64results about "Facility decommissioning" patented technology

Nuclear reactor vessel segmenting utilizing improved arc saw systems and methods.

The invention concerns a method of providing a seal within a pipe or aperture in a vessel and preventing fluid flow therethrough, the method comprising: (a) providing a non-porous, expandable, flexible container within said pipe or aperture; (b) introducing an expandable polymeric material into said container so as to expand said container, thereby forcing said container to fill the cross-sectional area of said pipe or aperture and displacing any fluid in said pipe or aperture in order to provide an engineered blockage within said pipe or aperture; (c) applying a bonding resin between the external surfaces of said container and the internal surfaces of the walls of said pipe or aperture; and (d) curing said expandable polymeric material and bonding resin so as to bond the expanded container to the pipe or aperture and create a seal between the outer surfaces of said container and the internal surfaces of the walls of said pipe or aperture. The method finds particular application in the prevention aqueous liquid flow through pipework and in environments contaminated with radioactivity. It is simple and cost effective to employ.

A nuclear radiation protective tent assembly (10) for intervention by an operator (2) on a glove box (1), said tent assembly comprising at least one leak tight envelope (4) and an outer support (11), said envelope being formed by at least one flexible sheet and being provided with at least one access opening (15), said envelope being mounted on said outer support (11), said tent assembly further comprises an outer transparent shielding panel (7) provided to be placed peripheral to said envelope, said shielding panel having at least one further access opening (9) for enabling said operator to have access via said at least one access opening to an inner space of said envelope, said panel being provided for shielding said operator (2) against nuclear radiation, said outer support being provided with means for holding said shielding panel (15).

A method is provided for removing radioactive internals structural members in the core of a reactor pressure vessel in a containment vessel. The method includes placing a first cask in a first internals assembly, detaching radioactive first internals structural members from second internals structural members of the first internals assembly, placing the detached first internals structural members in the first cask, placing the first internals assembly in a second cask, and removing the second cask containing the first internals assembly and containing the casked detached radioactive first internals members from the containment vessel. The first internal members may be radioactive baffle plates, and the second internals members may be former plates bolted to the radioactive baffle plates. Novel tooling, framework and fixtures facilitate disassembling, moving and storing the radioactive baffle plates.

The present invention relates to a remote dismantling system for a nuclear power plant. The remote dismantling system comprises: a transfer system for transferring an object to be cut, the object being placed on one side of the transfer system; and a parallel vertical rail robot arm system arranged within the movement radius of the transfer system and comprising a cutting robot arm for cutting the object to be cut. The transfer system comprises a gantry crane and a jib crane which are arranged to be movable across each other and transfer the object to be cut. The parallel vertical rail robot arm system comprises a transfer robot arm arranged to be vertically movable along with the cutting robot arm in order to transfer finely cut pieces which have been cut from the object to be cut.

A mobile melting device for consolidating contaminated scrap and to a corresponding method. The melting device has a crucible chamber and a crucible base. The crucible is arranged on the crucible base during operation, and the crucible base and the crucible chamber together form a gas-tight furnace housing. It is thus possible to carry out the method in a vacuum or under protective gas such that even a reactive material can be consolidated. The melting device can be assembled and disassembled with little effort.

The invention relates to an optimized laser cutting method for cutting a part from a material by means of a cutting system comprising: a laser source for producing a laser beam having a certain power; and a cutting head comprising an end nozzle for passage of a cutting laser beam, wherein the method comprises: determining a cutting power Pd such that Pd=Max(Popt;λe) where Max is the mathematical operator of the maximum, Popt is an optimal power of the laser beam of the cutting system, which is predetermined in accordance with the part to be cut, and/or with cutting parameters and/or with system parameters, in order to minimize the amount of aerosols produced when the part is cut, λ is a leading coefficient representing the number of kW required for cutting the part per mm of the thickness of the part, and e is the thickness of the part in mm.

