Systems and methods for decontaminating a surface comprising radioactive contamination are provided. The system comprises an ablation chamber which includes a body defining a receptacle for receiving a laser head and an opening for positioning over the surface. The receptacle and the laser head are configured to direct a laser to the surface and to ablate the radioactive contamination into ablation products. A support may position the body above the surface and define a gap between the body and the surface. A suction blower is in fluid communication with the ablation chamber and is configured to provide a vacuum within the ablation chamber to move the ablation products from the ablation chamber to a filtration system. The filtration system filters the particles from air as it moves from the ablation chamber to the outlet.
01 - Chemical and biological materials for industrial, scientific and agricultural use
09 - Scientific and electric apparatus and instruments
11 - Environmental control apparatus
35 - Advertising and business services
37 - Construction and mining; installation and repair services
40 - Treatment of materials; recycling, air and water treatment,
42 - Scientific, technological and industrial services, research and design
Goods & Services
Moderating materials for nuclear reactors; heavy water; fuel for nuclear reactors. Safeguard systems, namely surveillance cameras, radiation sensors and detectors, seals (mechanical, fibre optic or electronic), and associated instrumentation to monitor the movement of nuclear material to detect the removal of nuclear material from designated storage locations. Nuclear reactors; installations for processing nuclear fuel and nuclear moderating material; parts and fittings for all of the aforesaid. Procurement services in the field of nuclear reactors. Construction maintenance and repair services in the field of nuclear reactors; consulting services in the field of nuclear reactor construction. Nuclear reactor decontamination services. Material testing services in the field of nuclear reactor design, research and development, and in-service inspection; nuclear reactor engineering project management services.
01 - Chemical and biological materials for industrial, scientific and agricultural use
09 - Scientific and electric apparatus and instruments
11 - Environmental control apparatus
35 - Advertising and business services
37 - Construction and mining; installation and repair services
40 - Treatment of materials; recycling, air and water treatment,
42 - Scientific, technological and industrial services, research and design
Goods & Services
Moderating materials for nuclear reactors; heavy water; fuel for nuclear reactors. Safeguard systems, namely surveillance cameras, radiation sensors and detectors, seals (mechanical, fibre optic or electronic), and associated instrumentation to monitor the movement of nuclear material to detect the removal of nuclear material from designated storage locations. Nuclear reactors; installations for processing nuclear fuel and nuclear moderating material; parts and fittings for all of the aforesaid. Procurement services in the field of nuclear reactors. Construction maintenance and repair services in the field of nuclear reactors; consulting services in the field of nuclear reactor construction. Nuclear reactor decontamination services. Material testing services in the field of nuclear reactor design, research and development, and in-service inspection; nuclear reactor engineering project management services.
01 - Chemical and biological materials for industrial, scientific and agricultural use
09 - Scientific and electric apparatus and instruments
11 - Environmental control apparatus
37 - Construction and mining; installation and repair services
40 - Treatment of materials; recycling, air and water treatment,
42 - Scientific, technological and industrial services, research and design
45 - Legal and security services; personal services for individuals.
Goods & Services
(1) Moderating materials for nuclear reactors; heavy water; fuel for nuclear reactors
(2) Safeguard systems, namely surveillance cameras, radiation sensors and detectors, seals (mechanical, fibre optic or electronic), and associated instrumentation to monitor the movement of nuclear material to detect the removal of nuclear material from designated storage locations
(3) Nuclear reactors; installations for processing nuclear fuel and nuclear moderating material; parts and fittings for all of the aforesaid (1) Procurement, commissioning, operation and decommissioning services in the field of nuclear reactors
(2) Construction maintenance and repair services in the field of nuclear reactors
(3) Nuclear reactor decontamination services
(4) Material testing services in the field of nuclear reactor design, research and development, and in-service inspection; nuclear reactor project management services; consulting services in the field of nuclear reactor construction
5.
Method and apparatus for filtering fluid in nuclear power generation
A filtering apparatus for a fluid intake of a nuclear power generation facility comprise primary and secondary frames. The primary frame defines an enclosed volume having least one inlet opening, and at least one outlet opening in fluid communication with the fluid intake. A primary filter is supported on the primary frame and covers the inlet opening such that fluid passes into the enclosed volume through the primary filter. The secondary frame is located within the volume enclosed by the primary frame. A secondary filter is supported on the secondary frame and defines an enclosed flow passage in communication with the outlet opening, such that fluid passes into the at least one outlet opening through the secondary filter and the enclosed flow passage.
