Abstract: The method and system for bringing a nuclear power plant to a safe state after extreme effect reduce the temperature of the coolant after extreme effect. The system includes inlet and outlet pipelines, a steam generator, a storage tank and a heat exchanger, a separation tank above the steam generator and connected by two pipelines to a storage tank, a pump, a control unit. The method involves filling the system with coolant, feeding the coolant from the steam generator through the inlet pipeline and the storage tank to the heat exchanger, and feeding the coolant through the outlet pipeline back to the steam generator, wherein the pump is turned on for feeding the coolant and subsequent operation of the system. The first air valve is used to maintain pressure in the system, ensuring the absence of boiling of the coolant.

Abstract: Provided are a system and method for reducing the atmospheric release of radioactive materials caused by a severe accident. The system includes a steam generator disposed in a containment building, configured to generate steam by using heat of a coolant heated in a nuclear reactor, and connected to a turbine through a main steam line, a decontamination tank connected to the main steam line through a connection line and containing decontamination water for decontaminating the steam delivered from the steam generator and reducing atmospheric release of radioactive materials when a severe accident occurs, and a depressurizing power generation unit disposed on the connection line and configured to generate emergency power while depressurizing the steam delivered from the steam generator toward the decontamination tank when the severe accident occurs.

Abstract: A plurality of heat transfer pipes; a first header and a second header to which both ends of each of the heat transfer pipes that are disposed in parallel are fixed, respectively; a plurality of plate-shaped fins through which each of the heat transfer pipes is penetrated and that are provided at intervals in a direction in which the heat transfer pipes extend between the first header and the second header; and a fan that circulates an airflow between the plate-shaped fins are included. The first header and the second header are formed to be sectioned into multiple rows, the heat transfer pipes are disposed densely in an sectioned area of the first header and the second header, and the heat transfer pipes are disposed sparsely in an area between the sectioned areas of the first header and the second header.

Abstract: An integrated fan heat exchanger stator assembly is provided including a hub and a casing. A plurality of elements is arranged between the hub and the casing. The plurality of elements is separated from one another by a plurality of external flow passages. At least one internal flow passage is configured to convey a first heat transfer fluid through one or more of the plurality of elements. The first heat transfer fluid is arranged in thermal communication with a second heat transfer fluid configured to flow through at least one of the external flow passages.

Abstract: A component cooling water system for a nuclear power plant. In one embodiment, the system includes an inner containment vessel housing a nuclear reactor and an outer containment enclosure structure. An annular water reservoir is formed between the containment vessel and containment enclosure structure which provides a heat sink for dissipating thermal energy. A shell-less heat exchanger is provided having an exposed tube bundle immersed in water held within the annular water reservoir. Component cooling water from the plant flows through the tube bundle and is cooled by transferring heat to the annular water reservoir. In one non-limiting embodiment, the tube bundle may be U-shaped.

Abstract: A main pump shaft seal water injection system of a nuclear power plant includes a jet pump, a high pressure cooler, a hydrocyclone, valves and a main connection pipeline outside of a main pump, and an auxiliary pump and an internal flow path inside the main pump. Inner and outer flow paths of the main pump are connected with a shaft seal water injection hole and a high temperature water drainage hole. The main connection pipeline is connected between an upper filling water pipeline and a shaft seal water injection hole. A bypass pipeline connected with the jet pump, the high pressure cooler and the hydrocyclone, the main connection pipeline is provided with a normally open main pipeline isolating valve. The bypass pipeline allows low temperature upper filling water in the RCV system to enter the shaft seal water injection hole of the main flange directly.

Abstract: The present disclosure provides a cooling system of an emergency cooling tank, which enables long-term cooling without refilling cooling water, in case of the change in a quantity of heat transferred to the emergency cooling tank according to a lapse of time upon an occurrence of an accident of a nuclear reactor, and a nuclear power plant having the same. The emergency cooling tank cooling system includes an emergency cooling tank, a heat exchanging device installed to be exposed to an outside of the emergency cooling tank to operate in air, and configured to externally emit such that the operation of the emergency cooling tank is continued even without refilling the cooling water, and an opening and closing unit installed at an upper portion of the emergency cooling tank to be located higher than a water level of the cooling water.

Abstract: Provided are a nuclear reactor and an operating method for the reactor. The reactor includes a driving system and a safety system. The safety system includes isolation vessels, heat exchangers, a coolant pipe, and a communication pipe. Fluid is distributed in the safety system according to thermal, pressure, and leak conditions.

