Abstract: An underwater decommissioning method of a nuclear facility including a nuclear reactor pressure vessel and bio-protective concrete comprising a cavity in which the nuclear reactor pressure vessel is positioned is disclosed. The method includes: (a) lifting the nuclear reactor pressure vessel above the cavity; (b) forming an insertion part in the bio-protective concrete adjacent to the cavity, filling the insertion part with water, and installing a support part on a bottom surface of the insertion part; (c) inserting the nuclear reactor pressure vessel in the insertion part and mounting a lower portion of the nuclear reactor pressure vessel on the support part; and (d) repeatedly cutting portions of the nuclear reactor pressure vessel mounted on the support part by using a cutting device in an underwater position. The method allows performing cutting operations in the water, and thus, it is possible to prevent radiation exposure due to occurrence of dust.

Abstract: An apparatus for removing irradiated capsules containing produced Co-60 from a plurality of burnable absorber rodlets. The apparatus comprises a solenoid that induces an electromagnetic flux into a Co-60 capsule and magnetically locks the Co-60 capsule in parallel with the apparatus. The apparatus is slideable along a longitudinal axis of the burnable absorber rodlet and causes the Co-60 capsule to overcome holding forces exerted on it.

Abstract: A combined blade guide and exchange tool, include a blade guide tool having a lower end and an upper end and a plurality of frame rails supporting a pair of lower collet housings at a lower end of the blade guide tool. A pair of fuel support grapple actuating rods are supported between the plurality of frame rails and have a first end engaging a pair of collets within the pair of lower collet housings and a second end disposed at the upper end of the blade guide tool. A blade exchange tool is releasably mounted to the upper end of the blade guide tool and includes a pair of upper collets for engaging the pair of fuel support grapple actuating rods. The blade exchange tool further including a slider and hook assembly attached to a cable guided by the blade exchange tool and adapted for engaging a control rod.

Abstract: A device for removing shielding balls from calandria of a heavy water reactor is provided. The device includes a head for moving the shielding balls positioned inside of an end shield of the calandria to an outside of the end shield; and a mover for moving the head to the end shield of the calandria. The head includes a head body, an opening former installed on the head body and configured to form an opening in the end shield, and a gate installed on the head body and configured to control an amount of the shielding balls discharged to the outside through the opening.

Abstract: Disclosed herein is a machine for cutting nozzles of reactor vessels. The machine for cutting nozzles of reactor vessels comprises a cutting unit positioned at an upper surface edge of a reactor vessel having a nozzle and having a saw blade part having different contact areas to cut the nozzle, a drive unit providing the saw blade part with rotary power, and a foreign substance suction unit provided at one end of the cutting unit in contiguity with the saw blade part to suck foreign substances generated when the nozzle is cut by the saw blade part, wherein the foreign substance suction unit sucks the foreign substances by approaching an outer peripheral surface of the nozzle when the saw blade part moves in a cutting direction of the nozzle.

Abstract: A combined blade guide and exchange tool, include a blade guide tool having a lower end and an upper end and a plurality of frame rails supporting a pair of lower collet housings at a lower end of the blade guide tool. A pair of fuel support grapple actuating rods are supported between the plurality of frame rails and have a first end engaging a pair of collets within the pair of lower collet housings and a second end disposed at the upper end of the blade guide tool. A blade exchange tool is releasably mounted to the upper end of the blade guide tool and includes a pair of upper collets for engaging the pair of fuel support grapple actuating rods. The blade exchange tool further including a slider and hook assembly attached to a cable guided by the blade exchange tool and adapted for engaging a control rod.

Abstract: A nuclear reactor decommissioning system according to an embodiment includes a cutting device to cut a reactor, a lifting device inserted inside the reactor to lift the reactor, and a shielding device that is positioned between the reactor and the lifting device and blocks radioactive dust generated by the cutting device from spreading.

