Abstract: A method of inspecting, performing maintenance on, or repairing a nuclear reactor may include operatively connecting a fixing device, a first track, an arm including one or more second tracks, and an effector to form an apparatus; inserting the apparatus into the reactor; fixing the apparatus within the reactor; and operating the apparatus. At least one of the one or more second tracks may include at least three track sections. The arm may have a contracted length. The arm may have an expanded length. The expanded length may be greater than two times the contracted length. The first track may include one or more motors configured to move the arm relative to the first track. A method of operating a reactor may include shutting down; inspecting, performing maintenance on, or repairing the reactor; and starting up the reactor.

Abstract: An opening and closing device that opens and closes an access port opened from a substantially cylindrical working platform disposed inside a reactor vessel and used to access a nozzle stub of the reactor vessel from the inside of the working platform, the opening and closing device includes: a cover that is slidable along an outer peripheral surface or an inner peripheral surface of the working platform from a closing position where the access port is closed to an opening position where the access port is opened; and moving device for sliding the cover.

Abstract: Disclosed is a nozzle stub working system for a reactor vessel that performs work inside a nozzle stub of the reactor vessel, the nozzle stub working system for the reactor vessel including: a platform unit that is provided at an upper portion inside the reactor vessel and includes a substantially cylindrical side wall portion and a bottom portion blocking the lower end of the side wall portion; an access window that is provided at the side wall portion of the platform unit to allow the inside of the platform unit to communicate with the nozzle stub; an access window moving device that opens and closes the access window; a working device that advances from the inside of the platform unit to the inside of the nozzle stub to perform work inside the nozzle stub; and a control device that is provided at the outside of the reactor vessel and controls the access window moving device and the working device, wherein the control device drives the access window moving device to open the access window, drives the workin

Abstract: Sealing means comprising a seal carrier and a seal connected thereto, wherein the seal carrier is removably fixable between two areas insulated from each other, and a transfer device between two chambers, which are separated by a wall, wherein said transfer device comprises a transfer mechanism and at least one sealing means according to the invention which is positioned between the wall and the transfer mechanism.

Abstract: Example embodiment damping devices may include a housing capturing a piston. The housing may be filled and/or able to be filled with a damping fluid compatible with the nuclear reactor coolant, so that a leak from the housing or coolant passing into the housing does not damage the reactor or example embodiment devices. Example embodiments may further include one or more springs that provide an elastic force opposing movement between the piston and housing. A shaft of the piston and an end of the housing may be connected to two nuclear reactor components with relative motion or vibration to be damped. Example methods may use example embodiment damping devices to reduce and/or prevent relative motion and vibration among components of a nuclear reactor.

Abstract: Control rod guide tubes for a nuclear reactor having a body with an axial length that defines a lower end portion and an upper end portion and a cavity within a substantial length of the body. Orifices are included at the upper and lower end portions of the body. A control rod chamber is located within the cavity and is configured for receiving a control rod. A plurality of ports is coupled to the cavity and is positioned at a substantial length from the upper end portion of the body. Also included are at least two flow channels within the cavity that extend a substantial portion of the axial length of the body. Each flow channel is fluidly coupled to one or more of the ports for receiving fluid flow from outside the body and an outlet proximate to the upper end portion of the body for providing the received fluid flow.

Abstract: A quick disconnect for a control rod drive mechanism seismic support tie rod system that is remotely operable from a nuclear power plant's operating deck. A wall mounted anchor in the reactor cavity contains one half of a disconnect coupling that interfaces with the other half of the disconnect coupling on the ends of the tie rods employing a remote winching system that is actuated from the top of the reactor head assembly. A latching mechanism is then actuated from the refueling cavity operating deck to lock the tie rod in place and prevent displacement during a seismic or pipe break event. The tie rod may similarly be unlocked from the wall anchor and raised above the reactor head assembly as part of a reactor head disassembly operation to gain access to the core of the reactor vessel for refueling.

