Abstract: A method for safeguarding discharge of residual heat from a nuclear power station reactor upon a lowered filling level in a primary circuit of a reactor cooling system, includes initially shutting down the reactor and running through an initial cooling and pressure reduction phase in the primary circuit. Then an aftercooling system is cut in for taking over heat discharge from the primary circuit, when heat discharge is no longer guaranteed by a steam generator plant. Then complete pressure relief and a lowering of the filling level in the cooling system to a mid-loop level of a main coolant conduit take place. A coolant reservoir is present for a required refilling of the primary circuit and aftercooling system.

Abstract: Thermal sleeve assemblies for connecting a core spray line to a reactor safe end without welding. In one embodiment the thermal sleeve assembly includes a t-box junction, a thermal sleeve and a finger assembly. The t-box junction is attached core spray lines and the thermal sleeve. The finger assembly is coupled to the thermal sleeve and includes several fingers. The finger assembly includes a ring which is coupled to the thermal sleeve so that an opening in the ring is aligned with a bore extending through the thermal sleeve. The fingers are substantially L shaped and are attached to the ring so that when the ring is welded to the thermal sleeve second end the fingers extend from the thermal sleeve.

Abstract: Coupling apparatus for replacing a core spray line downcomer pipe coupled to a shroud T-box are described. In one embodiment, the coupling apparatus includes a seal ring, a mating flange, a housing having at least one wedge pocket, at least one coupling bolt, at least one wedge and at least one lateral pin. After extending the downcomer pipe into the housing, the seal ring is inserted into the opposite end of the housing adjacent the downcomer pipe. The seal ring is then seated on the mating flange seat. The two seats allow the downcomer pipe to be rotational misaligned with the coupling apparatus. The coupling bolts extend through the mating flange and the housing to rigidly secure the downcomer pipe to the coupling apparatus. Lateral pins extend through the housing and the downcomer pipe to provide vertical and torsional load transfer from the downcomer pipe to the coupling apparatus.

Abstract: A depressurization system (1) for pressurized steam operated plant employing injection of cold water contained in a superelevated tank (5), said injection being triggered rapidly and in a manner independent of the magnitude of the damage and of the presence of incondensible gases, by means of a natural circulation of steam in a closed loop of pipes (19, 20, 21, 22) around said plant (2, 3, 4), caused by the condensation of steam in a condenser (10), placed on said pipes, during the occurence of an accident, comprises a first siphon-type hydraulic shutoff (32), on said pipe loop (19, 20, 21, 22) and arranged close to the inlet collector (14) of said condenser (10), a second siphon-type hydraulic shutoff (29), on the cold water delivery pipe (26) and placed close to the pressurized steam operated plant (2, 3, 4), said second siphon-type hydraulic shutoff (29) being below said first siphon-type hydraulic shutoff (32).

Abstract: A nuclear reactor includes a propagation space for core melt. The propagation space has a coolant conduit leading to a coolant reservoir and a device which opens in a temperature-dependent manner. The coolant conduit in the propagation space is a spray conduit having a spraying area which covers the cross-section of the propagation space over a large area. The device is controlled in such a way that it opens when the core melt enters the propagation space. Spraying gives rise to a crust on the core melt which reduces heat radiation. At the same time, the propagation space fills with a steam atmosphere which drastically reduces the thermal load on building structures.

Abstract: Pipe connector assembly for replacing a core spray line in a nuclear reactor without field cutting, measuring, or welding such line. In one embodiment, the pipe connector assembly includes a first coupling member, a second coupling member, and at least one locking element. The first coupling member includes a flange, a pipe engaging portion, a spherical convex seat portion, a bore and a stud bore. The second coupling member includes a flange having a spherical concave seat portion for receiving the convex seat portion of the first coupling member, a pipe engaging portion, a bore, and a stud bore. The locking element includes at least one spherical washer and a crimp mechanism and couples the first coupling member and the second coupling member by extending through the flange stud bores.

