Abstract: A method for retrofitting a boiling water reactor slip joint of a jet pump to reduce vibrations is provided. The method includes removing a mixing chamber from an existing slip joint defined by a diffuser and the mixing chamber, the existing slip joint defining an existing annular gap, and providing a new slip joint defining a new annular gap, the new annular gap being reshaped to permit reduced vibration. A jet pump and a method of operating a jet pump are also provided.

Abstract: An embodiment of the present invention takes the form of a system that may reduce the level of flow-induced vibration (FIV) experienced by a jet pump assembly or other similar object within a pressure vessel. Essentially, an embodiment of the present invention may reduce the slip-joint leakage, which may be a cause of the FIVs, by adding a flow-limiting component to an outlet of the slip joint. This component may take the form of a collar, channel, and/or other component that may be connectable to a component of the jet pump assembly. After installation, an embodiment of the present invention may lower the amplitude of, and/or change the frequency of, the FIVs experienced by the jet pump assembly.

Abstract: An integral pressurized water nuclear reactor for the production of steam utilizing a helical coil steam generator, a plurality of internal circulation pumps, and an internal control rod drive mechanism structure.

Abstract: Example embodiment clamps may be used to clamp two components together, with a degree of freedom of motion between the clamped components, including both rotational and translational motion. Example embodiment clamps may clamp a BWR jet pump sensing line to a diffuser as a repair or installation of a sensing line support. Example clamps may include a ball subassembly that holds a component and allows rotation and twisting of the component within the clamp. Example clamps may further include jaws holding the ball subassembly and a biasing element that permits tightening of the clamp.

Abstract: Systems and method for tensioning jet pump beam bolts in a nuclear reactor are disclosed. The nuclear reactor may include at least one jet pump with each jet pump having a jet pump beam and a jet pump beam bolt. The system may include an actuating apparatus and a tensioning apparatus. The actuating apparatus may include a socket member for engaging the jet pump beam bolts, a sleeve member for engaging a handling pole, and an actuator hex positioned between the socket member and the sleeve member. The tensioning apparatus may include a base block having an opening for accommodating the jet pump beam bolt, a top plate having an opening for accommodating the actuator hex, and a hydraulic actuator for providing tension to the jet pump beam bolt in accordance to measurements of the actuating apparatus.

Abstract: An operation method and apparatus in a pressure vessel of a nuclear reactor is provided. The operation apparatus including a body and a guide inserted from the upper side of the nuclear reactor to an interior of the jet pump. The operation apparatus circulate water inside the pressure vessel. The guide is positioned at the end of a body of the operation apparatus, and is inclined with respect to the center axis of the body so as to be inserted into a side opening of the jet pump.

Abstract: A vertical spring wedge restores a tight fitup against an adjacent structure, such as between an inlet mixer and an adjacent restrainer bracket in a boiling water nuclear reactor jet pump. The vertical spring wedge includes a U-shaped bracket including a pair of guiding portions and a pair of bracket holes. A pair of wedge assemblies are coupled with the bracket, each of the wedge assemblies including a wedge segment attached to a spring-loaded guide rod. The guide rods are displaceable in the bracket holes between a retracted position and an extended position. The wedge segments engage the guiding portions, and a combination of the bracket and wedge assemblies have a first width when the guide rods are in the retracted position and have a second width wider than the first width when the guide rods are in the extended position.

Abstract: A clamp apparatus is provided which is designed to structurally replace a weld that attaches a riser brace assembly to a reactor pressure vessel wall, and a method for repairing the riser brace assembly. The riser brace assembly is designed to support a jet pump in the reactor pressure vessel. The riser brace assembly may include upper and lower riser brace leaves connected to a reactor pressure vessel pad on the wall. The clamp apparatus may include a first clamp component including a central extension portion, and a second clamp component including a slot portion. The central extension and slot portions may be engaged to provide alignment between the first and second clamp components between the upper and lower riser brace leaves of the riser brace assembly.