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

Abstract: A system, apparatus and method of processing and/or removing radioactive materials from a body of water that utilizes the buoyancy of the water itself to minimize the load experienced by a crane and/or other lifting equipment. In one aspect, the invention is a method comprising: a) submerging a container having a top, a bottom, and a cavity in a body of water having a surface level, the cavity filling with water; b) positioning radioactive material within the cavity of the submerged container; c) raising the submerged container until the top of the containment apparatus is above the surface level of the body of water while a major portion of the container remains below the surface level of the body of water; and d) removing bulk water from the cavity while the top of the container remains above the surface level of the body of water and a portion of the container remains submerged.

Abstract: A mast arrangement having two elongate individual masts. The first elongate individual mast comprises a hollow connector comprising an inner diameter. The second elongate individual mast comprises a protruding connector end. The protruding connector end telescopically engages with the hollow connector end. The mast arrangement also comprises a pin and slot arrangement and collars to connect the masts together and minimize unwanted disengagement of the masts from each other.

Abstract: The invention relates in particular to a robot system comprising a rail track and a robot, which is designed to be displaceable in a direction of movement, guided by the rail track. According to the invention, the rail track consists of a plurality of rail track segments disposed in the direction of movement, and the robot is designed to handle such rail track segments and to extend the rail track by attaching further rail track segments to a respective last rail track segment of the existing rail track. Furthermore, according to the invention, a tension member that is attached to the robot, in particular a tension cable, is provided, which runs along the rail track, wherein a winding device for receiving the tension member is provided in order to introduce a tractive force, preferably in the region of an end of the rail track.

Abstract: A dual drive winch having a drive assembly having a first shaft that is selectively movable between a first engaged position and a first disengaged position, and a second shaft that is selectively movable between a second engaged position and a second disengaged position. When the first shaft is in the first engaged position and the second shaft is in the second engaged position simultaneously, rotation of either the first shaft or the second shaft will, through a coupling mechanism, cause rotation of the other of the first shaft and the second shaft.

Abstract: A telescoping rod control cluster assembly change tool for moving control rod assemblies among fuel assemblies in a nuclear facility. The operation of the tool is completely mechanical and the telescoping feature enables the tool to have a relatively low profile when it is being moved and stored without housing a control rod assembly. Rigidly supported alignment cards guide a gripper that attaches to the control rod assembly as the control rod assembly is withdrawn into the tool with the alignment cards preventing any lateral or rotational movement of the gripper.

Abstract: Systems and methods for dismantling a nuclear reactor are described. In one aspect the system includes a remotely controlled heavy manipulator (“manipulator”) operatively coupled to a support structure, and a control station in a non-contaminated portion of a workspace. The support structure provides the manipulator with top down access into a bioshield of a nuclear reactor. At least one computing device in the control station provides remote control to perform operations including: (a) dismantling, using the manipulator, a graphite moderator, concrete walls, and a ceiling of the bioshield, the manipulator being provided with automated access to all internal portions of the bioshield; (b) loading, using the manipulator, contaminated graphite blocks from the graphite core and other components from the bioshield into one or more waste containers; and (c) dispersing, using the manipulator, dust suppression and contamination fixing spray to contaminated matter.

Abstract: A system and a method for securely connecting, or interlocking two pole sections together to ensure that they do not disconnect during use. The system includes a tubular female end portion of the first pole section and a male end portion of the second pole section that is insertable into the female end portion. The system additionally includes a locking nut threadingly engaged with the male end portion that is rotatable on the male end portion to longitudinally transition the locking nut into contact with the female end portion to fixedly interlock the male and female end portions. Furthermore, the system includes a biased locking sleeve assembly slidably and rotatably mounted on a locking assembly portion of the second pole. The locking sleeve assembly can include a locking sleeve and a biased plunger slidingly positioned within an interior of the locking sleeve for applying a locking force to the locking nut.