Abstract: A method, system, and apparatus for the thermal storage of nuclear reactor generated energy including diverting a selected portion of energy from a portion of a nuclear reactor system to an auxiliary thermal reservoir and, responsive to a shutdown event, supplying a portion of the diverted selected portion of energy to an energy conversion system of the nuclear reactor system.

Abstract: The heat exchanger comprises a heat exchanger body defining an exit plenum chamber shaped for uniform flow of a hot primary heat transfer fluid through the chamber. A plurality of adjacent heat transfer members are connected to the heat exchanger body define a plurality of flow passages between the heat transfer members and open into the exit plenum chamber. Spacing of the heat transfer members by a predetermined distance evenly distributes flow of the primary heat transfer fluid through the flow passages, across the surfaces of the heat transfer members and into the exit plenum chamber. Heat transfer occurs from the hot primary heat transfer fluid to the cooler secondary heat transfer fluid as the primary heat transfer fluid flows through the chamber and as the secondary heat transfer fluid simultaneously flows through the flow channel of each heat transfer member.

Abstract: Disclosed is a heat exchanger for a passive residual heat removal system, which improves heat transfer efficiency by expanding a heat transfer area. A heat exchange tube includes a first member connected to a steam pipe through which steam generated from a steam generator of a nuclear reactor circulates, and a second member connected to both of the first member and a feed water pipe used to supply water to the steam generator provided in the nuclear reactor, and the first member has the shape different from that of the second member, thereby expanding the heat transfer area so that the heat transfer efficiency is improved.

Abstract: A nuclear reactor is provided that includes a vessel; a core provided in the vessel; at least one plate heat exchanger provided in the vessel, with at least one duct for supplying a secondary fluid to the heat exchanger and a duct for discharging the secondary fluid from the heat exchanger, the discharge duct extending through the vessel. The nuclear reactor comprises a device for attaching the heat exchanger to an area of the vessel through which the discharge duct extends.

Abstract: A method and apparatus for providing an alternative remote spent fuel pool cooling system for the spent fuel pool. The cooling system is operated to cool the spent fuel pool in the event of a plant accident when normal plant electricity is not available for the conventional fuel pool cooling and cleanup system, or when the integrity of the spent fuel has been jeopardized. The cooling system is operated and controlled from a remote location, which is ideal during a plant emergency.

Abstract: The cooling duct assembly for a control element drive mechanism (CEDM) includes a skirt that is combined on a circumference of a reactor head and has first air channels in an inner side thereof; a lower duct that is combined with an upper side of the skirt, has second air channels that are connected to the first air channels, and is disposed to surround a circumference of the CEDM; and an upper duct, an edge of which is combined with the cooling air handling device, and other edge of which is detachably combined with the lower duct, wherein air that cools the CEDM is discharged to the outside after sequentially passing the first air channels, the second air channels, the upper duct, and the cooling air handling device, and the upper duct separated from the lower duct is lifted together with the cooling air handling device.

Abstract: A method and apparatus for providing an alternative remote spent fuel pool cooling system for the spent fuel pool. The cooling system is operated to cool the spent fuel pool in the event of a plant accident when normal plant electricity is not available for the conventional fuel pool cooling and cleanup system, or when the integrity of the spent fuel has been jeopardized. The cooling system is operated and controlled from a remote location, which is ideal during a plant emergency.

Abstract: A nuclear reactor cooling system with passive cooling capabilities operable during a reactor shutdown event without available electric power. In one embodiment, the system includes a reactor vessel with nuclear fuel core and a steam generator fluidly coupled thereto. Primary coolant circulates in a flow loop between the reactor vessel and steam generator to heat secondary coolant in the steam generator producing steam. The steam flows to a heat exchanger containing an inventory of cooling water in which a submerged tube bundle is immersed. The steam is condensed in the heat exchanger and returned to the steam generator forming a closed flow loop in which the secondary coolant flow is driven by natural gravity via changes in density from the heating and cooling cycles. In other embodiments, the cooling system is configured to extract and cool the primary coolant directly using the submerged tube bundle heat exchanger.

Abstract: A nuclear reactor cooling system with passive cooling capabilities operable during a loss-of-coolant accident (LOCA) without available electric power. The system includes a reactor vessel with nuclear fuel core located in a reactor well. An in-containment water storage tank is fluidly coupled to the reactor well and holds an inventory of cooling water. During a LOCA event, the tank floods the reactor well with water. Eventually, the water heated by decay heat from the reactor vaporizes producing steam. The steam flows to an in-containment heat exchanger and condenses. The condensate is returned to the reactor well in a closed flow loop system in which flow may circulate solely via gravity from changes in phase and density of the water. In one embodiment, the heat exchanger may be an array of heat dissipater ducts mounted on the wall of the inner containment vessel surrounded by a heat sink.