Abstract: Core spray line riser repair apparatus and methods for axially restraining a reactor core spray line riser to a T-box are described. In one embodiment, the repair apparatus includes a sleeve, a threaded draw bolt extending through the axial bore, and a threaded block. The sleeve includes a substantially cylindrical main body having an axial bore extending therethrough and a flange at one end of the main body. The sleeve is configured to be inserted into the T-box until the flange abuts against the T-box. The draw bolt is configured to extend through the sleeve flange, the sleeve bore, and an opening in the core spray line riser. The draw bolt engages the block to draw the block in tight engagement with the core spray line riser.

Abstract: Breaker valve assemblies for a simplified boiling water nuclear reactor are described. The breaker valve assembly, in one form, includes a valve body and a breaker valve. The valve body includes an interior chamber, and an inlet passage extends from the chamber and through an inlet opening to facilitate transporting particles from outside of the valve body to the interior chamber. The breaker valve is positioned in the chamber and is configured to substantially seal the inlet opening. Particularly, the breaker valve includes a disk which is sized to cover the inlet opening. The disk is movably coupled to the valve body and is configured to move substantially concentrically with respect to the valve opening between a first position, where the disk completely covers the inlet opening, and a second position, where the disk does not completely cover the inlet opening.

Abstract: Systems, methods, and apparatus for preventing steam leakage between a drywell and a wetwell in a nuclear reactor are described. In accordance with one embodiment of the present invention, the vacuum breaker of the nuclear reactor is coupled to a vacuum breaker condensing system which includes a condenser and a steam inlet pipe. The steam inlet pipe is substantially hollow and includes a first end, a second end, and a loop seal between the first and second ends. The first end of the pipe is positioned adjacent the drywell and the second end of the pipe is coupled to the vacuum breaker. The condenser is positioned proximate the steam inlet pipe and includes an inlet, an outlet, and a plurality of condenser tubes. The condenser inlet and condenser outlet are each coupled to a pool of water, e.g., the Gravity Driven Cooling System pool, and configured to draw water from the pool of water and through the condenser tubes to substantially condense steam flowing through the steam inlet pipe.

Abstract: A passive safety system for a nuclear reactor coolant system including a water storage tank, a heat exchanger positioned within the water storage tank and connected to the hot leg, and a core make-up tank having a tank inlet connected to the heat exchanger and a tank outlet connected to a selected location of the nuclear reactor coolant system. Upon the occurrence of an abnormal condition, water flows by natural circulation from the hot leg through the heat exchanger so that heat may be transferred to the water in the water storage tank, and thereafter flows through the core make-up tank and into a selected location of the nuclear reactor coolant system to provide cooling for the reactor core.

Abstract: A reactor cavity flooding system, which is used to immerse the hemispherical lower head of a nuclear reactor vessel by flooding the reactor cavity, is connected to both coolant injection nozzles located at the annulus gap between the lower head and the thermal insulator of a reactor and the discharge loops which are used to drain the hot water of the annulus gap into either the cavity floor or a liquid eductor. The subcooled water at a fire protection system can be directly injected into the annulus gap through twenty-five (25) nozzles at the lowest, middle, and top injection headers by a pump. The hot water heated at the lower head will be drained into either the cavity floor and/or the liquid eductor via two discharge loops that consist of both a suction header in the annulus gap at the equator level of the lower head and four (4) leakage collectors at the outside of four (4) shear keys of a reactor vessel. Drainage and recirculation of the hot water can be achieved in two ways.

Abstract: In the event of an incident in a pressurized water reactor with a safety feed and borating system, it is necessary that sufficient primary cooling water be available in the reactor cooling system or be resupplied, and it must also be possible to render the reactor subcritical with added boron and to maintain it in that state. The invention is a safety feed and borating system for a pressurized water reactor with series-connected safety feed and additional borating pumps. The additional borating pump is connected downstream of the safety feed pump and it has a parallel-connected bypass line with a check valve. Both pumps have a common minimum quantity line with different and reversible throttle restrictions. Thus the feed level and throughput of the entire system can be adapted optimally to existing demands. It is no longer necessary to provide a separate high-pressure borating system.

Abstract: A core spray line assembly for a nuclear reactor is described. In one embodiment, the core spray line assembly includes first and second core spray lines. Each of the core spray lines is substantially located within the reactor pressure vessel and has first and second ends connected to the shroud The first and second core spray lines include an adjustable core spray header and first and second articulating vertical pipe connector. The adjustable core spray header and articulating pipe connectors facilitate fast and easy replacement of existing core spray lines with the present core spray lines.

