Abstract: Disclosed is a water jet peening method that includes the steps of: preparing a water jet peening apparatus having a supporting member, a first divider plate, a nozzle support body, and a second divider plate; inserting the water jet peening apparatus into a piping in which a structure or electronic device is mounted that is susceptible to damage by a jet of water discharged from a jet nozzle or by shock waves; disposing either the first divider plate or the second divider plate between the jet nozzle and the structure or electronic device; filling water into an internal area formed in the piping between the first divider plate and the second divider plate; and subjecting the inner surface of the piping to water jet peening by allowing the jet nozzle to discharge a jet of water into the water in the internal area.

Abstract: In a water jet peening apparatus, a high-pressure under-water pump is installed on an upper end of a casing and an injection nozzle drive mechanism equipped with an injection nozzle is attached to the casing. A high-pressure hose whose one end is connected to the high-pressure under-water pump is disposed in the casing and the other end of the high-pressure hose is connected to the injection nozzle. The casing is seated at an upper end of a control rod drive mechanism housing and the high-pressure under-water pump is driven. The high-pressure water pressurized by the high-pressure under-water pump is supplied to the injection nozzle through the high-pressure hose in the casing and is jetted toward the weld portion between the control rod drive mechanism housing and a stub tube. The time required for a water jet peening operation can be shortened.

Abstract: A miniature sludge lance for a steam generator in a pressurized water nuclear reactor is provided. The sludge lance is structured to enter the steam generator via an inspection opening and has a body sufficiently thin to fit between adjacent tubes. The sludge lance rail has at least two types of nozzle assemblies that may be attached thereto. One nozzle assembly rotates and another nozzle assembly translates in a vertical direction. A drive assembly, a mounting assembly, an oscillation assembly, and flow straighteners are also provided.

Abstract: A miniature sludge lance for a steam generator in a pressurized water nuclear reactor is provided. The sludge lance is structured to enter the steam generator via an inspection opening and has a body sufficiently thin to fit between adjacent tubes. The sludge lance rail has at least two types of nozzle assemblies that may be attached thereto. One nozzle assembly rotates and another nozzle assembly translates in a vertical direction. A drive assembly, a mounting assembly, an oscillation assembly, and flow straighteners are also provided.

Abstract: A miniature sludge lance for a steam generator in a pressurized water nuclear reactor is provided. The sludge lance is structured to enter the steam generator via an inspection opening and has a body sufficiently thin to fit between adjacent tubes. The sludge lance rail has at least two types of nozzle assemblies that may be attached thereto. One nozzle assembly rotates and another nozzle assembly translates in a vertical direction. A drive assembly, a mounting assembly, an oscillation assembly, and flow straighteners are also provided.

Abstract: A moveable sludge lance (76) said moveable sludge lance having duel lance heads (77, 79) passed through handholes (62) in the side of a nuclear steam generator and into a central tube lane (60) having a central stay rod (61) which cleans with high pressure fluid through the row 1 tubes (85) in the tube lane, where the distance (200) between the dual lance heads (77, 79) is wide enough to allow the dual lance heads to extend beyond the central stay rod (61).

Abstract: Disclosed herein is a segmental ultrasonic cleaning apparatus configured to remove scales and/or sludge deposited on a tube sheet. The segmental ultrasonic cleaning apparatus includes a plurality of segment groups arranged in a ring shape on a top surface of a tube sheet along an inner wall of the steam generator, in which each of the segment groups includes an ultrasonic element segment and a guide rail support segment loosely connected to each other by metal wires through hand holes located at a lower portion of the steam generator, such that ultrasound waves radiated from an ultrasonic transducer in each of the ultrasonic element segments travels along the surface of the tube sheet, with the segment groups tightly connected in the ring shape by tightening the metal wires via wire pulleys of flange units.

