Abstract: Methods, systems and apparatus are described to provide visual feedback of a change in map view. Various embodiments may display a map view of a map in a two-dimensional map view mode. Embodiments may obtain input indicating a change to a three-dimensional map view mode. Input may be obtained through the utilization of touch, auditory, or other well-known input technologies. Some embodiments may allow the input to request a specific display position to display. In response to the input indicating a change to a three-dimensional map view mode, embodiments may then display an animation that moves a virtual camera for the map display to different virtual camera positions to illustrate that the map view mode is changed to a three-dimensional map view mode.

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: Method of repairing nuclear reactors that include one or more submerged lines welded to one or more support brackets may include: removing a damaged section of one of the one or more submerged lines; and replacing the damaged section of the one of the one or more submerged lines without welding. Methods of operating nuclear reactors that include one or more submerged lines welded to one or more support brackets may include: shutting down the nuclear reactor; repairing damage to at least one of the one or more submerged lines without welding; and starting up the nuclear reactor. Methods of operating nuclear reactors that include one or more submerged lines welded to one or more support brackets may include: cooling down the nuclear reactor; repairing damage to at least one of the one or more submerged lines without welding; and heating up the nuclear reactor.

Abstract: A clamp assembly for securing a thermal sleeve and an elbow in a pipe assembly in a nuclear reactor. The clamp assembly comprises a sleeve clamp adapted to be arranged surrounding the elbow at a first joint between the elbow and a thermal sleeve, and comprising a sleeve support adapted to extend across the first joint. The clamp assembly comprises at least one clamp arm with a first end arranged to rest against at least one of a core shroud and a core plate support ring, to provide support for the positioning of the sleeve clamp.

Abstract: A method of preventing separation of a feedwater sparger end bracket assembly comprises installing first and second clamp members of a clamp over a feedwater sparger end bracket assembly in opposition to one another, and leaving the clamp in place to constrain the feedwater sparger end bracket assembly against separation in first, second and third directions.

Abstract: An apparatus and method are provided which are designed to structurally replace welds that attach a riser brace assembly to a jet pump riser pipe. The riser brace assembly may include an upper clamp assembly, a lower clamp assembly, and a plurality of mechanical fasteners to provide clamping forces to the upper clamp assembly and the lower clamp assembly. The upper clamp assembly and the lower clamp assembly sandwich a riser brace support, wherein the riser brace support is provided with at least one through-hole to accommodate the plurality of mechanical fasteners.

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 core spray sparger assembly for supplying coolant to a nuclear reactor. The nuclear reactor includes fuel assemblies, a top guide, coolant supply pipes and a shroud head. The core spray sparger assembly includes at least one coolant manifold, at least one coolant coupling in fluid communication with the coolant manifold, and at least one mounting device configured to couple the coolant manifold to the nuclear reactor. The core spray sparger assembly further includes a plurality of fluid conductors in a parallel array positioned above the fuel assemblies, the fluid conductors in fluid communication with the coolant manifold, and a plurality of nozzles in fluid communication with the fluid conductors.

Abstract: A core spray sparger for use in a nuclear reactor pressure vessel. The core spray sparger includes a plurality of core spray lines, a coupling apparatus, a bracket assembly, and an end clamp assembly. The core spray line includes a core spray line end cap.

Abstract: A collar clamp assembly is disclosed for repairing and providing a temporary seal around leaking pipe coupling areas of an internal core spray system of a nuclear reactor. The clamp assembly includes first and second housings having respective first and second ends and a pair of longitudinal edges between the ends. The housings have a tongue and groove mating configuration along the longitudinal edges to seal and accommodate variations in the outside diameter of the core spray piping. A plurality of threaded fasteners are used to secure the first and second housings together to form a closed conduit shaped to receive a length of the core spray piping, including the leaking pipe coupling. First and second seals are located at first and second longitudinally spaced positions, respectively, on each of the first and second housings and extend around the closed conduit.

Abstract: Downcommer coupling apparatus and methods for replacing a core spray line downcommer pipe coupled to a shroud T-box are described. In one embodiment, the coupling apparatus includes a wedge flange, a wedge, a wedge housing, a pipe seal, a cylindrical pipe, an elbow, a lower flange, and a shroud seal. The downcommer pipe is connected to the coupling apparatus by extending the pipe through the wedge flange, the wedge, and the wedge housing. The wedge has a plurality of flexible thinned segments that extend into the wedge housing to secure the downcommer pipe to the wedge housing. Wedge flange bolts extend through the wedge flange, the wedge, and the wedge housing to rigidly secure the downcommer pipe to the coupling apparatus. Dowel bolts extend through the wedge housing and the downcommer pipe to provide vertical and torsional load transfer from the downcommer pipe to the coupling apparatus. The lower flange is configured to receive the shroud T-box.