Abstract: A suction strainer includes a hollow internal core tube and an external filtering surface built around the internal core tube. A plurality of openings are defined through the side wall of the internal core tube core. In some cases the openings through the side wall are constructed and arranged such that there is somewhat less open area near the downstream end than the upstream end of the internal core tube, and the amount of open area tapers between the upstream end and the downstream end. As a result, when liquid is drawn into the internal core tube through the plurality of openings, a substantially uniform inflow distribution may be defined along substantially the entire length of the internal core tube. The internal core tube functions as a rigid structural support for the external filtering surface, enabling the apparatus to withstand post-LOCA hydrodynamic forces.

Abstract: A containment spray system for a light-water reactor includes a water trough being disposed in a safety tank. An immersion pump disposed in the vicinity of the bottom of the water trough, a spray branch and an outlet-side spray nozzle array, are connected to the water trough for injecting water into the containment in finely dispersed form in the event of an operational incident.

Abstract: A device for filtering water to at least one emergency cooling system in a nuclear power plant of the type comprising a reactor arranged in a containment which substantially consists of an upright, suitably cylindrical container whose bottom part forms a pool for collecting water formed by condensation of steam present in the containment, the condensation pool including a number of back-flushable containers filter water which is taken from the pool and, if required, is supplied to nozzles in the emergency cooling system in order to cool the reactor core in the event of an inadmissible temperature rise therein, each strainer having a shape of a housing with at least one, suitably cylindrical, apertured strainer wall through which the water can flow from the outside and into the housing, and being connected, by a first conduit passing through the container wall, to a suction pump disposed outside the container wall, as well as connected to a secondary conduit for supplying wash water to the interior of the hous

Abstract: A method and an apparatus for in situ ultrasonic inspection of the core spray T-box to thermal sleeve attachment weld and the core spray T-box to cover plate attachment weld in BWRs. The apparatus incorporates a stationary clamping mechanism and sliding and rotational mechanisms which are operated remotely to scan the transducer over the T-box welds and heat-affected zones thereof.

Abstract: A primary coolant system of a nuclear power plant for providing coolant to a reactor vessel, the primary coolant system comprises a primary loop for transferring heat away from the reactor vessel. An accumulator tank for containing water under a pressurized, gaseous atmosphere is attached to the primary loop via a coupling, which provides an outlet for the coolant from the accumulator tank to pass to the primary loop. A valve, which includes a pressure sensor that senses the pressure in the accumulator tank and opens or closes the coolant flow in the coupling in response to the sensed pressure, is attached to the coupling for sensing the pressure in the accumulator tank.

Abstract: A boiling water reactor having an optimum combination of active and passive safety systems. By combining three active divisions (I,II,III)of the boiling water reactor with a passive fourth division, the resulting design achieves improved plant reliability in addition to on-line maintenance of the emergency core-cooling systems. Included in the passive division is a new component, the reactor heat removal condenser (48), to be used in conjunction with pressure release valves (50) to provide backup depressurization of the reactor pressure vessel and backup heat removal and inventory control. The operating pressure of the heat removal condenser is maintained in the range of 100-200 psi.

Abstract: A nuclear reactor and emergency core cooling system. A nuclear reactor is provided with a cylinder around the core barrel that defines an annular channel therebetween. An injection nozzle is provided through the reactor vessel for delivery of emergency coolant to the defined channel. Emergency coolant is supplied during a LOCA to the injection nozzles sequentially from a high pressure tank, a low pressure tank, gravity feed tanks inside the reactor building, and from sumps that collect coolant in the reactor building. Check valves in the upper portion of the cylinder vent steam to the reactor inlet lines during a LOCA. Bores around the upper circumference of the cylinder break any siphoning action that might occur at the injection nozzle if there is a break in the emergency coolant lines from the emergency coolant sources.

Abstract: A passive cooling system for cooling an enclosure only when the enclosure temperature exceeds a maximum standby temperature comprises a passive heat transfer loop containing heat transfer fluid having a particular thermodynamic critical point temperature just above the maximum standby temperature. An upper portion of the heat transfer loop is insulated to prevent two phase operation below the maximum standby temperature.