Abstract: A nuclear plant has a containment shell and a pressure relief pipe connected thereto in which a blowing device and a Venturi washer placed in a container with a washing liquid are connected in series. Even the finest particles or aerosols carried by air are held in the Venturi washer with a very high degree of reliability and the release thereof in environment is excluded in a particularly reliable manner in the case of decompression even associated with seal failures. For this purpose, the size of the blowing device and the Venturi washer are selected in such a way that during the operation of the blowing device a flow rate of liquid in the Venturi washer flowing to the decompressing pipe is higher than 130 m/sec, preferably higher than 180 m/sec.

Abstract: A filtration separation method for waste resin containing highly radioactive uranium powder and device thereof is mainly used for the waste resin after water treatment process in a nuclear facility. The uranium powder contained in the waste resin is highly radioactive. Thus, prior to the treatment of the waste resin, it is necessary to filter and separate the highly radioactive uranium powder to reduce the radioactivity. It is to put the uranium powder containing waste resin into an underwater holding tank and withdraw the waste resin by an underwater pump into a uranium powder filtration box. Then the uranium powder filtration box is lifted by a hoist to move to an underwater ultrasonic cleaner. High-pressure water flushing is applied and followed by underwater ultrasonic cleaning. Then the cleaning water (containing precipitated uranium powder) from the ultrasonic cleaner is drained to uranium powder collection device.

Abstract: A moveable sludge lance (76) said moveable sludge lance having duel lance heads (77, 79) passed through handholes (62) in the side of a nuclear steam generator and into a central tube lane (60) having a central stay rod (61) which cleans with high pressure fluid through the row 1 tubes (85) in the tube lane, where the distance (200) between the dual lance heads (77, 79) is wide enough to allow the dual lance heads to extend beyond the central stay rod (61).

Abstract: A method of cleaning sludge from the tube sheet (34) of a nuclear steam generator (10) includes introducing a moveable sludge lance (76) said moveable sludge lance having duel lance heads (77) through handholes (62) in the side of the generator and into a central tube lane (60) having a central stay rod (61) and sludge lancing with high pressure fluid through the row 1 tubes (85) in the tube lane, where the distance (200) between the dual lance heads (77) is wide enough to allow the dual lance heads to extend beyond the central stay rod (61).

Abstract: A wireless receiver includes a hardware (HW) block, a converter block and a digital signal processor (DSP). The HW block receives a wireless signal having a first DC Offset Component (DCOC), removes a portion of the first DCOC to produce a residual DCOC centered at DC, and generates parameters that estimate the residual DCOC. The converter block is coupled to the HW block and receives the residual DCOC centered at DC and converts it to a residual DCOC centered at IF. The DSP is coupled to the HW block and the converter block and receives the residual DCOC centered at IF from the converter block and the parameters from the HW block, and uses the parameters to eliminate the residual DCOC, and generate a baseband signal that is substantially free of the first DCOC and the residual DCOC.

Abstract: A method of cleaning sludge from the tube sheet (34) of a nuclear steam generator (10) includes introducing a moveable sludge lance (76) said moveable sludge lance having duel lance heads (77) through handholes (62) in the side of the generator and into a central tube lane (60) having a central stay rod (61) and sludge lancing with high pressure fluid through the row 1 tubes (85) in the tube lane, where the distance (200) between the dual lance heads (77) is wide enough to allow the dual lance heads to extend beyond the central stay rod (61).

Abstract: A system is provided for delivering tooling, suction pickup, and alignment platforms to a stay dome region of a stem generator or the tube-free lane regions adjacent to the stay dome region and includes a suction device positioned in the stay dome region of a steam generator capable of rotating 360° about a vertical axis which also acts as a platform for mounting inter-bundle tooling and alignment devices used to position the suction device radially at any given tube location around the stay dome region to align it with an annulus based spray nozzle tube cleaning system.

Abstract: A method for estimating a signal-to-noise ratio, in particular digital, received by a radio communication receiver. The method includes estimating separately the signal and the noise and filtering (36, 44) separately the signal (Eb) and the noise (N0) before carrying out the division (40) of the signal from the noise. The noise filtering is for example of the statistical type, whereas the signal filtering is of the low-pass filtering type.

