isolation valve, V4: Small diameter power density than a water cooledSG water dump line isolation valve, V5: Large diameter SG water dump line isolation valve, V6: reactor with a lower coolant volume.Nitrogen supply line isolation valve50"