Abstract: A nuclear reactor includes a pressure vessel and a nuclear reactor core disposed in the pressure vessel. A subterranean containment structure contains the nuclear reactor. An ultimate heat sink (UHS) pool is disposed at grade level, and an upper portion of the subterranean containment structure defines at least a portion of the bottom of the UHS pool. In some embodiments, the upper portion of the subterranean containment structure comprises an upper dome, which may protrude above the surface of the UHS pool to define an island surrounded by the UHS pool. In some embodiments, a condenser comprising a heat exchanger including hot and cold flow paths is disposed inside the subterranean containment structure; and cooling water lines operatively connect the condenser with the UHS pool.

Abstract: The underwater electricity production module according to the invention, of the type including means in the form of an elongated cylindrical box (12) in which means are integrated forming an electricity production unit including means forming a nuclear boiler (30), associated with electricity production means (37) connected to an external electricity distribution station by electrical cables, is characterized in that the nuclear boiler-forming means (30) are placed in a dry chamber (19) of the reactor compartment (18) associated with the chamber forming a safety water storage reservoir (20) of the reactor whereof at least the radial wall (53) is in a heat exchange relationship with the marine environment.

Abstract: A nuclear reactor module includes a reactor vessel and a reactor housing mounted inside the reactor vessel, wherein the reactor housing comprises a shroud and a riser located above the shroud. The nuclear reactor module further includes a heat exchanger proximately located about the riser, and a reactor core located in the shroud. A steam generator by-pass system is configured to provide an auxiliary flow path of primary coolant to the reactor core to augment a primary flow path of the primary coolant out of the riser and into the shroud, wherein the auxiliary flow path of primary coolant exits the reactor housing without passing by the heat exchanger.

Abstract: According to an embodiment, a pressurized water reactor plant has a primary system which includes: a reactor vessel for housing a reactor core which is cooled by a primary coolant, a single steam generator, a hot leg pipe for connecting the reactor vessel and the steam generator, cold leg pipes, at least two primary coolant pumps, and a pressurizer for pressurizing the primary coolant pressure boundary in which the primary coolant flows. The plant also has: a passive cooling and depressurization system which is a primary depressurization means for equalizing the primary system pressure to the secondary system pressure at the time of a tube rupture accident of the steam generator, and a reactor containment vessel containing the primary system and cooling the primary system by air cooling. Thus, a compact pressurized water rector with high economic efficiency, safety, and reliability can be provided.

Abstract: The underwater electricity production module according to the invention includes means in the form of an elongated cylindrical box (12) in which means are integrated forming an electricity production unit including means forming a nuclear boiler (30), associated with electricity production means (37) connected to an external electricity distribution station (7) by electrical cables (6), is characterized in that the nuclear boiler-forming means (30) include a secondary circuit (36) associated with the electricity production means (37) and a secondary backup circuit (60) in parallel on that secondary circuit and including at least one secondary passive heat exchanger (61) placed outside the underwater module (12) in the marine environment.

Abstract: A method of harnessing geothermal energy to produce electricity by lowering a geothermal generator deep into a pre-drilled well bore below the Earth's surface. The Self Contained In-Ground Geothermal Generator (SCI-GGG) includes a boiler, a turbine compartment, an electricity generator, a condenser and produces electricity down at the heat sources and transmits it up to the ground surface by cable. The Self Contained Heat Exchanger (SCHE) is integral part of (SCI-GGG) system and can function independently. It consists of a closed loop system with two heat exchangers. No pollution is emitted during production process. There is no need for hydro-thermal reservoirs although not limited to hot rocks. It can be implemented in many different applications. The SCHE also includes an in-line water pump operatively coupled to the closed loop system and can be used in many different applications.

Abstract: In a cooling structure and a cooling method for a control rod drive mechanism and in a nuclear reactor, a housing (59) in which magnetic jacks are housed is fixed to an upper portion of a reactor vessel (41), and an air intake unit (102) that takes cooling air into the housing (59), a first exhaust duct (104) that is arranged side by side with the air intake unit (102) in a circumferential direction of the housing (59), into which cooling air in the housing (59) is suctioned through a first inlet (109) at a lower portion thereof, and that guides the cooling air upward, a second exhaust duct (105) that is disposed below the air intake unit (102), into which cooling air in the housing (59) is suctioned through a second inlet (110), and that guides the cooling air to the first exhaust duct (104), and a discharging unit (111) that is formed at an upper portion of the housing (59) and discharges cooling air in the first exhaust duct (104) to the exterior are provided.