Abstract: A clamp assembly connects a diffuser adapter or lower ring to a diffuser tail pipe of a jet pump diffuser in a boiling water nuclear reactor. The clamp assembly includes at least two clamp segments shaped generally corresponding to an exterior circumference of the diffuser, a swivel link affixed at each end of each of the clamp segments, and at least two connecting bands pivotably secured to the swivel links between the ends of the clamp segments. The clamp segments each includes a locking assembly engageable with the diffuser adapter or lower ring and the diffuser tail pipe. The clamp assembly structurally replaces/repairs the weld joining the diffuser adapter or lower ring and the diffuser tail pipe.

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 jet pump diffuser weld repair device includes a lower ring section and an upper ring section respectively sized to fit around a circumference of the diffuser on opposite sides of the weld to be repaired. The lower and upper ring sections are provided with a plurality of aligned gripper slots. A corresponding plurality of grippers are fit into the gripper slots, where at least one of the gripper slots and the grippers defines cam surfaces shaped to drive the grippers radially inward as lower and upper ring sections are drawn toward each other. A plurality of connector bolts are secured between the lower ring section and the upper ring section. Tightening of the connector bolts draws the lower and upper ring sections toward each other.

Abstract: A BWR jet pump assembly has a wedge slidably mounted on a jet pump that is movable under the force of gravity to seat between a bracket and the jet pump in order to horizontally support the jet pump against vibrations. The wedge or the bracket is repaired in situ by: providing a spacer layer between mating surfaces of the wedge and the bracket; and then lowering the wedge until the spacer layer is between and in contact with the wedge and the bracket.

Abstract: Object of this invention is to provide an axial torsional vibration measurement device of the reactor internal pump capable of measuring the axial torsional vibration easily. The vibration detector 2 that detects vibration in the radial direction, and the sound detector 3 that detects vibration in the circumferential direction are fitted on cylindrical motor casing 6, which contains the motor of a reactor internal pump. The dimension of both signals of a vibration waveform signal detected by the vibration detector 2, and a sound waveform signal detected by the sound detector 3 are matched in vibration calculating device 15, to thereby obtain an axial torsion vibration of a motor from the difference of both signals.

Abstract: A method of inspecting a jet pump beam in a nuclear reactor is provided. The reactor includes at least one jet pump assembly with each jet pump assembly including at least one jet pump beam. Each jet pump beam includes a beam bolt opening, a first arm, a second arm, a top surface, and a bottom surface. In an exemplary embodiment, the method includes positioning at least one ultrasonic phased array probe adjacent the bottom surface of the jet pump beam, and scanning the jet pump beam with the at least one ultrasonic phased array probe.

Abstract: A piping support wedge apparatus for a jet pump in a nuclear reactor is provided. In an exemplary embodiment, the wedge apparatus includes a first tapered wedge segment having a first end portion and a second end portion and a second tapered wedge segment having a first end portion and a second end portion. The first and second wedge segments are joined at the first ends portions to form a substantially U-shaped body. The wedge apparatus also includes a slot defined by an area between the first and second wedge segments and extending from the first end portions to the joined second end portions of the wedge segments.

Abstract: Object of this invention is to provide an axial torsional vibration measurement device of the reactor internal pump capable of measuring the axial torsional vibration easily. The vibration detector 2 that detects vibration in the radial direction, and the sound detector 3 that detects vibration in the circumferential direction are fitted on cylindrical motor casing 6, which contains the motor of a reactor internal pump. The dimension of both signals of a vibration waveform signal detected by the vibration detector 2, and a sound waveform signal detected by the sound detector 3 are matched in vibration calculating device 15, to thereby obtain an axial torsion vibration of a motor from the difference of both signals.

Abstract: A piping support wedge apparatus for a jet pump in a nuclear reactor is provided. In an exemplary embodiment, the wedge apparatus includes a first tapered wedge segment having a first end portion and a second end portion and a second tapered wedge segment having a first end portion and a second end portion. The first and second wedge segments are joined at the first ends portions to form a substantially U-shaped body. The wedge apparatus also includes a slot defined by an area between the first and second wedge segments and extending from the first end portions to the joined second end portions of the wedge segments.