Abstract: The invention relates to a guide tube especially for an instrumentation lance extending into a reactor pressure vessel. The guide tube includes a lower tube section and an upper tube section that extends into the interior of the reactor pressure vessel. In order to prevent radioactively contaminated particles from reaching the lower tube section disposed outside the reactor pressure vessel from forming a source of radiation, a separator is arranged in the upper tube section. The separator has a separation chamber in which the particles are deposited and are removed from the water.

Abstract: A device and method for removing radioactive crud material deposited on surfaces of a nuclear fuel assembly in a nuclear plant is provided. The device comprises a container arranged to accommodate the nuclear fuel assembly, a first pumping means to pump a fluid, composed of water and ice, through the container in order to release the deposit from the nuclear fuel assembly by abrasion and to transport the released radioactive material out from the container. The first pump means also enables the feeding of a gas or steam or both to the fluid that is fed into and through the container in order to create a turbulence in the fluid. The device further comprises means, arranged in a &ggr;-radiation-dampening medium, disposed to receive the radioactive deposit transported out of the container by the fluid.

Abstract: A preventive maintenance method and apparatus for a structural member in a reactor pressure vessel according to the present invention reduce a tensile residual stress on a surface of the structural member by impinging a water jet from a nozzle onto a plane surface of a deflector to thereby change direction of flow of the water jet, and impinging the water jet after being deflected onto the surface of the structural member. This method and apparatus are applicable to a narrow space portion, and can improve a residual stress on the surface of the structural member and can also prevent damage such as stress corrosion cracking.

Abstract: A process for the treatment of radioactive graphite which includes the following steps: (i) reacting the radioactive graphite at a temperature in the range of from 250° C. to 900° C. with superheated steam or gases containing water vapor to form hydrogen and carbon monoxide; (ii) reacting the hydrogen and carbon monoxide from step (i) to form water and carbon dioxide; and (iii) reacting the carbon dioxide of step (ii) with metal oxides to for carbonate salts. The process enables radioactive graphite, such as graphite moderator, to be treated either in-situ or externally of a decommissioned nuclear reactor.

Abstract: A scale removing device for removes scale adhering to the interior of a shell-and-tube-heat-exchanger-type steam generator. The scale removing device is provided with a flexible lance (58) holding a high-pressure water hose (91) movable with respect to a tube plate, tube support plates, and heat-transfer tubes. A cleaning head (60) is mounted to the forward end of the flexible lance. Formed inside the cleaning head is a cavitation generating nozzle hole (99a, 99b) communicating with the high-pressure water hose. Bubbles are generated at the time of cleaning, and the impact pressure generated when the bubbles collapse is propagated to remove scale over a wide range.

Abstract: A novel high-purity polymer dispersant and sludge conditioner added to the feedwater entering the secondary side of a nuclear steam generator for minimizing the accumulation of metal-oxide deposits within the nuclear steam generator during the continuing operation of the generator is disclosed. The high-purity polymer is selected from a group consisting of acrylic acid polymer, methacrylic acid polymer, acrylate polymer, methacrylate polymer, copolymers, and terpolymers, acrylate/acrylamide copolymer, acrylate/methacrylate copolymer, terpolymers, and mixtures thereof. Methods of making and applying the polymer dispersant and sludge conditioner are described. Means for removing the metal oxides and polymer from the blowdown stream are disclosed.

Abstract: The present invention is a control rod guide tube cleaning apparatus in a nuclear reactor which comprises a rod member, one end side portion of which has the thickness such that the end side portion can pass through an inside of a connecting portion between a housing of a control rod drive mechanism and a control rod guide tube, a nozzle for sucking water, mounted on the rod member on the one end side so that the nozzle can go in and out of the rod member, a means for rotating the rod member in a horizontal direction, and a water passage for leading water sucked in the nozzle to an outside of the housing along the rod member. The rod member is inserted into the control rod guide tube through the inside of the housing. Then, the nozzle is rotated downward so that a suction port of the nozzle faces adjacently to the bottom inside the control rod guide tube. The nozzle is rotated in the horizontal direction by rotating the rod member in the horizontal direction.