Abstract: A nozzle for joining a pool of water to a nuclear reactor pressure vessel includes a tubular body having a proximal end joinable to the pressure vessel and a distal end joinable in flow communication with the pool. The body includes a flow passage therethrough having in serial flow communication a first port at the distal end, a throat spaced axially from the first port, a conical channel extending axially from the throat, and a second port at the proximal end which is joinable in flow communication with the pressure vessel. The inner diameter of the flow passage decreases from the first port to the throat and then increases along the conical channel to the second port. In this way, the conical channel acts as a diverging channel or diffuser in the forward flow direction from the first port to the second port for recovering pressure due to the flow restriction provided by the throat.

Abstract: A reactor cooling system for boiling water reactors comprises a pressure vessel containing a core of a boiling water reactor, a static core injection system including a first water source installed at a position higher than the pressure vessel and a first core injection line communicating the first water source with the pressure vessel, and having a capacity not less than 100% of the capacity necessary to maintain submergence of the core in the pressure vessel, and a plurality of dynamic core injection systems each including a second water source, a second core injection line communicating the second water source with the pressure vessel, and a pump provided in the second core injection line, and each having a capacity not less than 50 % of the capacity necessary to maintain submergence of the core in the pressure vessel.

Abstract: A passive cooling system for removing decay heat from an open cycle nuclear reactor. Coolant tanks are filled with coolant during normal operation of the reactor and coolant pump. A check valve in the inlet line for each tank prevents loss of coolant through the inlet line. After the reactor is shut down and the coolant pump is inoperative, coolant flows from the coolant tanks through exhaust lines into the normal coolant line and to the reactor for removal of decay heat. A flow control valve or fixed orifice in the exhaust line for each tank provides for a different predetermined flow rate of coolant from each tank to match the decay heat rate of the reactor.

Abstract: An emergency reactor coolant accumulator has a depressurizer to depressurize the accumulator at an appropriate timing, thereby preventing the flow of accumulator gas into the reactor system. If an accident occurs in the reactor system and the pressure of the reactor system decreases, the accumulator water (19) in the accumulator body (11), which is pressurized by the accumulator gas (18) is injected into the reactor system through the accumulator water outlet line (12) via the check valve (13) to cool the reactor core, and at the same time, the accumulator water (19) in the accumulator body (11) is introduced into the depressurizing vortex damper body (21) through the lower inlet (21c) of the damper (21) in the tangential direction to form a vortex. The increase in resistance due to the vortex reduces the amount of water discharged from the accumulator body (11) to the gas release line (22) via the depressurizing vortex damper (21).

Abstract: A nuclear reactor has a passive system for adjusting the pH of post accident water in the containment vessel. A basic liquid is stored in the containment vessel at an elevation above the maximum post accident water level. When radiation levels in the containment vessel exceed a predetermined, normal level the basic liquid is gravitationally drained into sumps located in the containment vessel below the maximum post accident water level where it mixes with emergency core cooling system water, raising the pH of the water to about 7.

Abstract: A pressurized-water nuclear reactor with inherent safety comprises a pressurized vessel filled with borated water within which is the body of the reactor. The latter includes an upper part and a lower part within which is the reactor core. The upper part includes a first tubular cavity, a second tubular cavity coaxial with and outside the first cavity and a plurality of helical tube bundles extending between respective pairs of connectors for the inlet and outlet of water circulating in the tube bundles.

Abstract: A pressurized water nuclear reactor uses its residual heat removal system to make up water in the reactor coolant circuit from an in-containment refueling water supply during staged depressurization leading up to passive emergency cooling by gravity feed from the refueling water storage tank, and flooding of the containment building. When depressurization commences due to inadvertence or a manageable leak, the residual heat removal system is activated manually and prevents flooding of the containment when such action is not necessary. Operation of the passive cooling system is not impaired. A high pressure makeup water storage tank is coupled to the reactor coolant circuit, holding makeup coolant at the operational pressure of the reactor. The staged depressurization system vents the coolant circuit to the containment, thus reducing the supply of makeup coolant. The level of makeup coolant can be sensed to trigger opening of successive depressurization conduits.