Abstract: A steam power station, in particular a nuclear power station, includes a steam conduit leading through a wall and forming a fixed point with the wall for the introduction of forces and moments. A main valve is connected to the steam conduit at the fixed point, without a high-pressure pipe being interposed. Satellite valves, which have smaller nominal widths than the main valve, are fastened to the housing of the main valve, without a high-pressure pipe being interposed. At least one additional valve has a housing fastened to the housing of a satellite valve, without a high-pressure pipe being interposed and without any support.

Abstract: A restraint assembly which is a bolted lattice structure for preventing the in-core guide tubes from experiencing excessive flow induced vibrations is described. In one embodiment, the restraint assembly includes upper and lower restraint brackets secured to an in-core housing and in-core guide tube assembly. The restraint brackets are located approximately equal distance from the end supports of the in-core guide tube and in-core housing assembly. The upper restraint bracket is welded between sections of the in-core guide tube, and the lower restraint bracket is welded between the in-core guide tube and the in-core housing. Each bracket includes four flanges, and each flange has tapped, or threaded, openings therein. Each bracket also includes cylindrical sections extending from the flanges, and in one embodiment, the cylindrical sections have inner and outer diameters which match the inner and outer diameters of the in-core housing and the in-core guide tube.

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: A spacer for maintaining a pressure tube in spaced relation with a caland tube of a nuclear reactor. The spacer comprising a split ring adapted to be disposed about the outer surface of said pressure tube. The ring has a central annular body portion with a raised bearing surface thereon adapted to contact the inner surface of said calandria tube and prevent contact between said outer surface and said inner surface. An annular land projecting from each side of said central body portion is adapted to receive a collar thereon effective create an interference fit between said ring and said pressure tube and thereby constrain axial movement of said spacer on said pressure tube. The spacer of the present invention maintains its location on the pressure tube and does not suffer the axial movement which characterizes some conventional spacers. The bearing surface can have a coating to reduce wear and heat transfer.

Abstract: Methods for sealing cracks adjacent stub tube attachment welds in a reactor pressure vessel of a nuclear reactor are described. The reactor pressure vessel includes at least one stub tube through which a control rod housing extends. The control rod housing is attached to one end of the stub tube with an upper stub tube attachment weld. In one embodiment, a sidewall of a control rod drive housing is cut at a location below the upper stub tube attachment weld to form a weld passage in the control rod drive housing between the control rod drive housing and the stub tube. A weld is then formed in the weld passage so that it is in physical contact with both the stub tube and the control rod housing, and thus seals the control rod drive housing against the stub tube.

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: The reactor pressure vessel comprises a pipe socket (2) connected to a feed-water supply line (3), in which is disposed a coaxial protective sleeve (5) (thermal sleeve) which expands with changes in temperature. With its outer end the protective sleeve (5) slidably abuts the pipe socket (2) and with its inner end it is connected to a feed-water distributing ring situated in the vessel. A pipe section (10), in which bellows (15) are disposed, is inserted between the outer end of the pipe socket (2) and the feed-water supply line (3). With one end the bellows (15) are tightly connected to the outer end of the protective sleeve (5) and with their other end they are tightly connected to the pipe section (10).

Abstract: A removable feedwater sparger assembly includes a sparger having an inlet pipe disposed in flow communication with the outlet end of a supply pipe. A tubular coupling includes an annular band fixedly joined to the sparger inlet pipe and a plurality of fingers extending from the band which are removably joined to a retention flange extending from the supply pipe for maintaining the sparger inlet pipe in flow communication with the supply pipe. The fingers are elastically deflectable for allowing engagement of the sparger inlet pipe with the supply pipe and for disengagement therewith.

Abstract: A method for sealing a leak between a control rod drive (CRD) stub tube (3) arranged in a reactor wall (2) and a tubular CRD housing (1) extending through the CRD stub tube (3) and the vessel wall (2). According to the invention, this sealing is obtained by deforming a suitably shaped element of memory metal below the transition temperature of the memory metal in such a way that it can be inserted, in the form of a sleeve (5) or a ring, into or around the CRD housing (1) where said housing passes through the vessel wall (2), or alternatively replace part of the CRD housing (1) at the passage through the vessel wall (2). Then when the memory metal is heated to above the transition temperature, it strives to resume its original shape which shall then have been such that the desired seal is obtained.