Abstract: Methods of installing an external dashpot tube around a control rod guide tube in a nuclear reactor fuel assembly are disclosed herein. The nuclear reactor fuel assembly may include a top nozzle, a bottom nozzle, and a plurality of grids. The various methods may comprise inserting a guide tube into a skeleton of the nuclear reactor fuel assembly to a lower middle grid, the lower middle grid being second closest grid to the bottom nozzle of the plurality of grids. The various methods may also include installing an external dashpot tube over the guide tube after it has been inserted to the lower middle grid; inserting the guide tube with the installed external dashpot tube to the bottom nozzle; attaching the guide tube to the skeleton; and bulging the guide tube onto the external dashpot tube.

Abstract: A system and method for printing an image on a surface using a printing robot, wherein data from an internal position determination system of the robot as well as data from a reference system comprising a stationary reference external to the robot are used to calculate an estimate of position, velocity and acceleration of the print head relative to the surface. As print head is moved along the surface during printing, i.e. as the print head is moved while ink is ejected from nozzles of the print head, the positioning of the print head and activation of nozzles of the print head are controlled based on the estimate.

Abstract: A radioactive source removing and introducing tooling includes a first support frame, a shield door disposed on the first support frame, a shield cover located on the shield door, and a first pull rod device. The shield door includes a movable first shield block. The shield cover is able to be separated from the shield door, and the shield cover includes one opening and one accommodation space. The first pull rod device includes a pull rod and a first connection portion disposed on the pull rod, and the pull rod is able to extend into the shield cover and drive the first connection portion to move inside the accommodation space of the shield cover.

Abstract: A nuclear fission reactor, flow control assembly, methods therefor and a flow control assembly system. The flow control assembly is coupled to a nuclear fission module capable of producing a traveling burn wave at a location relative to the nuclear fission module. The flow control assembly controls flow of a fluid in response to the location relative to the nuclear fission module. The flow control assembly comprises a flow regulator subassembly configured to be operated according to an operating parameter associated with the nuclear fission module. In addition, the flow regulator subassembly is reconfigurable according to a predetermined input to the flow regulator subassembly. Moreover, the flow control assembly comprises a carriage subassembly coupled to the flow regulator subassembly for adjusting the flow regulator subassembly to vary fluid flow into the nuclear fission module.

Abstract: Slip joint clamps seat on a diffuser end via external features of the diffuser, like guide ears, regardless of slip joint wear or damage. The clamps can be opened and closed to surround an inlet mixer forming a slip joint with the diffuser without disassembly. Slip joint clamps drive or bias the inlet mixer in a lateral direction largely perpendicular to the axial orientation and end of the diffuser to achieve a desired preload force in the inlet mixer and clamp connection. Clamp arms include rotatable halves that, when joined, form a complete fill between an inner surface of the diffuser and outer surface of the inlet mixer. A lateral drive pushes the inlet mixer against the clamp and may include a resistive element. An accessible set of guide ear bolts and lateral driving bolts permit exterior manipulation to axially mount or laterally bias the clamp in the slip joint.

Abstract: Seals are positioned between abutting nuclear reactor components. Example seals are held in position by gravity, grooves, retainers, direct joining, or other mating structures to seal the abutting components. Compression of example seals drives the seals against the joining components, preventing fluid passage therebetween. Example seals may include a cavity opening to a higher pressure fluid outside the joined components to drive expansion or sealing of the seal. Seals may have a C-shaped, E-shaped, O-ring, coiled, helical, or other cross-section to provide such a cavity. Example seals may be flexible materials compatible with radiation and heat encountered in a nuclear reactor. Seals may be continuous or sectional about the abutment of the components. An annular seal may extend continuously around a perimeter of removably joined core plates, supports, shrouds, and/or chimney heads and structures. Seals can be installed between and in the components at any time access is available to the components.

Abstract: A nuclear reactor seismic isolation assembly includes an enclosure that defines a volume; a plastically-deformable member mounted, at least in part, within the volume; and a stretching member moveable within the enclosure to plastically-deform the plastically-deformable member in response to a dynamic force exerted on the enclosure.

Abstract: A method for preparing to reload a fast nuclear reactor with heavy liquid metal coolant includes extracting a reactor plug and extracting a removable reactor block. The method includes installing handling equipment to form an unloading path under radiation safety conditions. The reactor plug is extracted from the reactor monoblock housing and transported to a plug shaft. The removable reactor block is extracted from the reactor monoblock housing and transported to a block shaft for later disassembly.