Abstract: A water storage tank in the coolant water loop of a nuclear reactor contains a tubular heat exchanger. The heat exchanger has tubesheets mounted to the tank connections so that the tubesheets and tubes may be readily inspected and repaired. Preferably, the tubes extend from the tubesheets on a square pitch and then on a rectangular pitch therebetween. Also, the heat exchanger is supported by a frame so that the tank wall is not required to support all of its weight.

Abstract: If an emergency arises in gas-cooled nuclear reactor plants having a heat exchanger for removing afterheat due to failure of a blower, the afterheat can be only inadequately removed because of the many deflections and restrictions in a primary circulation loop. In order to achieve adequate removal of afterheat solely on the basis of natural draught, a heat exchanger is located above a top reflector and reaches across a part of coolant gas bores in the top reflector. During normal operation of the nuclear reactor plant, there is a flow of cold gas through the heat exchanger in the direction toward the reactor core and in the event of an emergency, there is a flow of hot gas in a direction out of the center of the core of the reactor. A natural draught coolant circulation is established with the return of the cooled gas through the coolant gas bores in the top reflector.

Abstract: Part length water regions are located above part length fuel rods in boiling water nuclear reactor fuel bundles. The part length water regions include discrete containers having entry ports at the top of the part length water regions for capturing water, and vent ports for permitting internally generated steam to escape. The advantages of improved neutron moderation in the upper portion of the fuel assembly are maintained while the uranium fuel removal requirements are minimized.

Abstract: A fuel bundle for a boiling water nuclear reactor having an improved water rod is disclosed, this water rod having two discrete compartments upper and lower for containing water. The bottom compartment flows moderator from the bottom of the fuel bundle through the water rod compartment to discharge points located through the water rod side walls between the upper most spacers; the top compartment opens upwardly and is naturally filled with liquid moderator settling out of the upwardly flowing moderator during reactor operation. There results the requisite presence of liquid moderator within the water rod for supplying the upper two phase region of the fuel rod with nearly full moderator density. At the same time, water flow through of the water rod from the bottom of the fuel bundle to the upper two phase region of the fuel bundle improves the thermal hydraulic performance.

Abstract: Disclosed is liquid filling apparatus for a high-temperature and high-pressure vessel. The apparatus comprises a high-temperature and high-pressure vessel, a closed liquid storage tank disposed at a level higher than that at which liquid is supplied to the high-temperature and high-pressure vessel, a liquid-filling flow passage for supplying liquid from the closed liquid storage tank into the high-temperature and high-pressure vessel, a pressure-feed flow passage for supplying a pressure from the high-temperature and high-pressure vessel to the closed liquid storage tank, valves equipped on the liquid-filling flow passage and the pressure-feed flow passage respectively, and a liquid-filling liquid source adapted to communicate with the interior of the closed liquid storage tank via a valve, whereby the environmental surroundings of the closed liquid storage tank are lower in temperature than the interior of the high-temperature and high-pressure vessel.

Abstract: A nuclear reactor system including a main heat transport path around which a first coolant is pumped by main circulation pumps to transport heat from the reactor core to a steam generator. A heat exchanger is located in the main heat transport path after the outlet from the steam generator, the secondary side of that heat exchanger being in a decay heat removal loop which contains a second liquid coolant. A vapor separator in the decay heat removal loop is connected to an outlet of the heat exchanger with the vapor separator's outlet being connected to an inlet of a further heat exchanger located in a large tank of water which forms a heat sink. The further heat exchanger's outlet is connected to the heat exchanger's inlet forming a closed loop. The further heat exchanger is located at a higher elevation than the heat exchanger whereby a natural convection flow can occur in the decay heat removal path.

Abstract: A conventional low pressure coolant injection system for boiling water reactors is provided. With the modification, the cross tie conduits and associated valves remain open between two LPCI divisions. On the occasion of an LOCA, the LPCI pumps are activated and injection valves for each of the LPCI divisions are opened to commence coolant injection in the recirculation loops in simultaneous fashion. However, the rate of flow of water coolant within each injection system is controlled by a hydraulic resistance, which is selected to achieve reactor core cooling within requisite time and in requisite quantities from one injection path. Thus, even though coolant water may flow through a rupture within one recirculation loops, sufficient water will be injected in the other loop to achieve core cooling.