Abstract: The tube (4) to be plugged is cut at its ends adjacent to the first and to the second branch (14, 15) and the metal of the junction zones (16, 16') of the tube (4) with each of the branches (14, 15) is eliminated. At least one portion of the tube (4) adjacent to at least one of the branches (14, 15) is cut and eliminated. Into each of the ends of the tube (4) in place inside the heat exchanger is introduced a plug (24, 30) of tubular shape, the diameter of which is smaller than the inside diameter of the tube (4), so that the plug has a closed end (24a, 30a) inside the tube (4) and an opposite end located inside the corresponding branch (14, 15). The plugs (24, 30) are fixed in place in the branches (14, 15), and a continuous sealing weld is made between each of the plugs (24, 30) and the corresponding branch (14, 15 ), the tube (4) having some freedom of movement in the longitudinal direction in relation to the plugs (24, 30).

Abstract: The invention relates to a sealing sleeve for sealing a leak in, for example, a pipe, a pipe socket or the like in a nuclear reactor. The sleeve comprises a bellows-like mid-portion (1) with annular ends, at least these or part of these (2) being made of a memory metal with a suitable transition temperature. At a temperature above the transition temperature, that part of these annular ends which consists of memory metal has been given an inner diameter suitable for achieving sealing around the relevant pipe section on each side of the leak. The mentioned part of the ends has thereafter, at a temperature below the transition temperature, been deformed into a diameter which permits the sleeve to be freely fitted onto the pipe. In fitted position, the sleeve is then heated to above the transition temperature, the memory metal then striving to recover its previous shape and shrinks the sleeve so as to obtain sealing.

Abstract: A hot pipeline is welded to a flange which is supported by brackets connected to a nozzle. The pipeline with a flange can expand freely radially. Welded to the other end of the flange is a pipe, which can withstand an axial temperature gradient between a temperature T.sub.1 at the pipeline and flange, and a temperature t.sub.2 at a compensator and the nozzle. The axial expansion of pipe is accommodated by the compensator, which is welded to the pipe and at its other end to the nozzle. The pipeline, the flange, the pipe and the compensator are subject to the difference between pressure p.sub.2 in the vessel and the pressure p.sub.1 in the pipeline.

Abstract: A restraint to enable temporary bracing and operation of a thermally cracked sparger nozzle mounted from a sparger manifold at the end of a pipe elbow is disclosed. The restraint includes a second and surrounding restraint elbow which is fitted over and captures the sparger elbow. The restraint elbow has a saddle surface baseplate communicated to the lower end which rest on the sparger manifold to form a substantially water tight base for the restraint. The nozzle end of the restraint elbow is fitted with a nozzle aperture plate for surrounding the outside of the sparger nozzle again in substantially water tight relation. The plate is mounted for movement on the end of the restraint elbow for conforming threading of the restraint at the plate over the sparger nozzle. The restraint can be rapidly mounted (in less than a minute), tack welded at the aperture and seat tensioning bold (in less than 4 minutes) and left in the reactor for a complete fuel cycle.

Abstract: In a known design of liquid metal cooled fast fission nuclear reactor, the primary pumps (22) plug into the outboard ends of the high pressure pipes (28), leading to the development of a vertical load which has to be supported by substantial additional structure to avoid subjecting the reactor diagrid (18) to significant bending moments. The invention resides in connecting the inboard ends of the high pressure pipes (28) to the diagrid (18) via spigot and socket joints (40) so that the pipes are not rigidly connected at either end. With this arrangement loads are developed at each end of the pipes which combine to produce radial reaction loads acting on smaller moment arms whereby the total moments imposed on the diagrid are reduced.

Abstract: Multi-layer compensator with spacers arranged between the layers and with the spacers having the shape of flat strips distributed parallel to the longitudinal axis of the compensator over the circumference, with a gap between spacers.

Abstract: The invention relates to a gas cooled high temperature reactor located in the cavity of a pressure vessel, with spherical fuel elements, and removal apparatus for fuel elements. The latter is made of at least one ceramic pebble outlet tube extending through the graphite structural parts of the nuclear reactor (bottom reflector, bottom layers) and a number of metal pebble outlet tubes installed through the bottom of the pressure vessel. They are arranged coaxially in the liner of the passage through the vessel. To be able to dismantle the metal pebble outlet tubes, they are constructed of several releasably interconnected tube segments. Between the uppermost tube segment and the corresponding ceramic pebble outlet tube a compensating tube is provided and connected with the tube segment by means of a sliding joint. The other end of the compensating tube is fastened to the thermal bottom shield.