Abstract: A method and apparatus for an alternative cooling system used to cool the suppression pool of a Boiling Water Reactor (BWR) nuclear reactor. The cooling system includes a cooling coil in an isolation condenser located at an elevation that is above the suppression pool. The isolation condenser is connected to the suppression pool via inlet and outlet pipes. The system may provide a natural convection flow of fluids between the suppression pool and the cooling coils to passively cool fluid from the suppression pool without requiring external electrical power.

Abstract: A method and system for an alternate energy removal path for a reactor pressure vessel (RPV) of a light water reactor. A pair of manually operated containment isolation valves, one located inside and one located outside of primary containment, are used to open and close a steam extraction line that is fluidly coupled between the RPV and a heat sink. The heat sink is located outside of primary containment. A source of external electrical power is not required to operate the system or perform the method.

Abstract: A method and system for external alternate suppression pool cooling for a Boiling Water Nuclear Reactor (BWR) that does not breach the Mark I primary containment. The external cooling system may include a heat sink fluidly coupled to cooling coils surrounding the suppression pool. Cool water may be pumped through the cooling coils without the need for normal plant electrical power, which is ideal during a plant emergency. The cooling system may also be operated and controlled from a remote location to protect the safety of plant personnel.

Abstract: Disclosed herein is a fully passive decay heat removal system utilizing a partially immersed heat exchanger, the system comprising: a hot pool; an intermediate heat exchanger which heat-exchanges with the sodium of the hot pool; a cold pool; a support barrel extending vertically through the boundary between the hot pool and the cold pool; a sodium-sodium decay heat exchanger received in the support barrel; a sodium-air heat exchanger provided at a position higher than the sodium-sodium decay heat exchanger; an intermediate sodium loop connecting the sodium-sodium decay heat exchanger with the sodium-air heat exchanger; and a primary pump, wherein a portion of the effective heat transfer tube of the sodium-sodium decay heat exchanger is immersed in the cold pool, particularly in a normal operating state, and the surface of the lower end of a shroud for the sodium-sodium decay heat exchanger, the lower end being immersed in the sodium of the cold pool, has perforated holes.

Abstract: A pressurized water nuclear reactor (PWR) has an internal pressurizer volume containing a steam bubble and is surrounded by a containment structure. A condenser is disposed inside the containment structure and is operatively connected with an external heat sink disposed outside of the containment structure. A valve assembly operatively connects the PWR with the condenser responsive to an abnormal operation signal such that the condenser condenses steam from the steam bubble while rejecting heat to the external heat sink and returns the condensed water to the PWR. A quench tank contains water with dissolved neutron poison. A valved tank pressurizing path selectively connects the steam bubble to the quench tank to pressurize the quench tank, and a valved soluble poison delivery path selectively connects the quench tank to the PWR such that the quench tank under pressure from the steam bubble discharges water with dissolved neutron poison into the PWR.

Abstract: A combined makeup tank and passive residual heat removal system that places a tube and shell heat exchanger within the core makeup tank. An intake to the tube side of the heat exchanger is connected to the hot leg of the reactor core and the outlet of the tube side is connected to the cold leg of the reactor core. The shell side of the heat exchanger is connected to a separate heat sink through a second heat exchanger.

Abstract: A residual heat removal system for a nuclear power plant. The residual heat removal system for a nuclear power plant may include an air duct provided on an outside of a reactor containment building, a heat exchanger disposed on an inside of the air duct, a first pipe to transfer, to the heat exchanger, steam generated in a steam generator disposed on an inside of the reactor containment building, and second pipe to transfer, to the steam generator, water condensation that is cooled and condensed in the heat exchanger, wherein the heat exchanger is air-cooled using outside air flowing inside of the air duct.

Abstract: A method and apparatus for providing an alternative remote spent fuel pool cooling system for the spent fuel pool. The cooling system is operated to cool the spent fuel pool in the event of a plant accident when normal plant electricity is not available for the conventional fuel pool cooling and cleanup system, or when the integrity of the spent fuel has been jeopardized. The cooling system is operated and controlled from a remote location, which is ideal during a plant emergency.

