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64results about "Facility decommissioning" patented technology
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Systems and methods for nuclear reactor vessel segmenting
ActiveUS20160336084A1Arc welding apparatusNuclear engineering solutionsNuclear reactor coreNuclear reactor
Owner:LAGUARDIA & ASSOC LLC
Method and tooling for dismantling, casking and removal of nuclear reactor core structures
ActiveUS7668281B2Increasing the thicknessReduce radiation levelsNuclear energy generationFacility decommissioningNuclear reactor coreNuclear reactor
Owner:WESTINGHOUSE ELECTRIC CORP
Tube cutting device having conical fitting member to cut tube of waste steam generator
ActiveCN106891061AFreedom from radioactive contaminationMetal sawing devicesNuclear energy generationTransmitted powerGuide tube
A tube cutting device for cutting a tube of a waste steam generator including: a body configured to transmit power; a tube-shaped rotary body provided on a side surface of the body and having a horizontal rotary shaft configured to rotate with the power supplied from the body; a plurality of clamps provided along an outer peripheral surface of a first end portion of the rotary body and configured to fix the rotary body to the tube to be cut; a saw provided on a second end portion opposite to the first side end portion of the rotary body and configured to rotate together with the rotary body to cut the tube; and a fitting member configured to be inserted into a hollow portion formed on a center portion of the saw.
Owner:DOOSAN HEAVY IND & CONSTR CO LTD
Sealing means
InactiveUS20110006482A1Satisfactory performanceSleeve/socket jointsFluid pressure sealed jointsCost effectivenessRadioactive contamination
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.
Owner:NUCLEAR DECOMMISSIONING AUTHORITY
Shielded protective tent assembly
InactiveCN102831944ALow risk of releaseReduce generationNuclear engineering problemsFacility decommissioningInterior spaceNuclear radiation
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).
Owner:BELGONUCLEAIRE SA
Method and tooling for dismantling, casking and removal of nuclear reactor core structures
ActiveUS20090285345A1Reduce radiation levelsContact level can be reducedNuclear energy generationFacility decommissioningNuclear reactor coreNuclear reactor
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.
Owner:WESTINGHOUSE ELECTRIC CORP
Remote dismantling system for nuclear power plant and nuclear power plant having same
PendingUS20210210236A1Improve securityReduce addNuclear energy generationFacility decommissioningNuclear plantControl engineering
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.
Owner:KOREA ATOMIC ENERGY RES INST
Melting device for consolidating contaminated scrap
ActiveUS20150380118A1Reduce transportationLower the volumeCrucible furnacesFacility decommissioningScrapReactive material
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.
Owner:ALD VACUUM TECH
Laser Cutting Method Optimized In Terms Of The Amount of Aerosols
ActiveUS20140054274A1Satisfactory robustnessMinimal pressureFacility decommissioningLaser beam welding apparatusMathematical OperatorsEngineering
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.
Owner:COMMISSARIAT A LENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES
Method of segmenting irradiated boiling water reactor control rod blades
ActiveUS20130074302A1Reduce storageNuclear energy generationNuclear engineering problemsControl rodBoiling water reactor
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.
Owner:WESTINGHOUSE ELECTRIC CORP
Mobile system for intervention in an atmosphere of radioactive gas, notably tritium
ActiveUS20130008314A1Reduce pressureHigh trafficCombination devicesAuxillary pretreatmentRadioactive gasRadioactive waste
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.
Owner:COMMISSARIAT A LENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES
Systems and methods for nuclear reactor vessel segmenting
Owner:LAGUARDIA & ASSOC LLC
Method for decommissioning nuclear power plant
InactiveUS20180190400A1Reduce maintenance costsLow costNuclear energy generationNuclear engineering problemsNuclear powerNuclear engineering
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.
Owner:MITSUBISHI HEAVY IND LTD
Laser cutting method optimized in terms of mass defect per unit length
ActiveUS20130299473A1Minimise Mp defectOverall light weightFacility decommissioningLaser beam welding apparatusMathematical OperatorsSpray nozzle
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.
Owner:COMMISSARIAT A LENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES
Machinery system allowing replacement of old reactor with a new reactor in nuclear power electric generating station
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. Original containment integrity will be reinstated by closure of the opening.
Owner:JUGL JOHN
Method and device for controlling the dynamic confinement of an enclosure
InactiveUS20150013473A1Quality assuranceAvoid contamination riskNuclear energy generationNuclear monitoringDifferential pressureAlarm signal
The invention relates to a method and device for monitoring the confinement of an enclosure including walls delimiting an interior volume and an external environment, according to which a differential pressure (ΔP) is maintained between the interior volume and the external environment. According to the invention, the enclosure includes a port in one of the walls thereof establishing a fluid communication between the interior volume and the external environment, the port is traversed by a gas stream having a speed (V) at least equal to a reference speed Vréf, under the effect of the differential pressure (ΔP). Method according to which the following steps are performed, measuring the speed (V) of the gas stream at predetermined time intervals or continuously, and comparing the speed (V) measurement with reference speed Vréférence, and when the speed (V) measurement is less than reference speed Vréférence, transmitting at least one alarm signal.