B01D 29/07 - Filters with filtering elements stationary during filtration, e.g. pressure or suction filters, not covered by groups Filtering elements therefor with flat filtering elements supported with corrugated, folded or wound filtering sheets
B01D 29/56 - Filters with filtering elements stationary during filtration, e.g. pressure or suction filters, not covered by groups Filtering elements therefor with multiple filtering elements, characterised by their mutual disposition in series connection
G21C 19/307 - Arrangements for introducing fluent material into the reactor coreArrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products specially adapted for liquids
A portable testing device and method for measuring physical characteristics of a polymeric or elastomeric material is provided. The testing device includes an indenter probe; a drive system for controlling movement of said probe, said drive system comprising a motorized linear slide operatively associated with the probe to advance said probe from a first position to a second position to deform said polymeric or elastomeric material and to facilitate instant or fast retraction of said probe to a predetermined intermediate position between said first and second positions; and a force/displacement measurement system including a first sensor for measuring force at the tip of said probe during contact with said polymeric or elastomeric material and a second sensor for measuring displacement of the probe; and a controller configured to provide control to the force/displacement measurement system and the drive system.
A portable testing device and method for measuring physical characteristics of a polymeric or elastomeric material is provided. The testing device includes an indenter probe; a drive system for controlling movement of said probe, said drive system comprising a motorized linear slide operatively associated with the probe to advance said probe from a first position to a second position to deform said polymeric or elastomeric material and to facilitate instant or fast retraction of said probe to a predetermined intermediate position between said first and second positions; and a force/displacement measurement system including a first sensor for measuring force at the tip of said probe during contact with said polymeric or elastomeric material and a second sensor for measuring displacement of the probe; and a controller configured to provide control to the force/displacement measurement system and the drive system.
A portable testing device and method for measuring physical characteristics of a polymeric or elastomeric material is provided. The testing device includes an indenter probe; a drive system for controlling movement of said probe, said drive system comprising a motorized linear slide operatively associated with the probe to advance said probe from a first position to a second position to deform said polymeric or elastomeric material and to facilitate instant or fast retraction of said probe to a predetermined intermediate position between said first and second positions; and a force/displacement measurement system including a first sensor for measuring force at the tip of said probe during contact with said polymeric or elastomeric material and a second sensor for measuring displacement of the probe; and a controller configured to provide control to the force/displacement measurement system and the drive system.
A seal assembly for a pump comprises a gland housing mounted to the pump casing. A staging flow pathway is defined within the gland housing with multiple seal chambers. A seal stage is positioned in each seal chamber, each having a static sealing element and a rotating sealing element, the sealing elements engaging one another to form a fluid-tight seal. A rotor assembly pumps coolant through the gland housing. Fluid passing through the staging flow pathway is accelerated by an acceleration surface of the rotor assembly. An inlet passage feeds coolant fluid into the staging flow pathway and past the acceleration surface.
F16J 15/34 - Sealings between relatively-moving surfaces with slip-ring pressed against a more or less radial face on one member
G21C 15/04 - Arrangement or disposition of passages in which heat is transferred to the coolant, e.g. for coolant circulation through the supports of the fuel elements from fissile or breeder material
G21C 15/243 - Promoting flow of the coolant for liquids
F04D 29/16 - Sealings between pressure and suction sides
10.
Methods and apparatus for repairing a tubular structure
Apparatuses and methods for repairing a defect in a nuclear reactor are provided. The apparatus includes a body for insertion in a tubular structure, the body includes: an end effector having a weld torch operable to deposit weld material by forming molten weld droplets and depositing the weld droplets the tubular structure. A drive unit includes a brace for selectively anchoring against said tubular structure; at least one linear actuator for moving the apparatus relative to the brace; and a rotational actuator coupled to rotate the weld torch. The method includes inserting a repair apparatus into tubular structure of the nuclear reactor; moving the repair apparatus to a defect location; depositing a protective weld layer over the defect by sequentially depositing weld droplets atop a weld pool on the tubular structure, wherein the protective weld layer bonds to the tubular structure surrounding the defect.
Methods and systems for cleaning inner surfaces of tubes in a heat exchanger. Some systems include a cleaning device having a nozzle configured to inject cleaning fluid into first and second tubes to perform different first and second cleaning cycles on the tubes, respectively, a controller configured to determine delivery parameters for the cleaning cycles based on a characteristic of each tube, and to control the cleaning device to perform the cleaning cycles based on the delivery parameters. Some methods include determining, with a controller, a tube in the heat exchanger engaged with a nozzle of a cleaning device for injecting a cleaning fluid into the tube during a cleaning cycle, a characteristic of the tube, and a delivery parameter of the cleaning cycle for the tube based on the characteristic of the tube; and performing the cleaning cycle for the tube based on the delivery parameter.