Abstract: A containment structure contains an interior volume, and a nuclear reactor is disposed in the interior volume. An ultimate heat sink pool is disposed outside of the containment structure. A condenser includes a plurality of closed-path heat pipes or closed-path thermosiphons having first ends and opposite second ends. The closed-path heat pipes or closed-path thermosiphons are embedded in the containment structure with the first ends protruding into the interior volume and the second ends protruding outside of the containment structure.

Abstract: An apparatus for generating medical isotopes provides an annular fissile solution vessel surrounding a neutron generator. The annular fissile solution vessel provides for good capture of the emitted neutrons and a geometry that provides enhanced stability in an aqueous reactor. A neutron multiplier and/or a neutron moderator may be used to improve the efficiency and control the criticality of the reaction in the annular fissile solution vessel.

Abstract: A nuclear reactor module includes a reactor vessel and a reactor housing mounted inside the reactor vessel, wherein the reactor housing comprises a shroud and a riser located above the shroud. The nuclear reactor module further includes a heat exchanger proximately located about the riser, and a reactor core located in the shroud. A steam generator by-pass system is configured to provide an auxiliary flow path of primary coolant to the reactor core to augment a primary flow path of the primary coolant out of the riser and into the shroud, wherein the auxiliary flow path of primary coolant exits the reactor housing without passing by the heat exchanger.

Abstract: A passive auxiliary condensing apparatus of a nuclear power plant includes a steam generation unit configured to heat a water supplied thereto into a steam by a heat produced when operating a nuclear reactor, a water cooled heat exchange unit connected to the steam generation unit and configured to store a cooling water therein to condense the steam provided from the steam generation unit, and a steam-water separation tank including a first side connected to the water cooled heat exchange unit and a second side connected to the steam generation unit, wherein a mixture of a water and a steam provided from the water cooled heat exchange unit is separated into the water and the steam to provide only the water to the steam generation unit.

Abstract: A passive cooling system of a nuclear power plant includes a cooling water storage tank configured to store a cooling water therein, a steam generation unit to which the cooling water is supplied from the cooling water storage tank connected thereto, the supplied cooling water being heated to generate a steam, a water cooling heat exchange unit connected to the steam generation unit and provided within the cooling water storage tank, and an air cooling heat exchange unit connected to the steam generation unit and provided outside the cooling water storage tank.

Abstract: A nuclear reactor system that, in one embodiment, utilizes natural circulation (i.e., thermosiphon) to circulate a primary coolant in a single-phase through a reactor core and a heat exchange sub-system. The heal exchange sub-system is located outside of the nuclear reactor pressure vessels and, in some embodiments, is designed so as to not cause any substantial pressure drop in the flow of the primary coolant within the heal exchange sub-system that is used to vaporize a secondary coolant. In another embodiment, a nuclear reactor system is disclosed in which the reactor core is located below ground and all penetrations into the reactor pressure vessel are located above ground.

Abstract: An auxiliary system for cooling a spent nuclear fuel pool through a submersible heat exchanger to be located within the pool. In each train or installation, a single loop or series of loops of cooling fluid (e.g., sea water or service water) is circulated. The system is modular, readily and easily installed during an emergency and can be self operating with its own power source. Multiple trains may be used in parallel in order to accomplish the required degree of spent fuel pool cooling required.

Abstract: A nuclear power station has a containment in which a reactor core is accommodated. According to the invention, an external cooling system for cooling the containment in the event of an accident is associated with the containment. The cooling system in particular has a coolant reservoir that is configured as a lake or is lake-like, and in which the containment is in contact with a coolant or may be brought into contact with a coolant, in particular a liquid coolant, in the event of an accident.

Abstract: A nuclear power plant with an improved cooling system using nanoparticles in solid or fluid form to improve heat transfer and reduce corrosion is provided. The nanoparticles are delivered to a closed cooling circuit such as a CCWS. Methods for providing the nanoparticles are also provided.

Abstract: A boiling water reactor includes a reactor pressure vessel; a steam pipe for transporting steam generated in the reactor pressure vessel out from a steam dome positioned at an upper part of the reactor pressure vessel; a high pressure turbine connected to the steam pipe and driven by the steam; a feedwater heater which heats feedwater supplied to the reactor pressure vessel using bleed steam flowing from the high pressure turbine to the feedwater heater; a bleeding valve which adjusts a flow rate of the bleed steam; and a pressure sensor provided in a main steam line including the steam dome and the steam pipe. The boiling water reactor further includes a monitor and control system which controls an opening degree of the bleeding valve based on a magnitude of fluctuating pressure in the main steam line that is detected by the pressure sensor.