Abstract: The invention refers to a method for operating a nuclear light water reactor during an operation cycle including a cardinal cycle and a number of successive control rod cycles. The reactor includes a plurality of elongated fuel units containing a nuclear fuel in the form a fissible material, a burnable absorber, and a plurality of control rods introduceable in a respective control rod position. Substantially all control rods are introduced in the core before the reactor is started and an operation cycle is initiated. The reactor is operated during the cardinal cycle with a first control rod configuration with a first group of control rods at least partly introduced and the remaining control rods extracted. The reactor is operated during the subsequent control rod cycles with a respective control rod configuration which each includes a different group of control rods at least partly introduced, wherein the cardinal cycle is substantially longer than each of the subsequent control rod cycles.

Abstract: An instrument removal system for removing detector cables from a nuclear reactor includes a removal cart and a disposal cask. in an exemplary embodiment, the removal cart includes a base including a plurality of wheels coupled thereto, a motor mounted on the base, and a drive shaft operatively coupled to the motor. A disposal spool is removably mounted on the drive shaft, and the disposal spool includes a notch sized to receive the detector cable. A housing is mounted on the base, with the housing enclosing the disposal spool. Also, an entrance port is located in the housing to permit the detector cable to enter the housing.

Abstract: Disclosed is a method for removing a thermal sleeve from a cold leg of a reactor coolant system, which enables removal of an unintentionally separated thermal sleeve without implementation of a pipe cutting operation, preventing invasion of impurities into pipes and securing reliability in repetitious welding of the pipes. In particular, the method enables a remote operation and an underwater operation using wire ropes, thus being capable of minimizing a negative effect on workers due to radiation exposure.

Abstract: Disclosed is an apparatus for removing a thermal sleeve from a cold leg of a reactor coolant system, which removes an unintentionally separated thermal sleeve without pipe cutting, preventing invasion of impurities into pipes and achieving reliable pipe re-welding. The apparatus includes a sleeve removal tool including a corn head formed at a shaft, a pressure plate below the corn head to maximize hydraulic pressure inside a safety injection pipe, a spring connected to the pressure plate to keep the pressure plate unfolded, and a guide wheel to guide the sleeve removal tool into the safety injection pipe, a horizontal movement carrier including bodies connected to each other by a link, a seating rod for seating of the sleeve removal tool, and moving wheels for movement of the horizontal movement carrier, and a vertical movement carrier including first and second anti-separation bars to prevent separation of the horizontal movement carrier.

Abstract: Maintainability of a traversing in-core probe is improved without any hindrance to passage and the like in an access tunnel in which an indexing device of a TIP system is installed. An indexing device installation unit provided in the TIP system includes: a base on which an indexing device of a traversing in-core probe used in a nuclear reactor is mounted; a holding part holding the base in a suspended state in an access tunnel formed in a nuclear reactor containment vessel; and a lift mechanism moving up and down the base held by the holding part together with the indexing device.

Abstract: An outer filter removal tool for a boiling water reactor control rod drive that uses a mechanical advantage obtained through the use of lead screw threads to pull the outer filter off of the control rod drive. Fingers on the tool are closed around the upper flange of the outer filter by sliding a collar over the outwardly biased fingers. A shaft extending through the tool is rotated which in turn extends a push plate against the control rod drive index tube causing the fingers to pull against the upper flange on the outer filter until the filter is freed from the control rod drive. The tool will hold the filter in place until affirmatively released for proper disposal.

Abstract: The invention concerns a method for repairing guide rails (27) of an assembly (10) radially maintaining a core supporting plate (5), which consists in measuring the spacing between the spans of the lateral branches of the guide rail (27) to be repaired, cutting and removing at least one lateral branch of said guide rail (27) to be repaired, measuring the dimensions of said lateral branch and machining with identical dimensions at least one substitution lateral branch, mounting and fixing said substitution lateral branch and measuring the spacing between the spans of the lateral branches of the repaired guide rail.

Abstract: A access apparatus is set on instrumentation nozzles penetrating a bottom portion of a reactor pressure vessel, in the reactor pressure vessel filling water. The access apparatus has an arm turned, and a mounting fixture that can move along the arm and having a holding member. A cover apparatus having a guide pipe covers the access apparatus, and is installed on the bottom portion in underwater environment in the reactor pressure vessel. The water below the cover apparatus is drained from the reactor pressure vessel to form an air space below the cover apparatus. A variety of device heads is suspended and lowered in the air space through the guide pipe, and mounted to the holding member of the mounting fixture. Repair or preventive maintenance operation against the instrumentation nozzles is performed by the variety of device heads.