Abstract: Object of this invention is to provide an axial torsional vibration measurement device of the reactor internal pump capable of measuring the axial torsional vibration easily. The vibration detector 2 that detects vibration in the radial direction, and the sound detector 3 that detects vibration in the circumferential direction are fitted on cylindrical motor casing 6, which contains the motor of a reactor internal pump. The dimension of both signals of a vibration waveform signal detected by the vibration detector 2, and a sound waveform signal detected by the sound detector 3 are matched in vibration calculating device 15, to thereby obtain an axial torsion vibration of a motor from the difference of both signals.

Abstract: The invention relates to a method of repairing the labyrinth seal of a diffuser in a primary pump, the diffuser being of the type comprising a peripheral skirt and a circular end wall having an orifice provided with the labyrinth seal. The method consists in making a bore in the circular end wall having a diameter greater than that of the orifice, in reducing the thickness of the remaining portion of the end wall, in forming a chamfer on the edge of the bore, in positioning a replacement part in said bore, the replacement part including a central orifice and a chamfer on its own peripheral edge, in making a bead of welding between the chamfers, and in making a new labyrinth seal in the central orifice of the replacement part.

Abstract: A vibration mitigation clamp apparatus is provided, which is designed to stiffen a riser brace assembly in a nuclear reactor so as to increase the natural vibration frequency of the riser brace assembly. In an embodiment, the vibration mitigation clamp apparatus may include a first plate, a second plate and a wedge assembly. The vibration mitigation clamp apparatus is attached to upper and lower riser brace leaves of the riser brace assembly, at a location near a weld that attaches the leaves to a riser brace block of the riser brace assembly that is affixed to an RPV sidewall. The wedge assembly is expandable to apply forces on inside surfaces of the riser brace leaves, countering clamping forces applied to the first and second plate to fixedly secure the vibration mitigation clamp apparatus on the riser brace assembly.

Abstract: A jet pump for a nuclear reactor includes a riser and an inlet mixer having a set of nozzles and a mixing section for receiving coolant flow from the nozzles and suction flow from an annular space between the reactor vessel and the shroud core. To minimize or eliminate electrostatic deposition of charged particulates carried by the coolant on interior wall surface of the inlet-mixer of the jet pump, and also to inhibit stress corrosion cracking, the interior wall surfaces of the nozzles and mixing section are coated with a ceramic oxide such as TiO2 and Ta2O5 to thicknesses of about 0.5-1.5 microns.

Abstract: Methods for cutting a labyrinth seal in a nuclear reactor jet pump assembly are described. In one embodiment, the method includes removing an irradiated jet pump inlet mixer from the jet pump assembly, positioning the jet pump inlet mixer underwater, and cutting at least one circumferential groove in an inlet mixer outside surface.

Abstract: An old core shroud (11) and an old jet pump (16) received in a reactor pressure vessel (1) are cut and carried out. A module of core internals having a new core shroud (N11), a new jet pump (N16) and a new baffle plate (N29) integrated is carried into the reactor pressure vessel (1) in which an old baffle plate (28) and an old shroud support cylinder (13) welded and fixedly secured to the reactor pressure vessel (1), and an old shroud support leg (12) fixedly secured to said old baffle plate (28) and said old shroud support cylinder (13) are left. Then, the new baffle plate (29) is fixedly secured to the old baffle plate (28), and the new core shroud (11) is fixedly secured to the old shroud support leg (12).

Abstract: A reactor pressure vessel (RPV) for a nuclear reactor that permits measurement of the flow through each reactor internal pump (RIP) is described. The reactor pressure vessel also includes at least one reactor internal pump that includes an impeller and a pump diffuser. At least two seal rings extend circumferentially around an outer surface of the diffuser housing outer wall and are located in circumferential grooves in the housing outer wall. At least one lateral bore extends through the housing outer wall into a diffuser housing longitudinal flow passage. Each lateral bore is located in an area between two adjacent seal rings, with each inter-seal ring area containing one lateral bore. At least one pressure tap bore extends from the outer surface of the RPV bottom head petal, through the pump deck to an inner surface of a pump deck opening. Each pressure tap bore is aligned with an area in the RIP containing a corresponding lateral bore.