Abstract: A control rod drive replacement device includes a channel for mounting on a support under a nuclear reactor pressure vessel and a control rod drive extractor removably received in the channel. The control rod drive extractor includes a base and a housing pivotably connected to the base. The housing is configured for receiving a control rod drive. The base includes a base axis. The housing is pivotably attached to the base at the base axis for pivoting between a horizontal orientation in which the housing is aligned within the channel and a vertical orientation in which the housing is aligned for receiving the control rod drive from the nuclear reactor pressure vessel. The housing is vertically movable with respect to the base in the vertical orientation.

Abstract: An automated high speed under vessel work platform with three automated axes comprising a 360° rotational horizontal axis, a linear horizontal axis via a traversing trolley, and a linear vertical axis via swappable task robots, which can also add fourth and fifth axes capabilities. The automated high speed under vessel work platform has the ability to drive to a specific location by typing the core location into the control software. The work platform can be operated manually via a hand wheel, or locally via a handheld pendant or from the control room. The work platform also has a camera for inspections and verification of the work.

Abstract: A lifting fixture for removing the upper internals from a nuclear reactor to provide access to the core during a refueling that does not require flooding of a refueling canal. A shield plate is integral to a lifting rig used to remove the upper internals. The shield plate is sized to be supported on the reactor vessel upper flange and to cover the reactor vessel opening with the closure head removed. The shield plate has openings that are in-line with the control rod assembly drive rod travel housings. Control rod assembly drive rods can be accessed through the openings. The lifting rig allows personnel to decouple the drive rods from the rod cluster control assemblies. The lifting fixture enables the decoupled drive rods to be lifted from the core with the upper internals, while shielding maintenance personnel without flooding the area above the reactor.

Abstract: A control rod guide frame has a central passage of constant cross-section as a function of position along a central axis that passes through the central passage. The central passage is sized and shaped to guide a traveling assembly including at least one control rod as it moves along the central axis. The control rod guide frame comprises at least two radial guide frame sections secured around and defining the central passage. Each radial guide frame section may comprise an extruded radial guide frame section, which may be made of extruded steel. The central passage may include control rod guidance channels parallel the central axis and machined into the extruded radial guide frame sections. The at least two radial guide frame sections may be interchangeable. In some embodiments the at least two radial guide frame sections consist of between four and eight radial guide frame sections.

Abstract: A system for disposing of one or more radioactive components from a nuclear reactor may include a first receptacle configured to receive the one or more radioactive components, a frame configured to support the first receptacle in the nuclear reactor, and a device configured to separate the one or more radioactive components into two or more portions during lowering of the one or more radioactive components into the first receptacle. A method for disposing of one or more radioactive components from a nuclear reactor may include assembling a system for disposing of the one or more radioactive components, and moving the assembled system to an area of a reactor core. A method for disposing of one or more radioactive components from a nuclear reactor may include assembling a system for disposing of the one or more radioactive components in an area of a reactor core.

Abstract: A pressurized water nuclear reactor (PWNR) includes a core having a containment shield surrounding a reactor vessel having fuel assemblies that contain fuel rods filled with fuel pellets, and control rods, and a steam generator thermally coupled to the reactor vessel. A flow loop includes the steam generator, a turbine, and a condenser, and a pump for circulating a water-based heat transfer fluid in the loop. The heat transfer fluid includes a plurality of nanoparticles having at least one carbon allotrope or related carbon material dispersed therein, such as diamond nanoparticles.

Abstract: A method of refueling a nuclear reactor that includes the steps of removing the reactor vessel head and upper internals to a storage location and installing a cylindrical tank having open upper and lower ends, on the reactor vessel flange. The cylindrical tank is sealed to the reactor vessel and a penetration on the side of the cylindrical tank is sealed to a refueling canal that is connected to a spent fuel pool. The level of reactor coolant within the reactor vessel is then raised to at least partially fill the cylindrical tank to a level equal to that of the spent fuel pool. The refueling canal is then opened and a refueling machine supported on the reactor vessel is employed to transfer fuel assemblies between the core and the spent fuel pool.