A method of reducing the volume of a blade section of a boiling water reactor control rod for transport or storage that cuts the control rod spline into four substantially equal longitudinal sections, with each longitudinal section including one control rod blade. Each longitudinal section is radiologically characterized and the locations of desired lateral segmentation are identified. A band of malleable metal is wrapped around each longitudinal section at each of the locations and the bands are sheared to separate segments of the longitudinal section and the ends of the bands are crimped at the point of shearing to seal the interior of the segments.

A mobile system for intervention in an atmosphere of radioactive gas, notably tritium, which, includes; a dynamic confinement device, including & removable confinement barrier to surround an intervention, zone and a device for controlled extraction of air to keep the zone at a lower pressure than the exterior; a device for monitoring the radioactive gas concentration in the air of the zone; a device to detect and signal the exceedance of a predefined threshold by this concentration to the persons present in the zone.

A method for decommission of a nuclear power plant includes: a step of removing fuel from a reactor vessel and storing the fuel in a fuel storage pool; a step of carrying the fuel out from the fuel storage pool; a step of, after removing the fuel from the reactor vessel, taking a reactor internal structure inside the reactor vessel out to a work pool storing water and being positioned above the reactor vessel, and decommissioning the reactor internal structure under the water stored in the work pool; a step of carrying the decommissioned reactor internal structure out from the work pool; and a step of, after carrying the reactor internal structure out from the work pool, draining the water from the work pool. The step of taking out and decommissioning the reactor internal structure is started before completion of carrying out of the fuel from the fuel storage pool.

The invention relates to an optimized laser cutting method for cutting a part from a material by means of a cutting system comprising: a laser source for producing a laser beam having a certain power; and a cutting head comprising an end nozzle for passage of a cutting laser beam, said method being characterized in that it comprises a step of determining the cutting power Pd such that: Pd=Max(Popt;λe) where Max is the mathematical operator of the maximum, Popt is an optimal power of the laser beam of the cutting system, which is predetermined in accordance with the part to be cut, and/or with cutting parameters and/or with system parameters, to minimize the mass defect per unit length of the part when the part is being cut, λ is a leading coefficient representing the number of kW required for cutting the part per mm of the thickness of the part, and e is the thickness of the part in mm.

The invention relates to an emergency ventilation system for a nuclear facility master control room. The emergency ventilation system comprises a high-pressure air storage device and a conveying pipeline, wherein the high-pressure air storage device is used for storing high-pressure compressed air, one end of the conveying pipeline is connected with the high-pressure air storage device located outside the main control room, the other end of the conveying pipeline is connected with an air outlet located in the main control chamber, the conveying pipeline comprises a passive valve located in themain control chamber, and the emergency ventilation system further comprises a pressure relief device used for relieving pressure of the main control chamber. According to the emergency ventilation system, power support does not needed, the risk of retention loss of the master control room is reduced, and the safety coefficient and reliability of the ventilation system of the master control roomare enhanced.

There is provided a method for decommissioning plan of nuclear facility includes receiving a plurality of decommissioning related information data, and determining whether error data is included in the plurality of decommissioning related information data based on a database which contains characteristic information and decommissioning plan information of a plurality of nuclear facilities. The method further includes analyzing a state of a decommissioning target facility by identifying the decommissioning target facility based on the plurality of decommissioning related information data and the database, wherein when the error data is included in the plurality of decommissioning related information data, said analyzing is performed by identifying the decommissioning target facility based on the plurality of decommissioning related information data from which the error data is excluded and the database. The method further includes designing a decommissioning plan of the decommissioning target facility based on the analyzed state.

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

A heavy-water reactor facility dismantling apparatus according to an embodiment includes: a first cutting device for cutting the periphery of a first nozzle portion of a calandria, wherein the first nozzle portion is connected to the upper end of a first pipe positioned in the calandria of a heavy-water reactor facility; a second cutting device for cutting a first support part of the calandria, wherein the first support portion is connected to the lower end of the first pipe connected to the first nozzle portion; and a fixing and drawing device for fixing and drawing the first nozzle portion cut by the first cutting device.