Abstract: A passive safety injection system relies on differences in water density to induce natural circulatory flow patterns which help maintain prescribed concentrations of boric acid in borated water, and prevents boron from accumulating in the reactor vessel and possibly preventing heat transfer.

Abstract: A boiling water nuclear reactor plant is provided with a standby supply of auxiliary coolant water for use in the event of a loss of coolant mishap to provide supplementary coolant water for cooling the fuel core. The supply of standby auxiliary coolant water is maintained within the reactor pressure vessel and is administered by inherently passive means.

Abstract: A reactor core isolation cooling system includes a reactor pressure vessel containing a reactor core, a drywell vessel, a containment vessel, and an isolation pool containing an isolation condenser. A turbine is operatively joined to the pressure vessel outlet steamline and powers a pump operatively joined to the pressure vessel feedwater line. In operation, steam from the pressure vessel powers the turbine which in turn powers the pump to pump makeup water from a pool to the feedwater line into the pressure vessel for maintaining water level over the reactor core. Steam discharged from the turbine is channeled to the isolation condenser and is condensed therein. The resulting heat is discharged into the isolation pool and vented to the atmosphere outside the containment vessel for removing heat therefrom.

Abstract: A nuclear fission reactor combined with a propellant actuated depressurization and/or water injection valve is disclosed. The depressurization valve releases pressure from a water cooled, steam producing nuclear reactor when required to insure the safety of the reactor. Depressurization of the reactor pressure vessel enables gravity feeding of supplementary coolant water through the water injection valve to the reactor pressure vessel to prevent damage to the fuel core.

Abstract: The present invention is directed to a boiling water reactor wherein housed within the reactor pressure vessel is the nuclear core and an upper steam dome connected to a steam outlet in the RPV. The improvement comprises a vessel disposed in the steam dome and containing a neutron poison effective for inactivating the core. This vessel is vented to the steam dome for pressurizng the poison contained therein. The vessel also is connected by a line terminating beneath the core. The line contains an actuatable valve to release the poison through the line upon its actuation. The poison, when released, flows through the line by gravity to beneath the core for mixing with the reactor coolant which passes through the core resulting in consequent inactivation thereof.

Abstract: In order to supply emergency coolant directly to the core inlet of a nuclear reactor, a separate and distinct channel is located within the reactor vessel. This channel flows downward along the perimeter of the core barrel and discharges its emergency coolant directly to the core inlet. Separate nozzles couple this channel to the supply of emergency coolant.

Abstract: A method and system for controlling nuclear reactivity in a nuclear reactor are disclosed. The method includes maintaining a nuclear position solution at an initial poison pressure less than the steam pressure within the reactor vessel. The method further includes channeling a pressurizing fluid into the holding tank for pressurizing the poison solution to a pressure greater than the initial pressure thereof, and draining by gravity the poison solution from the holding tank and into the reactor vessel for mixing with the water to reduce reactivity in the core.

Abstract: Disclosed is a liquid filling apparatus for high-temperature and high-pressure vessel. The apparatus comprises a high-temperature and high-pressure vessel, a closed liquid storage tank disposed at a level higher than that at which liquid is filled into the high-temperature and high-pressure vessel, a liquid-filling flow passage for supplying liquid from the closed liquid storage tank into the high-temperature and high-pressure vessel, a pressure-feed flow passage for supplying pressure from the high-temperature and high-pressure vessel to the closed liquid storage tank, valves equipped on the liquid-filling flow passage and the pressure-feed flow passage respectively, and a liquid-filling liquid source adapted to communicate with the interior of the closed liquid storage tank via a valve, whereby the environmental surroundings of the closed liquid storage tank are lower in temperature than the interior of the high-temperature and high-pressure vessel.

Abstract: A boiling water nuclear water plant includes a reactor core isolation cooling (RCIC) system in which a turbine used to pump feedwater to the reactor also drives a generator. The generator is used to drive RCIC components, such as a room cooler and control electronics, during station blackout.