Abstract: Disclosed is a disaster warning device with a guided surface wave receive structure, an impedance matching network, a power circuit, a data processing circuit, and a warning output. The power circuit and the data processing circuit may be coupled to the guided surface wave receive structure. The power circuit may supply electrical energy to power to the data processing circuit and warning output. The power circuit may receive power from a guided surface wave. The data processing circuitry may receive data communications from a guided surface wave.

Abstract: An apparatus for reinforcing a jet pump riser includes: an elbow upper clamp for covering a riser elbow coupled to a thermal sleeve from an upper side thereof; an elbow lower clamping member for clamping the riser elbow from a lower side thereof; an elbow vertical portion clamping member for covering a vertical portion of the riser elbow; and an elbow horizontal portion clamping member for covering a horizontal portion of the riser elbow. These members are disposed in different orientations with respect to the elbow upper clamp so as to fix the thermal sleeve, the riser elbow and the riser pipe.

Abstract: A nuclear component transfer device that incorporates a shielded canister into the mast design of a conventional nuclear refueling machine. A moveable mast telescopes within a stationary mast which is attached to a bridge for lateral positioning. The canister allows for the addition of shielding that is positioned with the movement of the moveable mast without additional motorized components to deploy the shielding during nuclear component movement. The nuclear component is drawn up into the shielded canister as the moveable mast lifts the nuclear component. The nuclear component is then placed into a transfer cart that is also fitted with a shielded canister. The transfer is made without exposing the nuclear components resulting in completely shield movement.

Abstract: A nuclear facility comprising an anchor device is provided. This anchor device comprises a female part and a male part. The female part includes a groove extending along a longitudinal axis. The groove has a width which decreases longitudinally and a transverse section. The male part includes a slider with a shape mating that of the groove and is able to be longitudinally inserted into the groove. The transverse section of the groove is configured so as to prevent the extraction of the slider out of the groove transversely to the longitudinal axis. The anchor device includes a locking device able to prevent the slider from longitudinally sliding out of the groove.

Abstract: A nuclear reactor can include a pressure vessel for containing a pressurized moderator at a first pressure. The nuclear reactor can also include a plurality of fuel channels for a coolant fluid at a second pressure. The plurality of fuel channels are fluidly connected at inlet ends thereof to a coolant supply conduit and are adapted to receive nuclear fuel bundles and to be mounted within the pressure vessel and surrounded by the moderator. The outlet ends of the fuel channels are fluidly connected to a coolant outlet conduit to enable the coolant fluid to circulate from the coolant supply conduit through the fuel channels to the coolant outlet conduit. The plurality of fuel channels maintain separation between the coolant fluid circulating within the fuel channels and the moderator.

Abstract: A control room for a nuclear power plant including two or more nuclear reactor units includes a central workstation providing monitoring capability for both nuclear reactor units, a first operator at the controls (OATC) workstation in front of and to one side of the central workstation providing monitoring and control capabilities for the first nuclear reactor unit, a second OATC workstation in front of and to the other side of the central workstation providing monitoring and control capabilities for the second nuclear reactor unit, and a common control workstation directly in front of the central workstation providing monitoring and control capabilities for systems serving both the first nuclear reactor unit and the second nuclear reactor unit. The central and common control workstations do not provide control capabilities for either nuclear reactor unit. The common control workstation does not include any control capabilities that must be performed by a licensed operator.

Abstract: A semiconductor device includes a substrate, a first and second source/drain regions, and a gate stack. The first and second source/drain regions are disposed on the substrate. The gate stack is disposed over the substrate to overlay a channel region between the first and second S/D regions. The gate stack includes a gate dielectric layer disposed over the substrate; and a metal alloy disposed on the gate dielectric layer and configured as a filling layer in the gate stack; wherein the metal alloy has a first corrosion resistance corresponding to an etchant designed for removing a carbon-containing polymer.