Abstract: A remotely installable piping support device includes a pair of mating tapered wedge segments extending from lever arms connected with a spiral wound spring. The spring is machined integrally with the left lever arm and has a projecting center square drive hub with an internal mounting thread. The right lever arm has an internal square drive which mates with the drive hub. A bolt engages the drive hub and secures the lever arms together. The spring preload on the wedge acting across the shallow angled wedge surfaces maintains rigid contact between jet pump components and takes up the clearance from wear during operation.

Abstract: A jacking device includes first, second, and third members (51, 52, 53), and a jacking screw (55). The first and second members (51, 52) have sloping side portions (57). The third member (53) has a plurality of sloped side portions (57) and a threaded opening (67) extending from its top portion (69) through to its bottom portion (59). The third member (53) is movably supported between the first and second members (51, 52). The jacking screw (55) engages the threaded opening (67) in the third member (53).

Abstract: A seal apparatus for a jet pump slip joint in a boiling water nuclear reactor pressure vessel, in an exemplary embodiment, includes a split seal ring and a segmented diaphragm spring engaging the split seal ring at an inner circumference of the diaphragm spring. The diaphragm spring includes a plurality of latch assemblies spaced circumferentially around an outer circumference. A plurality of slots, spaced circumferentially around the inner circumference, extend from the inner circumference to the support portion. Each latch assembly includes a latch bolt extending through and threadendly engaging a corresponding latch bolt opening in the diaphragm spring. Each latch bolt includes a head and a plurality of ratchet teeth spaced around the periphery of the latch bolt head. A locking spring is positioned to engage the ratchet teeth of the latch bolt head. The latch assembly further includes a latch arm coupled to the latch bolt. The latch arm includes a slot sized to receive a diffuser guide ear.

Abstract: A clamp assembly for a jet pump sensing line adjacent a jet pump within a nuclear reactor pressure vessel. The jet pump sensing line includes a support block. The clamp assembly includes a clamp body, a clamp member coupled to the clamp body, and a slide member coupled to the clamp body. The clamp assembly further includes a clamp bolt, a swing arm bolt, and a swing arm coupled to the slide member. The swing arm and the slide member are sized to receive and secure the sensing line and the clamp member. The clamp member and the clamp body are sized to secure the clamp assembly to the jet pump.

Abstract: A jet pump beam bolt locking assembly includes a locking sleeve having a plurality of ratchet teeth extending around the periphery of a base portion, and a lock plate having a beam bolt opening, and an integral beam spring arm having a plurality of ratchet teeth extending from at least a portion of a side of the spring arm. The spring arm ratchet teeth are sized to mesh with the locking sleeve ratchet teeth. The lock plate also includes a lip extending at least partially around the beam bolt opening which captures the locking sleeve. The spring arm is movable between a first position where a lock plate detent is positioned in a spring arm notch which permits engagement of the ratchet teeth, and a second position where the side of the spring arm is in contact with the detent which disengages the ratchet teeth to permit loosening of the beam bolt.

Abstract: A method for repairing cracked jet pump riser assemblies in a boiling water reactor utilizes a spacer clamp and a seal collar. The spacer clamp is secured to the riser assembly to limit horizontal displacement of the riser assembly, and the seal collar is secured around the weld joining the riser elbow and the thermal sleeve to limit leakage from the weld over a predetermined range of horizontal displacement defined by the spacer clamp. A method for repairing a circumferential weld connecting an elbow of a jet pump riser assembly with a thermal sleeve involves positioning the weld within a seal collar and securing the seal collar on the jet pump riser assembly so that seals of the seal collar sealingly contact the elbow and the thermal sleeve, respectively, circumferentially on opposite sides of the weld.

Abstract: An electrode discharge machining (EDM) apparatus for machining slots in a jet pump diffuser in a nuclear reactor pressure vessel is described. The apparatus is configured to machine a plurality of slots in the diffuser at positions behind the diffuser sensing line within the plane formed by the center of the diffuser and the sensing line. The apparatus includes a housing, a plurality of clamp assemblies, a hook assembly configured to engage the sensing line standoff so that the apparatus is positioned at an angle from a plane formed by the center of the diffuser and the sensing line, and a plurality of electrode assemblies. The EDM apparatus can be configured to be installed clockwise or counter-clockwise around the sensing line depending on the spacing available around given diffusers. The EDM apparatus is capable of burning a plurality of slots at the same time, thereby saving time and money.