Abstract: An electrical discharge machining (EDM) tool and method for removing tack welds on a component in a reactor pressure vessel are disclosed. The tool may include a motor, a housing which engages the component having tack welds, an electrode, positioned in the housing, a first plate, and a second plate attached to the electrode. The second plate actuates to align the electrode to the tack weld, and the electrode is discharged to remove the tack welds from the component.

Abstract: An instrument removal system for removing detector cables from a nuclear reactor includes a removal cart and a disposal cask. in an exemplary embodiment, the removal cart includes a base including a plurality of wheels coupled thereto, a motor mounted on the base, and a drive shaft operatively coupled to the motor. A disposal spool is removably mounted on the drive shaft, and the disposal spool includes a notch sized to receive the detector cable. A housing is mounted on the base, with the housing enclosing the disposal spool. Also, an entrance port is located in the housing to permit the detector cable to enter the housing.

Abstract: A vibration mitigation apparatus and method of reducing vibration in a reactor component are described, which may reduce the amplitude of vibration in the reactor component. The apparatus may be provided on the reactor component to reduce the amplitude of vibration of the component as the component and apparatus are subjected to a harmonic excitation that generally may occur during reactor operations.

Abstract: The machinery system and its application herewith, intended to create an opening in the roof of a Reactor Primary Containment of Generation II and III Nuclear Power Electric Generating Station. This opening is necessary to replace an aging nuclear reactor with a new, safer and more efficient reactor. Generation II and III Nuclear Power Electric Generating Stations include General Electric (GE) Boiling Water Reactor BWR/2, 3, 4, 5 and BWR/6 located in Mark II, and Mark III wet containments and Pressurized Water Reactors manufactured by Westinghouse, Combustion Engineering and Babcock and Wilcox located in dry containments. Until this time, existing reactor replacement was not possible due to Reactor Primary Containment structural enclosure configuration. The Dual Head Vertical Milling Machine System will remove a Reactor Primary Containment Dome Segment thus providing an opening, allowing reactor replacement and the electric generating station to remain operational for an other 40 years and beyond.

Abstract: The invention relates to a device for the sealed docking (14) of mobile containers (42) equipped with plugs (44) of various diameters on a containment box (10). The device includes a center disk (22) and at least one docking flange (20a, 20b, 20c) that are concentric to each other, normally plugging the access opening (18) of the containment box. A locking/unlocking mechanism (24) makes it possible to only unlock the center disk (22) alone or the center disk and one or more of the docking flanges (20a, 20b, 20c), according to the diameter of the plug (44). This arrangement makes it possible, in particular, to clean the plug (44) of a mobile container (42) serving to transport contaminated nuclear equipment.

Abstract: A system includes a first platform movably mounted to a first rail assembly, a second rail assembly coupled to and supported by the first platform, and a second platform movably mounted to the second rail assembly. At least one articulating arm is coupled to the second platform, and a gripping and cutting apparatus is coupled to and supported by the at least one articulating arm. An apparatus includes first and second gripping mechanisms each configured for selective actuation between positions for gripping and releasing an object, and a cutting mechanism positioned generally between the first and second gripping mechanisms, and configured to cut the object when gripped on either side by the gripping mechanisms. The system and apparatus can be used to remove feeder pipes of a nuclear reactor power plant.

Abstract: An isotope production system that includes a cyclotron having a magnet yoke that surrounds an acceleration chamber. The cyclotron is configured to direct a particle beam from the acceleration chamber through the magnet yoke. The isotope production system also includes a target system that is located proximate to the magnet yoke. The target system is configured to hold a target material and includes a radiation shield that extends between the magnet yoke and the target location. The radiation shield is sized and shaped to attenuate gamma rays emitted from the target material toward the magnet yoke. The isotope production system also includes a beam passage that extends from the acceleration chamber to the target location. The beam passage is at least partially formed by the magnet yoke and the radiation shield of the target system.