Abstract: A process for the treatment of radioactive graphite which includes the following steps: (i) reacting the radioactive graphite at a temperature in the range of from 250° C. to 900° C. with superheated steam or gases containing water vapor to form hydrogen and carbon monoxide; (ii) reacting the hydrogen and carbon monoxide from step (i) to form water and carbon dioxide; and (iii) reacting the carbon dioxide of step (ii) with metal oxides to for carbonate salts. The process enables radioactive graphite, such as graphite moderator, to be treated either in-situ or externally of a decommissioned nuclear reactor.

Abstract: A preventive maintenance method and apparatus for a structural member in a reactor pressure vessel according to the present invention reduce a tensile residual stress on a surface of the structural member by impinging a water jet from a nozzle onto a plane surface of a deflector to thereby change direction of flow of the water jet, and impinging the water jet after being deflected onto the surface of the structural member. This method and apparatus are applicable to a narrow space portion, and can improve a residual stress on the surface of the structural member and can also prevent damage such as stress corrosion cracking.

Abstract: A preventive maintenance method and apparatus for a structural member in a reactor pressure vessel according to the present invention reduce a tensile residual stress on a surface of the structural member by impinging a water jet from a nozzle onto a plane surface of a deflector to thereby change direction of flow of the water jet, and impinging the water jet after being deflected onto the surface of the structural member. This method and apparatus are applicable to a narrow space portion, and can improve a residual stress on the surface of the structural member and can also prevent damage such as stress corrosion cracking.

Abstract: A method of performing maintenance on a structural member inside a reactor pressure vessel includes lowering an annular guide rail having a second lug until the guide rail rests on an upper flange of a core shroud provided inside the reactor pressure vessel, detachably mounting the second lug of the guide rail to a first lug mounted on the core shroud, positioning a discharging nozzle at a position at which compressive remaining stress is added to a surface of the core shroud by moving the discharging nozzle in a radial direction and an axial direction of the core shroud by a discharging nozzle moving apparatus mounted on a turnable revolving on the guide rail and discharging water to add compressive remaining stress to a surface of the core shroud from the discharging nozzle.

Abstract: A preventive maintenance apparatus for structural members inside a nuclear reactor pressure vessel includes a ring-shaped guide rail having a plurality of lugs which is placed on an upper flange of a core shroud provided inside a reactor pressure vessel. At least some of lugs separately engage with a plurality of guide rods provided on an inner surface of the reactor pressure vessel. A turntable is rotated on the guide rail. A first discharging nozzle moving apparatus placed on the turntable moves a first discharging nozzle for adding compressive remaining stress to an outer surface of the core shroud in a radial direction of the core shroud and in an axial direction of the core shroud. A second discharging nozzle moving apparatus placed on the turntable moves a second discharging nozzle for adding compressive remaining stress to an inner surface of the core shroud in a radial direction of the core shroud and in an axial direction of the core shroud.

Abstract: The proposed installation comprises an abrasive liquid jet cutting module using a mobile nozzle (25) rotatable in all directions and which also supports a sensor (37) so that it can previously recognize the position or shape of the structure to be cut, a dosimeter (49) to measure its irradiation and a decontamination device (51) to eliminate all excess contamination from it. Cutting residue may be collected by suction. The installation is more universal than previously known installations.

Abstract: Methods and assemblies for cleaning a control rod guide tube in a nuclear reactor are described. An assembly, in accordance with one embodiment, includes a support housing and a flush tube. The support housing includes a bore extending between its first and second ends. The flush tube also includes a bore extending between its first and second ends. The flush tube extends through the support housing bore and is movably coupled to the support housing adjacent the first end of the support housing. The second end of the flush tube extends from the support housing and includes a flush nozzle which is movable between a first, or latched, position and a second, or open, position.