Abstract: A control rod for a nuclear boiling water reactor is described. The control rod has a longitudinal centre axis and control rod blades, each control rod blade having a first and a second side and being substantially parallel to the longitudinal center axis. Each control rod blade comprises an absorber material which extends from a first absorber end to a second absorber end, the distance between the first absorber end and the second absorber end defining an active length. The control rod blades are provided with distance means on the first and second sides of the control rod blades, the distance means extending a distance of at least a third of the active length of the control rod blade.

Abstract: Apparatus for replacing a support pin for a control rod cluster guide tube. The support pin can fix the guide tube to a core plate. The apparatus can be used submerged in water. A movement device can hold and move the guide tube along a frame. A retrieval manipulator can remove an old support pin from the guide tube. A supply manipulator can provide a new support pin to the guide tube. A rotating means imparts rotation for loosening a nut from an old support pin, and for tightening a nut to a new support pin. A control device calculates variation in distance between the nut and the support pin on the basis of the rotation. The control device controls movement of the guide tube along the frame.

Abstract: This invention concerns robotic systems and is specifically concerned with an improved apparatus and method for remotely positioning a sensor, such as an ultrasonic probe, in limited access areas within a nuclear reactor. The apparatus includes a bottom frame and a top cover which is substantially aligned with and positioned above the bottom frame. A sensor is connected to the top cover and linear rails are connected to the bottom frame in a parallel relationship. There is a mechanism movably connected to the first and second linear rails in order to allow horizontal travel of the top cover. Further, there is at least one cable connected to the sensor and a power source, signal source or receiver.

Abstract: Apparatus and method for inspecting pipeline are provided. The pipeline inspecting apparatus moving along an external circumferential surface of a pipeline to inspect the pipeline, includes: a main frame having an arc shape having an opened portion to surround the pipeline; a main movement unit that is movably installed on the main frame, wherein the main movement unit is movably installed along a length direction of the pipeline while being in contact with the external circumferential surface of the pipeline; an auxiliary frame that has an arc shape having an opened portion to surround the pipeline and is separated from the main frame to face the main frame; an auxiliary frame adjusting unit that movably connects the auxiliary frame to the main movement unit in a circumferential direction of the pipeline; and a sensor adjusting unit that is fixed to the auxiliary frame, wherein a sensor for inspecting a state of the pipeline is installed.

Abstract: A device for the dry handling of nuclear fuel assemblies is provided. The device includes a transfer basket which can be connected to a lifter and which includes a gripper for gripping the fuel assembly to be transferred, the gripper being supported by a lift built into the basket; and an indexing table which can be placed on a cask and which comprises a positioner for positioning the basket over a slot in the cask.

Abstract: A system for storing high level radioactive waste. In one embodiment, the invention can be a system comprising an overpack body extending along a vertical axis and having a cavity for storing high level radioactive waste, the cavity having an open top end and a floor; an overpack lid positioned atop the overpack body to enclose the open top end of the cavity; an air inlet vent for introducing cool air into the cavity, the air inlet vent extending from an opening in an outer surface of the overpack body to an opening in the floor; and an air outlet vent in the overpack lid for removing warmed air from the cavity.

Abstract: In a movement control apparatus manipulation can be carried out while watching the movement of the moving body, without needing to watch one's hands, so even a novice operator can perform the manipulation easily, safely, reliably, and quickly. The apparatus can include a signal transmission cable, a casing of a manipulation remote controller disposed at one end of the cable, a rotary encoder that produces a signal corresponding to the direction of the casing, and a motor drive control circuit that is disposed on the other side of the cable and controls the movement of a moving body on the basis of a signal corresponding to the direction of the casing. The signal corresponding to the direction of the casing can be supplied from the rotary encoder, through the cable, to the motor drive control circuit.

Abstract: A shroud support of a BWR includes a shroud support cylinder, shroud support legs welded to a bottom of a reactor pressure vessel (RPV) and a shroud support cylinder, and an annular shroud support plate disposed between the RPV and the shroud support cylinder and welded to the RPV and the shroud support cylinder. A support apparatus is set a CRD housings installed to the bottom of the RPV. A rail guide member horizontally set to the support apparatus reaches directly below the shroud support plate through an opening between the shroud support legs. A bent rail is set on the rail guide member. The bent rail setting a repair device is pushed out along the rail guide member toward the RPV through the opening portion by the rail push-out apparatus set on the support apparatus. The bent rail is spread at directly below the shroud support plate.