Abstract: An embodiment of the present invention takes the form of an apparatus or system that may reduce the level of vibration experienced by an inlet riser or other similar object within a reactor pressure vessel. An embodiment of the present invention may eliminate the need for welding the riser brace to the inlet riser. An embodiment of the present invention provides at least one riser brace clamp that generally clamps the riser brace to the inlet riser. After installation, the riser brace clamp may lower the amplitude of, and/or change the frequency of, the vibration experienced by the inlet riser.

Abstract: An embodiment of the present invention takes the form of an apparatus or system that may incorporate a single component to connect the control rod blade to the control rod drive system (CRD) of a Nordic-type of BWR. An embodiment of the present invention may eliminate the need of using multiple components to connect the control rod blade with the CRD.

Abstract: The invention relates to a method for the water filling and air blow-off of a main primary circuit (1) of a nuclear unit after stopping the same, said main primary circuit (1) including a tank (2) located in a pool of a reactor building (4), primary pumps (5), at least one steam generator (6) including a plurality of steam generating tubes (7) located above the level of the tank (2), and a pressuriser (8).

Abstract: A tool to slide a channel on a nuclear reactor fuel bundle assembly, the tool includes: a plate having a slot to receive a handle of the fuel bundle and a lower surface that engages an upper edge of the channel; at least one post extends up from the plate, and an arm is attached to a pivot on the post and includes a first end to receive a downward force and a second end adapted to engage the handle of the fuel bundle to apply an upward force to the handle and push down on the channel.

Abstract: A nuclear fission reactor device including a core having an array of fissile material and which is capable of being transported to and from the place of operation using conventional transportation vehicles. In a first embodiment, the fissile material is a uranium hydride enriched 15%-to-20% with U-235. In a second embodiment, the fissile material is a uranium oxide enriched to 18% to 20% with U-235.

Abstract: An instrument removal system for removing detector cables from a nuclear reactor includes a removal cart and a disposal cask. in an exemplary embodiment, the removal cart includes a base including a plurality of wheels coupled thereto, a motor mounted on the base, and a drive shaft operatively coupled to the motor. A disposal spool is removably mounted on the drive shaft, and the disposal spool includes a notch sized to receive the detector cable. A housing is mounted on the base, with the housing enclosing the disposal spool. Also, an entrance port is located in the housing to permit the detector cable to enter the housing.

Abstract: A system for exchanging a control rod drive of a nuclear reactor is provided. The system may include an integrated drive exchange assembly system (IDEAS). The IDEAS may include a trunnion cart attached to a tower assembly. The tower assembly may include an integrated extension carriage assembly. The IDEAS may also include a control rod drive adapter; and a lead cart connected to the trunnion cart assembly.

Abstract: A method of calculating and using a constraint for fuel rods is provided. The method may utilize pin nodal exposures and pin nodal powers to obtain the constraint, calculate rod average exposures and rod average powers (kW/ft) in each fuel assembly, and develop maps from the calculated rod average exposures and powers (kW/ft) to operate design, optimization, licensing, and/or monitoring applications.

Abstract: An apparatus and method for manufacturing a handling pole including a pole section, a pole adapter connected to one end of the pole section, a spade member connected to the other end of the pole section, and a nut assembly for connecting adjoining poles. The pole adapter may include an upper sleeve and the spade member may include a lower sleeve.

Abstract: A handling method for a natural circulation boiling water reactor having a chimney having cylindrical chimney shell disposed above a core in a reactor pressure vessel, a plurality of square tubes disposed in the chimney shell, and a grid support plate with grid holes supporting and in communication with a lower end portion of the square tubes so that adjacent square tubes are disposed at an interval which exceeds the width of one square tube between them. The method includes steps shifting predetermined ones of the square tubes to the interval between the square tubes, and performing maintenance and inspection of members around a core via the grid holes which appear at positions from which the predetermined square tubes are taken out due to the shift of the predetermined square tubes.