Abstract: An optical detecting apparatus designed to reduce the time taken to stabilize the operation after a moment at which a power supply for the apparatus is turned on, as well as to limit the power consumption in a standby state. Three operating modes: a normal mode, an intermittent mode, and a precharge mode are changed by controlling two switches sw-Led and sw-Ref. In the normal mode, both the switches sw-Led and sw-Ref are maintained in the on state and the circuit of the invention is used for the same operation as the conventional circuit. In the intermittent mode, for the purpose of achieving low power consumption in the standby state, both the switches sw-Led and sw-Ref are turned on and off at a predetermined on-off ratio to make the circuit operate in an intermittent manner (that is, by turning on and off light emitting diodes at a predetermined on-off ratio).

Abstract: Apparatus for supporting the lower elbow assembly of a jet pump in a reactor pressure vessel (RPV) of a nuclear reactor are described. The clamp apparatus includes a lower clamp element and an upper clamp element. The upper and lower elements are configured to be positioned at the interface between the thermal sleeve and the jet pump riser elbow. The upper and lower elements include extended ridges that are configured to fit in circumferential grooves precisely machined into the sleeve-elbow assembly on opposing sides of the interface.

Abstract: A shroud attachment assembly which provides both structural support for the shroud and a seal between the shroud and shroud support is described. In one specific embodiment, the shroud attachment assembly includes a shroud flange formed integral with the shroud, and a pump deck flange formed integral with the pump deck. The shroud flange extends over the pump deck flange, and a plurality of studs extend through aligned openings in the flanges. In addition, a plurality of wedges are secured to the shroud flange by studs, and the wedges extend between the shroud flange and the pump deck flange. Generally, the studs which extend through aligned openings in the shroud and pump deck flanges transfer vertical loads from the shroud to the pump deck, and the wedges transfer horizontal loads from the shroud to the pump deck.

Abstract: An auxiliary wedge apparatus configured to couple to the restrainer bracket of a jet pump assembly is described. In one embodiment, the auxiliary wedge apparatus includes a support block configured to couple to the restrainer bracket, and a wedge configured to slidingly couple to a wedge channel in the support block, and to engage the inlet mixer to restore a tight rigid fit-up of the jet pump components. The support block includes a wedge channel having tongues depending from the parallel sides of the channel and a hook shaped portion configured to receive the restrainer bracket. The support block also includes a lock screw to couple the support block to the restrainer bracket. The wedge includes grooves in the parallel sides of the wedge configured to slidingly engage the tongues extending in the wedge channel.

Abstract: A wedge locking support apparatus that applies a downward preload force to a jet pump inlet mixer gravity wedge and is remotely installable without disassembly of the jet pumps is described. The downward force supplied by the wedge locking support apparatus supplements the force supplied by the weight of the gravity wedge and improves the lateral support provided to the inlet mixer by the gravity wedge. The wedge locking support apparatus includes an upper leaf spring assembly configured to engage the gravity wedge bracket, a lower leaf spring assembly slidably coupled to the upper leaf spring assembly and configured to engage the top of the wedge, and a jack bolt coupled to the upper and lower assemblies.

Abstract: A separator/injector having an outlet pressure higher than an inlet pressure thereof is introduced instead of the dynamic equipment for a reactor recirculation system that is necessary in the prior art, to achieve both liquid-vapor separation and forced circulation. A jet pump and a recirculation flow-rate control valve are provided in a lower portion of a downcomer portion of a reactor pressure vessel. A shroud head has a double-walled structure, a two-phase liquid-vapor flow that is flowing from a lower portion of the lower shroud head is accelerated by an accelerator nozzle of the separator/injector, and a liquid component of the thus-separated flow is increased in pressure and guided into a jet pump through a space formed between the double shroud heads.