Abstract: A method for dislodging and dislocating scale, sludge, corrosion and other deposits from heat transfer equipment surfaces, such as boiler and heat exchanger surfaces in steam generation systems, which are in contact with aqueous systems. This invention relates to the introduction of an aqueous chemical cleaning solution into the heat exchanger vessel. The aqueous chemical cleaning solution contains a non-corrosive carrier agent and/or a non-corrosive intercalation agent. The carrier agent has the ability to penetrate the matrix of the sludge, scale and other deposits, and the intercalation agent causes the sludge, scale and other deposits to fracture and break apart. This invention relates to generating a series of pressure pulses within the non-corrosive aqueous chemical cleaning solution to create shock waves for dislodging, dissolving and fluidizing sludge and corrosion products.

Abstract: A receiver for orthogonal frequency division multiplexed signals includes means (14) for calculating the (discrete) Fourier Transform of the received signal, and means (20) for calculating the phase error due to local oscillator errors.

Abstract: An improved method for removing scale, sludge, corrosion and other debris and deposits from the interior of a heat exchanger vessel such as a nuclear steam generator, includes generating pressure pulses in a non-corrosive, strongly basic, amine-containing chemical cleaning agent in aqueous solution after the agent has been introduced into the interior of the vessel to create shock waves in the liquid for dislodging, dissolving and fluidizing sludge and corrosion products. The chemical cleaning agent is an aqueous solution containing at least one of the group of lower alkyl amines, e.g., dimethylamine, ethylamine, 1,2-diaminoethane, or diaminopropane, lower alkanol amines, e.g., ethanolamine, 2-methyl-2-amino-1-propanol, and 5-aminopentanol, lower alkoxy alkyl amines, e.g., 3-methoxypropylamine, and cyclic diimines, e.g., 1,10-phenanthroline, 2,9-dimethyl-1,10-phenanthroline, 4,7-dimethyl-1,10-phenanthroline, 2,2'-bipyridine, and 4,4'-bipyridine, and terpyridine, or combinations thereof.

Abstract: Method and apparatus for enhancing removal of corrosion products from a nuclear reactor piping system. A reagent is supplied into a multi-part reactor piping system to react with the corrosion products therein. The corrosion products dissolve into the reagent to define a contaminated solution. The contaminated solution is brought into contact with an ion exchange resin bed that absorbs the corrosion products from the contaminated solution to define a reagent-containing contaminant-free solution. In this regard, a circulation pump having a predetermined net positive suction head (NPSH) interconnects the system with the resin bed for pumping the contaminated solution from one part of the reactor piping system and into contact with the resin bed and thereafter pumping the contaminant-free solution from the resin bed and to another part of the reactor piping system to remove the corrosion products.

Abstract: An improved composite waterlance and cavity connection is described where fiber reinforcements longitudinally extend through the body (24) of waterlance (10) and are inserted into a wedge shaped cavity at the top (18a) and bottom (18b) of a front manifold (18). An adhesive in the cavity and on the end of the rope (36) fixes the rope to the front manifold (18) and to the body (24) of the waterlance (10) to provide improved strength in the connection.

Abstract: Low temperature water in a low temperature water tank 12 installed outside a reactor pressure vessel 9 is pumped by a high pressure pump 15 and supplied through a conductor 17 under pressure. The supplied water is ejected, as a stream of cold water jet 8, from a nozzle 14 connected to the conductor 17 and introduced into the reactor pressure vessel 9 by a driving mechanism. The stream of cold water jet 8 ejected from the nozzle 14 is directed to impinge against a predetermined position of a core shroud 13 in reactor water 11 filled in the reactor pressure vessel 9 and being at temperature higher than the low temperature water. Then, while continuing to eject the cold water jet 8 from the nozzle 14, the nozzle 14 is moved away from the predetermined position, or the ejection of the cold water jet 8 from the nozzle 14 is stopped, allowing the predetermined position to be heated again with the temperature of the reactor water 11.