The invention discloses an underground nuclear power plant having a low-and-intermediate-level radioactive waste disposal site. The underground nuclear power plant comprises a nuclear island arranged in an underground cavern group of a nuclear island of a mountain and a conventional island arranged on a ground platform at the outer side of the mountain. The nuclear island consists of a reactor workshop arranged at the center, a nuclear fuel workshop, a safety workshop, an electrical workshop, and a nuclear auxiliary workshop, wherein the nuclear fuel workshop, the safety workshop, the electrical workshop, and the nuclear auxiliary workshop encircle the reactor workshop. And the nuclear island also includes a low-and-intermediate-level radioactive waste disposal site arranged in the underground cavern group of the nuclear island of the mountain; and the low-and-intermediate-level radioactive waste disposal site is communicated with the nuclear auxiliary workshop of the nuclear island by a waste transport tunnel. According to the invention, on the basis of combination of characteristics of the underground nuclear power plant, the processing requirement of the low-and-intermediate-level radioactive waste can be met, the closed circulation of fuels can be realized, and the radioactive contamination possibly occurring during the fuel cycle process can be reduced; and the unified planning and building of the nuclear power plant and the disposal site can be realized and costs are saved.

A safety cover structure of a nuclear facility is disclosed. The safety cover structure of a nuclear facility includes: a cover portion rotatably provided over body protection concrete so as to cover a cavity in which a reactor pressure container is positioned; a driving part for providing rotational driving power to the cover part; an opening and closing portion provided at the cover portion and thus products from the cutting and dismantling of the reactor pressure contain move therethrough; a fire extinguishing portion for extinguishing a fire occurring inside the cover portion; a radiation sensor which is provided on the cover portion and which measures radiation dose; and an alarming portion, which receives a sensing signal of the radiation sensor so as to issue an alert when radiation greater than or equal to a predetermined value is discharged from the reactor pressure container.

The invention discloses an automatic pretreatment device and method for liquid effluent 14C of a nuclear power plant, and the device comprises a cracking furnace, a condensation tank, a filter and an absorption bottle, the cracking furnace is used for instantly gasifying liquid effluent sample water of the nuclear power plant into mixed gas of 14CO2 and tritiated water vapor under the assistance of high-purity oxygen and a catalyst at the temperature of 790-810 DEG C; the condensing tank is used for condensing the mixed gas so as to separate out 14CO2 carrying residual tritiated water vapor; the filter is used for filtering the residual tritiated water vapor in the 14CO2 carrying the residual tritiated water vapor to obtain filtered 14CO2, and the 3H residual rate in the filtered 14CO2 is lower than 0.001%; and the absorption bottle is used for containing a NaOH solution so as to absorb the filtered 14CO2, so that an absorption solution is obtained. Unification of automation and accuracy can be realized.

The invention discloses a passive ventilation device which comprises a compressed air storage tank used for storing compressed air; the vortex tube is connected with the compressed air storage tank, the vortex tube is used for generating vortexes by the compressed air to separate cold airflow and hot airflow, and the vortex tube comprises a vortex tube body, a vortex tube hot end and a vortex tube cold end, and the vortex tube hot end and the vortex tube cold end are arranged on the vortex tube body; the purification mechanism is connected with the hot end of the vortex tube, and the purification mechanism is used for purifying air in the resident area through the hot airflow separated from the hot end of the vortex tube and then sending the purified air into the resident area; and the ventilation mechanism is connected with the cold end of the vortex tube, and the ventilation mechanism is used for feeding the cold air flow separated from the cold end of the vortex tube into the resident area, providing fresh air and cooling for the resident area and maintaining the positive pressure of the area. According to the ventilation device, compressed air is separated into cold air flow and hot air flow through the vortex tube, and power is provided for the ventilation mechanism and the purification mechanism through the pressure of the compressed air.

A method for complex-decommissioning a nuclear facility is disclosed. The method for complex-decommissioning the nuclear facility includes: cutting and expanding an inner wall of the cavity; installing a cutting device that cuts and decommissions the nuclear reactor pressure vessel inside the cavity; fixing the nuclear reactor pressure vessel inside the cavity by using a fixture; and cutting and decommissioning the nuclear reactor pressure vessel fixed inside the cavity by using a cutting device.