Abstract: An intrinsic-safety nuclear reactor of the pressurized water type, having:a reactor vessel (2) equipped with a core (4), a lower header (5) and an upper header (6), at least one heat exchanger (3) with a secondary fluid, means of hydraulic connection (9, 10) between said headers and said heat exchanger and at least one circulation pump (11),a pressurized container (1) surrounding the reactor vessel (2) and which defines a tank (15) full of a cold, neutron-absorbing liquid;pipes (20) allowing communication between the lower area of said tank and the lower header of the vessel, as well as pipes (21) allowing communication between the upper area of said tank and the upper header,in which the pressure drop in the primary fluid across the core is substantially equal to the difference in head between the cold column of said tank and the hot column of the vessel.The pressurized container (1) is immersed in a pool (18) containing a neutron-absorbing liquid at atmospheric pressure.

Abstract: A water cooled nuclear reactor comprises a reactor core, a primary water coolant circuit and a pressurizer arranged as an integral unit in a pressure vessel. A passive full pressure emergency core cooling and residual heat removal system is provided which comprises a tank having a reserve supply of water positioned above the primary water coolant circuit or the reactor core. The tank is interconnected to the primary water coolant circuit by a first pipe and a second pipe. The first pipe has an inverted U-bend which passes through a water space and a steam space of the pressurizer to form a vapor lock. The first pipe and second pipe are also provided with hydrostatic thermal seals. The tank has one or more residual heat removal circuits comprising a heat exchanger positioned in the tank and a heat exchanger outside the tank. Movement of the vapor lock from the inverted U-bend allows cool water from the tank to flow into the primary water coolant circuit and hot water to flow into the tank to be cooled.

Abstract: The present invention is directed to a nuclear reactor facility wherein a nuclear reactor pressure vessel (RPV) is housed within an annular sealed drywell, an annular sealed wetwell houses said drywell, a pressure suppression pool of liquid is disposed in said wetwell and is connected to said drywell by submerged vents, a condenser line connects said drywell to an isolation condenser, and a bleedline from said isolation condenser is connected to said pool and terminates under the surface of said pool. The improvement of the present invention comprises a liquid reservoir disposed in said drywell and a standpipe disposed in said wetwell. The reservoir and the standpipe are connected by a duct which is located below the surface of said reservoir a distance, D. The area of the reservoir is at least 25 times larger than the area of said standpipe.

Abstract: The invention is directed to a natural circulation reactor having a reactor pressure vessel with a core housed therein, the core being disposed in such a location that a top portion of the core is submerged under coolant even in the event that any pipe connected to the reactor pressure vessel is broken and then a coolant level in the reactor pressure vessel is lowered due to flushing. This permits the reactor core to be submerged under coolant even in the event of breakage of any pipe connected to the reactor pressure vessel, ensuring to eliminate a possibility that the top portion of the reactor core is exposed temporarily during an intermediate period before actuation of an accumulated coolant injection system to start injecting of the coolant into the reactor pressure vessel after the end of flushing.

Abstract: A multiple liquid standby safety injection system for nuclear fission reactor plants comprising means for injecting supplemental coolant water into the nuclear reactor pressure vessel to cool the fuel core and means for injecting a water solution of a neutron absorbing compound into the nuclear reactor pressure vessel about the fuel core to diminish the fission reaction. The coolant water and solution of neutron absorbent each comprise individual systems and are conveyed from their respective supply container by means of pressurized propelling gas. The individual standby safety injection systems for coolant water and solution are integrated with means for transferring propelling gas from one supply container to the other to enhance the source and available volume of liquid propelling gas for either system by drawing from the other.

Abstract: A passive decay-heat removal system for a water-cooled nuclear reactor employs a closed heat transfer loop having heat-exchanging coils inside an open-topped, insulated box located inside the reactor vessel, below its normal water level, in communication with a condenser located outside of containment and exposed to the atmosphere. The heat transfer loop is located such that the evaporator is in a position where, when the water level drops in the reactor, it will become exposed to steam. Vapor produced in the evaporator passes upward to the condenser above the normal water level. In operation, condensation in the condenser removes heat from the system, and the condensed liquid is returned to the evaporator. The system is disposed such that during normal reactor operations where the water level is at its usual position, very little heat will be removed from the system, but during emergency, low water level conditions, substantial amounts of decay heat will be removed.