Abstract: A method, system, and apparatus for the thermal storage of nuclear reactor generated energy including diverting a selected portion of energy from a portion of a nuclear reactor system to an auxiliary thermal reservoir and, responsive to a shutdown event, supplying a portion of the diverted selected portion of energy to an energy conversion system of the nuclear reactor system.

Abstract: A boiling water nuclear reactor comprises: a reactor containment vessel including a dry well and a wet well; a vent pipe connecting the dry well and the pressure suppression pool; a gravity-driven water injection pool to hold boric acid aqueous solution; an emergency core water-injection piping system for causing the boric acid aqueous solution in the gravity-driven water injection pool to fall so as to be injected into the reactor pressure vessel in case of reactor accident; a static containment vessel cooling system pool; a static containment vessel cooling system heat exchanger; a dry well connection pipe connecting an upper part of the static containment vessel cooling system heat exchanger and the dry well; and a gas vent pipe for discharging noncondensible gas in the static containment vessel cooling system heat exchanger into the inside of the pressure suppression pool.

Abstract: According to an embodiment, a pressurized water reactor plant has a primary system which includes: a reactor vessel for housing a reactor core which is cooled by a primary coolant, a single steam generator, a hot leg pipe for connecting the reactor vessel and the steam generator, cold leg pipes, at least two primary coolant pumps, and a pressurizer for pressurizing the primary coolant pressure boundary in which the primary coolant flows. The plant also has: a passive cooling and depressurization system which is a primary depressurization means for equalizing the primary system pressure to the secondary system pressure at the time of a tube rupture accident of the steam generator, and a reactor containment vessel containing the primary system and cooling the primary system by air cooling. Thus, a compact pressurized water rector with high economic efficiency, safety, and reliability can be provided.

Abstract: An emergency core cooling system comprises first and second safety divisions for an active emergency core cooling system. Each of the first and second safety divisions is provided with a high-pressure core cooling system and a low-pressure core cooling system, which also acts as a residual heat removal system.

Abstract: Pressurizer for a pressurized water nuclear power station, comprising an outer casing which delimits an inner space; a duct (11) which extends beneath the casing and which is capable of being tapped from the coolant system of the nuclear power station; a tap (18) which places the inner space of the casing in communication with the duct (11), this tap (18) being welded to the duct (11) by means of a weld seam (32); a sleeve (42) for protecting the weld seam (32), which sleeve is arranged inside the tap (18) and which has a lower peripheral edge (46) which is engaged in the duct (11), the sleeve (42) defining with the tap (18) and the duct (11) an annular space (74) which is capable of being filled with the primary liquid; wherein the annular space (74) is open along at least a portion of the lower peripheral edge (46) of the sleeve (42) and opens inside the duct (11).

Abstract: A natural-circulation type boiling water reactor according to the present invention includes a plurality of divided chimneys provided above a reactor core and a number of fuel assemblies are charged in the reactor core. The natural-circulation type boiling water reactor is provided with a pressure equalization structure arranged on rectangular-columnar lattice plates of the divided chimneys at an outlet of the reactor core for equalizing pressures in divided chimney portions so as to equalize the pressures of the divided chimneys with the pressure equalization structure.

Abstract: A decay heat removal system for a liquid metal reactor in which a decay heat exchanger (DHX) is installed concentrically with an intermediate heat exchanger (IHX) in the same cylinder which separates the DHX and IHX from the reactor pool fluid, and serves to remove the reactor core decay heat. The cylinder surrounds the IHX and DHX, and has an open top portion protruding out of the level of the fluid in a hot pool, a bottom portion connected to a cold pool and a guide pipe for allowing the passage of the fluid from the hot pool into the IHX. The decay heat removal system can remove decay heat immediately after occurrence of an accident, thereby improving the safety of a nuclear plant.

Abstract: A direct pool cooling type passive safety grade decay heat removal method and system for removing core decay heat in a pool type liquid metal reactor when a normal heat removal system breaks down. In the liquid metal reactor comprising a reactor vessel, the interior of which is partitioned into a hot pool above a core and a cold pool around the core so that liquid level difference between the hot pool and the cold pool is maintained by a primary pumping head under normal steady-state conditions, is disposed at least one circular vertical tube in such a manner that the sodium in the circular vertical tube is maintained with the same liquid level as the liquid level of the sodium in the cold pool.