Owner:COMMISSARIAT A LENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES
Decommissioning method of biodegradable concrete of pwr type nuclear power plant
ActiveUS20210158981A1Reduce processing timeMinimizationNuclear energy generationNuclear monitoringNuclear reactorNuclear chemistry
A decommissioning method of biodegradable concrete of a nuclear power plant according to an exemplary embodiment includes: decommissioning a neutron detector positioning device installed to biodegradable concrete surrounding a nuclear reactor to form a plurality of penetrated parts in the biodegradable concrete; inserting a part of a cutting device into the plurality of penetrated parts; and decomposing the biodegradable concrete into a plurality of sub-concrete parts by using the cutting device.
Owner:KOREA HYDRO & NUCLEAR POWER CO LTD
Emergency ventilation system for nuclear facility master control room
InactiveCN112283841ARealize cycle purificationQuality assuranceMechanical apparatusLighting and heating apparatusNuclear engineeringControl room
Owner:SANMEN NUCLEAR POWER CO LTD
Method and apparatus for decommissioning plan of nuclear facility
InactiveUS20200242558A1Ensure reliabilityEnsure safetyNuclear energy generationFacility decommissioningData packEngineering
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.
Owner:KOREA ATOMIC ENERGY RES INST
Efficient filtering lower tube seat, fuel assembly and nuclear reactor
InactiveCN113362976AReduce deflectionPromote circulationNuclear energy generationFacility decommissioningForeign matterNuclear reactor
The invention discloses an efficient filtering lower tube seat, a fuel assembly and a nuclear reactor. The lower tube seat is composed of a connecting plate and supporting legs; the connecting plate is designed into square grids which are densely and regularly arranged, an S-shaped curved surface array is adopted in the grids to form a flow channel for filtering foreign matters, and straight ribs are adopted to divide the S-shaped curved surface array into single completely-closed flow channels. The flow channel of the lower tube seat is composed of the S-shaped curved surface array, the filtering effect and the circulation effect are good, and compared with a C-shaped curved surface, the S-shaped curved surface is small in deflection and better in circulation capacity and deformation resistance capacity; a long flow guide section is reserved at the upper end of a S-shaped curved flow channel, so that the water flow direction at the outlet is consistent.
Owner:NUCLEAR POWER INSTITUTE OF CHINA
Nuclear reactor decommissioning system
ActiveUS20210183531A1Convenient lengthMinimizeNuclear energy generationFacility decommissioningNuclear reactorAtomic physics
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.
Owner:KOREA HYDRO & NUCLEAR POWER CO LTD
Laser cutting method optimized in terms of mass defect per unit length
ActiveUS9399270B2Overall light weightEase of evacuationFacility decommissioningLaser beam welding apparatusMathematical OperatorsLaser cutting
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.
Owner:COMMISSARIAT A LENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES
Aparatus and method for dismantling for heavy water reactor facilities
PendingUS20220068514A1Easy to dismantleEasy to liftNuclear energy generationFacility decommissioningProcess engineeringMechanical engineering
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.
Owner:KOREA HYDRO & NUCLEAR POWER CO LTD
Underground nuclear power plant having low-and-intermediate-level radioactive waste disposal site
ActiveCN106128534ASave design and construction costsAvoid radioactive releaseNuclear energy generationFacility decommissioningNuclear plantCyclic process
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.
Owner:CHANGJIANG SURVEY PLANNING DESIGN & RES
Safety cover structure of nuclear facility
PendingUS20220148749A1Effective fire extinguishingAvoid excessive radiationNuclear energy generationFire rescueNuclear engineeringRadiation sensor
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.
Owner:KOREA HYDRO & NUCLEAR POWER CO LTD
Automatic pretreatment device and treatment method for liquid effluent 14C of nuclear power plant
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.
Owner:TSINGHUA UNIV
Passive ventilation device
PendingCN114688651ASolution is not availableReduce infiltrationMechanical apparatusCompression machinesCold airFresh air
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.
Owner:CHINA NUCLEAR POWER ENG CO LTD
Stand-alone storage system for spent fuel storage during decommissioning of nuclear power plants
An independent storage system for spent fuel storage during nuclear power plant decommissioning comprises: an independent storage space, obtained by modifying a nuclear power plant into a separate building; a spent fuel storage tank, arranged in the separate storage space and configured to store spent fuel; a cooling system disposed in the separate storage space and configured to remove decay heatgenerated from spent fuel; a purification system disposed in the separate storage space, and configured to purify water in a spent fuel storage tank; and a cooling water supply system disposed in theseparate storage space and configured to supply cooling water to the cooling system, wherein the cooling system, the purification system, and the cooling water supply system only perform the functionfor storing spent fuel in the spent fuel storage tank, and the cooling system, the purification system, and the cooling water supply system are arranged in the same building in which the spent fuel tank is arranged.
Owner:KOREA ELECTRIC POWER CORP
Protective and disposable envelope-like intervention tent
InactiveCN102852375BFirmly connectedTents/canopiesFacility decommissioningEngineeringUltimate tensile strength
Owner:BELGONUCLEAIRE SA
Complex decommissioning method for nuclear facility
PendingUS20220165439A1Cutting stabilityShort working hoursMetal sawing devicesPlaning/slotting machinesNuclear reactorAtomic physics
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.
Owner:KOREA HYDRO & NUCLEAR POWER CO LTD
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