Abstract: An apparatus for inspecting a nuclear reactor may include a track, arm, fixing device, and effector. The arm may be operatively connected to the track, the fixing device may be operatively connected to the track, and the effector may be operatively connected to the arm. The arm may have contracted and expanded lengths. The expanded length may be greater than two times the contracted length. The track may include one or more motors adapted to move the arm relative to the track. A method of inspecting, performing maintenance on, or repairing a reactor may include: operatively connecting a fixing device, track, arm, and effector to form an apparatus; inserting the apparatus into the reactor; fixing the apparatus within the reactor; and operating the apparatus. A method of operating a reactor may include shutting down; inspecting, performing maintenance on, or repairing the reactor; and starting up the reactor.

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: Welding repairs are performed in an underwater environment adjacent the bottom head of the nuclear reactor vessel. To provide a dry welding environment, segments of a lower caisson are passed through the core plate holes and assembled along the interior surface of the bottom head. The assembled segments are held down by brackets and sealed to one another and to the bottom head by a water curable polymer. An upper caisson is passed through the core plate hole to sealingly engage the lower caisson. The caissons are pumped dry and welding equipment is passed through the caissons to effect weld repairs about the stub tube or along the bottom head cladding.

Abstract: A preventive maintenance/repair device 10 of the present invention includes: a device body 11, and holding mechanisms 13a and 13b connected to the device body 11, the holding mechanisms 13a and 13b being configured to hold the device body 11 on an outer circumferential surface of a cylindrical structure 19. Further, the device body 11 is equipped with a traveling and driving part configured to be circumferentially movable along the outer circumferential surface of the cylindrical structure 19. Furthermore, each of the holding mechanisms 13a and 13b is equipped with a maintenance/repair mechanism 16 configured to maintain and repair the cylindrical structure 19.

Abstract: A working apparatus has: a working equipment for doing works on a structure; a folding/unfolding mechanism for conveying the working equipment to the working position in a folded state; a conveyance mechanism (such as a horizontal thruster) for conveying the working equipment and the folding/unfolding mechanism to the working position; a pressing mechanism (such as a ballast tank) for pressing the working equipment against the lower surface of the structure; and a traveling mechanism including a wheel for traveling along the lower surface of the structure and positioning the apparatus.

Abstract: A method for executing water jet peening for giving an impact force to a surface of a structure member by a crushing pressure of a water jet and cavitation and improving residual stress, or washing, or reforming said surface, wherein said water jet peening is executed so as to make a natural frequency of oscillation of said structure member and a excitation frequency of oscillation of water jet peening different from each other.

Abstract: A method for delivery of a tool into a submerged bore includes controlling the movement of a tool delivery device in the pool by operating at least one propulsion drive located on the tool delivery device. The tool delivery device is coupled to an inlet to the bore and a tool is inserted from the tool delivery device through the inlet and into the bore.

Abstract: A system and method for storing multiple canisters containing high level waste below grade that afford adequate ventilation of the spent fuel storage cavity. In one aspect, the invention is a system comprising: an air-intake shell forming a substantially vertical air-intake cavity; a plurality of storage shells, each storage shell forming a substantially vertical storage cavity; a hermetically sealed canister for holding high level waste positioned in one or more of the storage cavities so that a gap exists between the storage shell and the canister, the horizontal cross-section of each of the storage cavities accommodating no more than one canister; a removable lid positioned atop each of the storage shells so as to form a lid-to-shell interface, each lid containing an outlet vent forming passageways between an ambient environment and the storage cavity; and a network of pipes forming a passageway between a bottom portion of the intake cavity and a bottom portion of each of the storage cavities.

Abstract: Sealing means comprising a seal carrier and a seal connected thereto, wherein the seal carrier is removably fixable between two areas insulated from each other, and a transfer device between two chambers, which are separated by a wall, wherein said transfer device comprises a transfer mechanism and at least one sealing means according to the invention which is positioned between the wall and the transfer mechanism.