Abstract: The present invention provides an apparatus for detecting and/or repositioning annulus spacers used to maintain the position of a pressure tube withm a calandria tube of a nuclear reactor. The method comprises the steps of: vibrationally isolating a section of the pressure tube; vibrating the wall of said pressure tube within said isolated section; detecting vibration of the wall at a minimum of two axial positions within said isolated sections; and detecting the reduction in vibration level of the wall at one or more of said axial positions in comparison to the remaining axial positions. The apparatus comprises a tool head to be inserted into the pressure tube, the tool head comprising a first end and a second and a clamping block m each of said ends. The clamping blocks are used to vibrationally isolate a section of the pressure tube located between said ends.

Abstract: A method for removing and replacing a bottom-mounted instrumentation nozzle on a nuclear reactor pressure vessel. The method (i) caps or plugs the existing bottom-mounted instrumentation nozzle; (ii) cuts the nozzle at or near the nozzle to in-core instrument tube weld; (iii) installs a water-tight sealing enclosure outside the vessel over the bottom of the bottom-mounted instrumentation nozzle creating a water-tight seal with the underside of the reactor vessel; (iv) cuts to sever the existing bottom nozzle from the reactor vessel; (v) extracts the existing nozzle; (vi) installs a replacement alloy 690 nozzle or plug from inside the vessel; and (vii) welds the replacement nozzle or plug in place. The replacement bottom-mounted instrumentation nozzle incorporates an integral shoulder that prevents ejection during operation and facilitates installation, and the entire method is performed while the reactor pressure vessel is filled with water.

Abstract: A CRDS unlatching tool includes a support assembly and a latching assembly, wherein the support assembly is received within the latching assembly in a manner wherein the latching assembly is moveable relative to the support assembly. The support assembly has a plurality of latch fingers and at least one pin, each of the latch fingers being movable between a latched position wherein the latch finger is structured to engage and hold the CRDS an unlatched position wherein the latch finger is structured to not engage the CRDS. The latching assembly includes a first sleeve member and a second sleeve member, the second sleeve member having at least one slot, wherein the at least one pin is moveably received within the at least one slot. The latching assembly is movable from a latched state to an unlatched state wherein the latch fingers are actuated by the first sleeve member.

Abstract: Illustrative embodiments provide systems, methods, apparatuses, and applications related to annealing nuclear fission reactor materials.

Abstract: The present invention provides a system and method for reclaiming energy from the heat emanating from spent nuclear fuel contained within a canister-based dry storage system. The inventive system and method provides continuous passive cooling of the loaded canisters by utilizing the chimney-effect and reclaims the energy from the air that is heated by the canisters. The inventive system and method, in one embodiment, is particularly suited to store the canisters below-grade, thereby utilizing the natural radiation shielding properties of the sub-grade while still facilitating passive air cooling of the canisters. In another embodiment, the invention focuses on a special arrangement of the spent nuclear fuel within the canisters so that spent nuclear fuel that is hotter than that which is typically allowed to be withdrawn from the spent fuel pools can be used in a dry-storage environment, thereby increasing the amount energy that can be reclaimed.

Abstract: A lid frame for a nuclear fuel assembly shipping container and a shipping container for nuclear fuel assemblies are provided. The shipping container can include a lower container in which a cradle is installed, an upper container detachably coupled to the lower container, and a base frame coupled to the cradle with at least one nuclear fuel assembly placed thereon. The lid frame can include a plurality of supports installed apart from each other so as to surround the nuclear fuel assembly placed on the base frame, and a plurality of clamps separated from each other, coupled to the plurality of supports perpendicular to the plurality of supports, rotatably hinged to the base frame, and configured to clamp the nuclear fuel assembly. The lid frame safely protects the nuclear fuel assembly that is being transported.