Abstract: A method for recovering the clock in an ADSL (asymmetric digital subscriber line) communication system at the receiver to match the frequency of the transmitted signal. A digital phase locked loop (DPLL) based clock is used to adjust the frequency of data read accesses from a FIFO (first-in first-out) memory (26) in a transceiver unit. The frequency is adjusted according to a predetermined offset value, where the offset value indicates the relative difference between a read location in the FIFO memory (26) and a write location. The predetermined offset value defines an operating point or nominal data location in the FIFO memory (26). A FIFO phase detector (31) determines and affects the frequency adjustment to maintain the FIFO memory at approximately the operating point. One embodiment provides clock recovery for a received ADSL subchannel and a means to recover a 16 kHz clock for a channel control.

Abstract: A replacement jet pump diffuser apparatus and method are described. In one embodiment, the replacement diffuser apparatus includes a conical section, a first cylindrical section, and a second cylindrical section. The conical section is welded to the first cylindrical section, and the first cylindrical section is welded to the second cylindrical section. A V-flange is formed at one end of the second cylindrical section. The assembly further includes an adapter having a V-flange formed at one end. The adapter is secured to the second cylindrical section by a band clamp which compresses the V-flanges into contact. The adapter further includes an engagement flange having a plurality of bores extending therethrough. L-bolts extend through the respective bores in the engagement flange, and each L-bolt includes an L-section and a threaded section. Respective nuts threadedly engage the threaded sections of the L-bolts. The L-section of each bolt contacts a lower surface of the shroud support plate.

Abstract: A tool for vertically supporting a shroud repair tie rod assembly having a clevis hook by bracing the clevis hook against a clevis pin installed in a gusset plate. This allows the vertical support at the upper end of the tie rod assembly to be removed, so that the upper support structure can be coupled to the tie rod. The lower end of the tie rod assembly is supported on both sides of the gusset plate. The tool for vertically supporting the lower end of the tie rod assembly is designed to fit in the narrow space bounded by a jet pump diffuser, the gusset plate and the reactor pressure vessel. The vertical support tool includes a pole adaptor for coupling to the end of a service pole, a pole adaptor extension having one end connected to the pole adaptor, a mounting block connected to the other end of the pole adaptor extension, and a hydraulic spreader mounted on the mounting block. The hydraulic spreader opens in response to actuation of a hydraulic cylinder.

Abstract: In a pressure vessel of a nuclear reactor containing a core assembly enclosed within a core shroud, the core shroud spaced radially inwardly of a side wall of the pressure vessel with an annular pump deck located in an annular radial space between the core shroud and the side wall of the pressure vessel, the improvement wherein the shroud is removably secured to an annular support leg extending upwardly from the bottom of the pressure vessel; and further wherein the annular pump deck is provided in the form of a plurality of removable segments.

Abstract: In a pressure vessel of a nuclear reactor containing a core assembly enclosed within a core shroud, the shroud spaced radially inwardly of a side wall of the pressure vessel, and an annular pump deck welded in a place in an annular radial space between the core shroud and the side wall of the pressure vessel. The shroud provided with a radially outwardly extending flange seated on and removably secured to the pump deck. Wedge elements are interposed between flange portions and the side wall.

Abstract: A method and an apparatus for electrically suppressing electrochemical potential near highly susceptible components of a boiling water reactor. A small self-powered, electrical device is affixed to the metal area to be protected, which device has the capacity to locally suppress electrochemical potential automatically and continuously without provision for external power supplies, cables, penetrations, or other paraphernalia usually associated with electrical and electronic systems. The result is that components susceptible to intergranular stress corrosion cracking are not as sensitive to the details of the water chemistry flowing over them and do not crack as much, or as rapidly, as presently. The new technique is based on the concept of supplying electrons directly and locally to the sensitized zone(s) of the metal, thereby inhibiting intergranular stress corrosion cracking. The source of the electrons is .beta.-emitting material which is contained in a housing attached to the metal.