Abstract: An apparatus for cleaning inlet mixers while they remain in their operating position within a nuclear reactor. A cleaning tool is inserted by remote control into the inlet mixer via a secondary inlet opening. Following insertion of the cleaning tool, the internal surfaces of the inlet mixer are cleaned with a waterjet created from an ultra-high-pressure source and directed by controlled positioning of a cleaning head having a nozzle which scans the cleaning waterjet across the surface to be cleaned. The cleaning system includes a nozzle cleaning tool, a throat/barrel/flare cleaning tool, pumping systems for supplying ultra-high-pressure equal to at least 20,000 psi and low-pressure water to an installed cleaning tool, a launching system located at the top of the opened reactor vessel for feeding the water conduits (power), control cables, monitoring cables (instrument) and cleaning tool into and out of the inlet mixer, and a computerized process monitoring and control system.

Abstract: An improved method for cleaning heat exchangers, wherein a first liquid containing a cleaning agent is used to remove substantially all of the accumulated sludge and deposits from the surfaces of the heat exchanger, and a second liquid containing a cleaning agent is used to remove deposits from the crevice regions of the heat exchanger. The concentration of cleaning agent in the second liquid and/or the duration of exposure for the second liquid are preferably greater than those of the first liquid, because the risk of corrosion is reduced as a result of a lower concentration of ferric ions in the second liquid. Furthermore, improved crevice region cleaning is obtained with the second liquid because the available cleaning agent is not depleted by the large volume of sludge and deposits removed by the first liquid. Mechanical cleaning techniques such as pressure pulse cleaning may be utilized with either or both of the cleaning liquids.

Abstract: A device for closing and sealing a lead-through (1), comprising means intended to open, clean and again close the lead-through. A cone (2) with a head (21), a rod-shaped part (22) and a sealing surface (23) arranged between said head and said rod-shaped part is arranged with the head inserted into the lead-through. In the end of the cone opposite to the head, the cone is provided with means (24) for connecting the cone to a flush pipe (5) arranged in the form of an extension of the rod-shaped part of the cone. An annular flange (3) is attached to the lead-through and around said rod-shaped cone, inserted into the lead-through, to retain the head of the cone in the lead-through. A sealing surface (31), arranged on the annular flange in the form of a seat, is adapted to correspond to and make contact with the sealing surface of the cone to close and seal the lead-through.

Abstract: A high-speed abrasive liquid jet is directed at the surface of the component (13) with an angle of incidence between 30.degree. and 90.degree.. The jet is moved so as to sweep over the internal surface of the component (13). At least two successive machining passes are made. The speed of sweeping increases from one machining pass to the next. The device (30), mounted so as to move in translation and in rotation inside the adaptor (13), consists of a tube assembly supplied with pressurized liquid onto which a nozzle (33) is fixed.

Abstract: A method for cleaning inlet mixers while they remain in their operating position within a nuclear reactor. A water-powered cleaning tool is inserted by remote control into the inlet mixer via a secondary inlet opening. Following insertion of the cleaning tool, the internal surfaces of the inlet mixer are cleaned with a waterjet created from an ultra-high-pressure source and directed by controlled positioning of a cleaning head having an nozzle which scans the cleaning waterjet across the surface to be cleaned.

Abstract: An apparatus decontaminates a radioactively contaminated surface region of a pipe, connector or vessel being open at one end, with a dry mechanical blasting medium. The apparatus includes a processing bell to be mounted on the open end of the pipe, connector or vessel. A flexible dustproof duct is connected to the processing bell. A retaining device protrudes into the duct and is movable from outside in the interior of the pipe, connector or vessel. A blasting head is disposed on the retaining device. A blasting system is connected to the blasting head and has a continuous circulation of the blasting medium.