Abstract: A multiple shell pressure vessel utilizes a number of spaced apart, concentrically disposed pressure vessel shells within and spaced apart from an outer pressure vessel shell, the spaces between each shell being filled with a low melting point, high boiling point material selected from the group, lead, tin, antimony, bismuth, or sodium and potassium, and mixtures thereof and subjected to a pressure whereby the innermost pressure vessel shell wall is maintained in compression while the main vessel is pressurized. Chemical compositions or compounds which contain boron or cadmium may also be added to the filler material. The vessel may include devices for keeping the pressure in the space between the innermost pressure vessel shell and the next innermost shell at a fixed predetermined multiple of the pressure within the innermost pressure vessel shell.

Abstract: A novel liquid nuclear reactor is described which comprises a reactor vessel that is connected through upper and lower liquid conduit means to one or more satellite tanks that contain a heat exchanger means and pump means.

Abstract: Disclosed is a nuclear reactor employing a liquid metal and containing a reactor vessel, and at least one satellite vessel, and a hot and a cold leg connecting means which combine to form a continuous pathway for the flow of the liquid metal between the reactor vessel and the at least one satellite vessel. Each of the hot leg and cold leg connecting means contain a bellows assembly which are readily accessible for repair or replacement without draining the reactor vessel of the liquid metal.

Abstract: A metal conduit assembly for interconnecting the discharge duct of the pump and the inlet coolant duct or reactor core in a pool-type nuclear reactor. The conduit assembly comprises an upper section for connection to the discharge of a reactor pump, a lower section for connection with the coolant inlet duct with reactor core and a third intermediate tubular section for interconnecting the other two sections. Joint means are provided for interconnecting one end of the intermediate section with an adjoining end at the upper section and an opposite end of the intermediate section with an adjoining end of the lower section. The joint means comprises a male portion having a ridge provided with a circumferential groove for receiving a seal means and an associated female portion having an inside diameter greater than that of the ridge for receiving said male portion and a seal means.

Abstract: An apparatus for expanding a tube against the walls of a circumscribing bore, or a sleeve within a tube to effect an interference joint therebetween, is described herein. The tube expansion apparatus generally comprises a fluid mandrel connected to a hydraulic expansion unit for applying a radially expansive force to the tube or sleeve, and a control circuit electrically connected to the expansion unit and fluidly connected to the mandrel for sensing fluctuations in the pressure of the fluid discharged from the mandrel during the elastic and plastic deformation of the tube or sleeve during the expansion process, computing a final swaging pressure on the basis of these pressure fluctuations, and deactuating the hydraulic expansion unit when this final swaging pressure is attained within the tube or sleeve. The invention is particularly adapted for minimizing or eliminating the clearance between the heat exchange tubes of a nuclear reactor, and the baffle plate bores through which they extend.

Abstract: A high-temperature nuclear power plant, includes a reactor, an inner vessel enclosing the reactor, an outer reactor pressure vessel disposed outside the inner vessel, a stub integral with the outer vessel, and a hot gas pipeline disposed in the stub, the improvement comprises a screw connection being releasable from outside the outer vessel for fastening the hot gas pipeline to the inner vessel, and a device connected to the hot gas pipeline for applying a force to the hot gas pipeline in a direction tending to separate the hot gas pipeline from the inner vessel.

Abstract: A pressure surge attenuation system for pipes having a fluted region opposite crushable metal foam. As adapted for nuclear reactor vessels and heads, crushable metal foam is disposed to attenuate pressure surges.

Abstract: The present invention relates to a nuclear boiler comprising a vessel whose top is closed by a dismountable cover, a cage bearing the core of the reactor and separating the vessel into an inner hot zone and an outer cold zone, at least one steam generator disposed outside the vessel and comprising a tight enclosure, a tube plate, separating the enclosure into a primary part, or water box, and a secondary part, and bearing U-shaped tubes whose ends open into two concentric zones of the water box separated by an internal structure, at least one hot connecting pipe and one cold connecting pipe respectively connecting the hot zone and the cold zone of the vessel to each of the concentric zones of the water box, wherein the tube plate, the tubes and the secondary part of the enclosure of the steam generator define a sub-assembly dismountable from the primary part of the enclosure, the hot connecting pipe being dismountably mounted between the cage and the internal structure of the water box, this strucutre itself

Abstract: A nuclear reactor assembly including a substantially cylindrically-shaped and vertically extending pressure vessel. A uniquely constructed bracket assembly is arranged for mounting a water distributor against an inner wall of the cylindrically-shaped pressure vessel, with the bracket assembly including a spring assembly capable of biasing an inlet conduit of the water distributor into abutting contact with an inlet nozzle extending through a wall of the pressure vessel.