Abstract: A control rod/fuel support handling apparatus that is used in the case where a control rod and a fuel support are held, removed and lifted in a reactor and then are transported into the reactor in a periodical inspection of a BWR and in the case where the control rod and the fuel support are attached and mounted again into the reactor, the control rod/fuel support handling apparatus including: a fuel support gripper that holds the fuel support with a support gripping member; a control rod gripper that includes a vertically movable and rotatable elevating/rotating unit, holds the control rod with a control rod gripping member, disconnects and connects the control rod and a control rod drive mechanism, and allows removal and attachment of the control rod; and a control panel that controls automatically controls the control rod gripper in response to the instructions from an operation pendant.

Abstract: A pressurized water reactor (PWR) includes a vertical cylindrical pressure vessel having a lower portion containing a nuclear reactor core and a vessel head defining an internal pressurizer. A reactor coolant pump (RCP) mounted on the vessel head includes an impeller inside the pressure vessel, a pump motor outside the pressure vessel, and a vertical drive shaft connecting the motor and impeller. The drive shaft does not pass through the internal pressurizer. A central riser may be disposed concentrically inside the pressure vessel, and the RCP impels primary coolant downward into a downcomer annulus between the central ser and the pressure vessel. A steam generator may be disposed in the downcomer annulus and spaced apart from with the impeller by an outlet plenum, A manway may access the outlet plenum so tube plugging can be performed on the steam generator via access through the manway without removing the RCP.

Abstract: A system, method and apparatus for remotely installing a flange cover assembly on a fuel transfer tube fixed flange in a containment pit in a nuclear power plant is presented. In one example, the flange cover assembly includes J-bolt spring assemblies in which the feet of the J-bolt are rotated between a clamping and non-clamping orientation to engage with the rear face of the fixed flange. A tool frame is lowered into the containment pit to engage with the flange cover assembly to compress the J-bolt springs and extend the J-bolt foot toward and away from the flange cover. Dual acting cylinders move a spring compression frame on the frame tool to compress and relax the J-bolt spring assemblies.

Abstract: According to an installation method of a water-chamber working apparatus of the present invention, the water-chamber working apparatus includes a base that holds heat transfer tubes on a tube plate surface and is fixed to the tube plate surface, and a manipulator that is coupled with the base, suspended in a water chamber and arranged therein, and has a separable configuration. In this case, a base installing step of installing the base on the tube plate surface and a manipulator coupling step of carrying the separated manipulator (a front stage and a rear stage) into the water chamber sequentially and individually and coupling the manipulator with the base (a coupling link) are performed.

Abstract: Exemplary embodiments provide automated nuclear fission reactors and methods for their operation. Exemplary embodiments and aspects include, without limitation, re-use of nuclear fission fuel, alternate fuels and fuel geometries, modular fuel cores, fast fluid cooling, variable burn-up, programmable nuclear thermostats, fast flux irradiation, temperature-driven surface area/volume ratio neutron absorption, low coolant temperature cores, refueling, and the like.

Abstract: Embodiments of the present invention provide a method, a device and a system for communication between double central processing units, which relates to the field of mobile communications technologies. An embodiment of the present invention provides a method for communication between double central processing units, where the method includes: receiving, by a baseband function module, a baseband function invocation request message sent by an application function module through a service channel and a virtual channel, where the baseband function invocation request message carries a virtual channel identifier, and the virtual channel identifier corresponds to the virtual channel; and in response to the baseband function invocation request message, returning, by the baseband function module, a baseband function invocation response message to the application function module, where the baseband function invocation response message carries the virtual channel identifier.

Abstract: A nuclear reactor comprises a pressure vessel, a nuclear reactor core comprising fissile material disposed in the pressure vessel, and a core basket disposed in the pressure vessel and containing the nuclear reactor core. An incore instrument is disposed in a guide tube of the nuclear reactor core. The incore instrument has a cable extending out of the bottom of the nuclear reactor core and making a 180° turn. A bottom support element is attached to the bottom of the core basket and defines or includes a routing tube that routes the cable of the incore instrument through the 180° turn. In some embodiments, the pressure vessel includes upper and lower vessel portions, the nuclear reactor core and core basket are disposed in the lower vessel portion, and the vessel penetration is through the lower vessel portion or through a mid-flange connecting the upper and lower vessel portions.