Abstract: A sliding lance guide flexible lance system (10) is attached to a hand hole (12) of a nuclear power plant steam generator by means of flange (14) of tilt module (16). A rail (18) extends from the tilt module (16) to a support stand (20) and is attached to the stand (20) by a pivot (22) so that the rail (18) is free to rotate with the tilt module (16). A tilt drive motor (24) is attached to the tilt module (16). A flexible lance (26) extends into the rail (18) for extension through a lance guide shoe (27). The lance guide shoe (27) deflects the lance from the rail (18) into the tube gap of the steam generator. The lance guide shoe (27) is slideably mounted in the rail (18), and is attached to a lance guide belt (30), which extends within and along the rail (18). Similarly, the flexible lance (26) extends within and along the rail (18). A lance guide belt sprocket drive (40) is mounted on support (33) to engage the lance guide belt (30).

Abstract: A water jet peening method in which a pressurized water jet flow containing cavities is jetted through a nozzle having a velocity increasing orifice portion and a horn-like jetting hole formed continuously with the velocity increasing orifice portion to impinge against a surface of a metallic material immersed in water and to cause the cavities to collapse at the surface of the metallic member, and a tensile plastic deformation is caused in a surface layer of the metallic material by a local high pressure generated by the impingement and the collapse so that a residual tensile stress in the surface of the metallic member is reduced. In this method, the nozzle is vibrated so that vibration-induced cavities are formed in the vicinity of a nozzle wall surface, and the vibration-induced cavities are caused to impinge against the surface of the metallic member by the pressurized water jet flow containing cavities.

Abstract: In addition to the metal-fiber filter and molecular sieve of a depressurization system for the containment vessel of a nuclear reactor, within an auxiliary equipment building adjacent the structure surrounding the containment vessel, at least one metal-fiber filter and at least one molecular sieve form filter elements of a system for evacuating the space between the structure and the containment.

Abstract: An on-line method and apparatus for dislodging deposits from the distributors (12) in an adsorption tower (10) thereby cleaning the tower (10) by causing a surge in a fluid to dislodge the blocked openings (14) of the distributors (12).

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 filtered venting system located in association with a reactor containment vessel installed in a reactor building comprises a filter device disposed in the reactor building and including filter means, a first venting line disposed on an upstream side of the filter device and having one end connected to the reactor containment vessel and another end connected to the filter device, a stand-by gas treatment system including outlet fan means or pump means and connected to the first venting line at the downstream side of the fan or pump means, and a second venting line disposed at a downstream side of the filter device and another end connected to an outlet means/ The filter device being utilized for the stand-by gas treatment system for treating and removing a radioactive substance contained in an atmosphere delivered from the reactor containment vessel.

Abstract: A control rod drive assembly includes a translatable drive tube joined to a control rod by a coupling having complementary screw threads. A purge flow is channeled between the screw threads to flush away debris therebetween for preventing galling of the threads during operation.

Abstract: The present invention is an apparatus and method of preparing and inspecting a submerged surface of a fluid reservoir. The apparatus includes a chassis sized and shaped to provide an optimally low center of gravity, a propulsion system comprising two independently controllable motor and track means, a scrubbing/vacuuming system disposed at the front of the chassis which includes a scrubbing system designed to mechanically break up sediment on the surface beneath the apparatus and a vacuuming system to remove sediment and sediment-containing fluid from beneath the apparatus, and an inspection system located immediately behind the scrubbing/vacuuming system with respect to the direction of apparatus travel and operative to inspect the freshly cleaned surface with either ultrasonics, optics, or a combination of both.

Abstract: An improved articulated sludge lance with a retractable movable extension nozzle for cleaning a steam generator. The extension nozzle includes a flexible conduit adapted to be moved with a wire cable to place the nozzle in close proximity to a support plate for effectively cleaning the broached holes therein. A bumper member fastened to the flexible conduit provides a side-to-side motion from impact with the tubes when the lance is moved therethrough.