Abstract: In a pressure vessel of a nuclear reactor containing a core assembly enclosed within a core shroud, the core shroud spaced radially inwardly of a side wall of the pressure vessel with an annular pump deck located in an annular radial space between the core shroud and the side wall of the pressure vessel, the improvement wherein the shroud is removably secured to an annular support leg extending upwardly from the bottom of the pressure vessel; and further wherein the annular pump deck is provided in the form of a plurality of removable segments.

Abstract: A jet pump assembly for recirculating coolant through a recirculation loop of a boiling water reactor vessel, the jet pump assembly comprises a jet pump in operative association with the recirculation loop for forcing the coolant through the recirculation loop. A beam is positioned adjacent and in operative association with the jet pump for assisting in maintaining the positional relationship of the jet pump. A bolt is inserted in the beam for resisting the hydraulic forces generated in the jet pump, and an insert is disposed in said beam for receiving and surrounding the bolt which, in turn, reduces stress on the beam.

Abstract: A method and a device for minimizing electrostatically enhanced deposition of charged particulates in the jet pump nozzles of operating BWR plants. The jet pump nozzle has an inner conducting surface which is electrically isolated from the main body of the nozzle. An electrical circuit is electrically coupled to the inner conducting surface of the nozzle. The electrical circuit is designed to electrically minimize charged-particle deposition at the nozzle surface exposed to a free-stream electrical potential, using a DC circuit with active element feedback to adjust the surface potential to minimize the net current to the inner conducting surface, thereby minimizing deposition.

Abstract: A boiling water reactor comprises a reactor pressure vessel accommodated in a vertical fashion, a core disposed at a low portion in the reactor pressure vessel, a plurality of control rods to be inserted from an upper side of the core into the spaces between adjacent fuel assemblies and withdrawn therefrom upwardly, a shroud surrounding the fuel assemblies so as to define the core and having an upper end opening, a shroud head which closes the upper end opening of the shroud and through which the control rods are inserted or withdrawn, a separator standing upward from the shroud head to carry out gas-water separation of steam generated from the core, a fixing pedestal disposed above the separator, a control rod driving mechanism mounted on the fixing pedestal and adapted to drive the control rods, a drier unit including a plurality of drier elements annularly arranged along an upper inner wall surface of the reactor pressure vessel and adapted to dry the steam passing through the steam flow hole of the fixing

Abstract: A recirculation system for driving reactor coolant water in a downcomer within a reactor pressure vessel includes a jet pump disposed in the downcomer and having a suction inlet at the top thereof and an outlet at the bottom thereof. A reactor internal pump is joined directly to the pressure vessel at an access nozzle thereof and includes a housing sealingly joined to the access nozzle, and in serial flow communication an inlet channel, an impeller, an outlet channel, and an injector nozzle. The inlet channel carries coolant water from the pressure vessel to the impeller which pressurizes the coolant water and returns it through the outlet channel and the injector nozzle for injection into the jet pump inlet. The water injected from the internal pump into the jet pump drives the jet pump for effecting recirculation flow within the pressure vessel.

Abstract: A steam generator chemical solvent mixing system and method is provided. The chemical solvent mixing system includes a pump, having a discharge port fluidly connected to a discharge line and a suction port fluidly connected to a suction line. An upper level injector, including an injector nozzle extends through one upper access opening in the outer casing of a steam generator and extends into the annulus of the generator between the tube bundle shroud and the outer casing, the upper level injector being fluidly connected to the discharge port of the pump. A lower access eductor is provided, including an eductor nozzle extending through one lower access opening of the outer casing and adapted to discharge solvent through one passageway in the tube bundle shroud and into the tube bundle of the generator, the lower access eductor being fluidly connected to the discharge port of the pump.

Abstract: A BWR coolant recirculation system includes a pump deck disposed in a downcomer and fixedly joined to a reactor pressure vessel and reactor core shroud. A plurality of circumferentially spaced reactor internal pumps (RIPs) are joined to the deck and operable in a pumping mode for pumping downwardly a reactor coolant from the downcomer and into a core inlet. In a pump inoperable mode, a portion of the coolant bypasses the RIPs for allowing increased natural recirculation of the coolant from the downcomer and into the core inlet.