B24C 3/32 - Abrasive blasting machines or devicesPlants designed for abrasive blasting of particular work, e.g. the internal surfaces of cylinder blocks
A gas-based reactivity control system for a nuclear reactor. The system control reactivity of a nuclear reactor by injecting pressurized neutron absorbing gas into gas tubes that are positioned inside a reactor core. Injector tanks are filled with the neutron absorbing gas. Upon detection of a reactivity control trigger, the fluid communication channels between the injector tanks and the gas tubes are opened. The pressure differential between the injection tanks and the gas tubes causes the neutron absorbing gas to flow into the gas tubes, thereby introducing negative reactivity into the reactor core. The negative reactivity may be introduced into the core relatively quickly, compared to conventional systems. The gas may be left in the gas tube to keep the reactor shut down. The gas in the gas tubes may be vented in a controlled manner to control reactivity increase in the core when restarting the reactor.
G21C 7/22 - Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of a fluid or fluent neutron-absorbing material
G21C 9/033 - Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse by an absorbent fluid
A gas-based reactivity control system for a nuclear reactor. The system control reactivity of a nuclear reactor by injecting pressurized neutron absorbing gas into gas tubes that are positioned inside a reactor core. Injector tanks are filled with the neutron absorbing gas. Upon detection of a reactivity control trigger, the fluid communication channels between the injector tanks and the gas tubes are opened. The pressure differential between the injection tanks and the gas tubes causes the neutron absorbing gas to flow into the gas tubes, thereby introducing negative reactivity into the reactor core. The negative reactivity may be introduced into the core relatively quickly, compared to conventional systems. The gas may be left in the gas tube to keep the reactor shut down. The gas in the gas tubes may be vented in a controlled manner to control reactivity increase in the core when restarting the reactor.
G21C 7/22 - Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of a fluid or fluent neutron-absorbing material
G21C 9/033 - Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse by an absorbent fluid
A seal assembly for a pump comprises a gland housing mounted to the pump casing. A staging flow pathway is defined within the gland housing with multiple seal chambers. A seal stage is positioned in each seal chamber, each having a static sealing element and a rotating sealing element, the sealing elements engaging one another to form a fluid-tight seal. A rotor assembly pumps coolant through the gland housing. Fluid passing through the staging flow pathway is accelerated by an acceleration surface of the rotor assembly. An inlet passage feeds coolant fluid into the staging flow pathway and past the acceleration surface.
A seal assembly for a pump comprises a gland housing mounted to the pump casing. A staging flow pathway is defined within the gland housing with multiple seal chambers. A seal stage is positioned in each seal chamber, each having a static sealing element and a rotating sealing element, the sealing elements engaging one another to form a fluid-tight seal. A rotor assembly pumps coolant through the gland housing. Fluid passing through the staging flow pathway is accelerated by an acceleration surface of the rotor assembly. An inlet passage feeds coolant fluid into the staging flow pathway and past the acceleration surface.
Apparatuses and methods for repairing a defect in a nuclear reactor are provided. The apparatus includes a body for insertion in a tubular structure, the body includes: an end effector having a weld torch operable to deposit weld material by forming molten weld droplets and depositing the weld droplets the tubular structure. A drive unit includes a brace for selectively anchoring against said tubular structure; at least one linear actuator for moving the apparatus relative to the brace; and a rotational actuator coupled to rotate the weld torch. The method includes inserting a repair apparatus into tubular structure of the nuclear reactor; moving the repair apparatus to a defect location; depositing a protective weld layer over the defect by sequentially depositing weld droplets atop a weld pool on the tubular structure, wherein the protective weld layer bonds to the tubular structure surrounding the defect.
Apparatuses and methods for repairing a defect in a nuclear reactor are provided. The apparatus includes a body for insertion in a tubular structure, the body includes: an end effector having a weld torch operable to deposit weld material by forming molten weld droplets and depositing the weld droplets the tubular structure. A drive unit includes a brace for selectively anchoring against said tubular structure; at least one linear actuator for moving the apparatus relative to the brace; and a rotational actuator coupled to rotate the weld torch. The method includes inserting a repair apparatus into tubular structure of the nuclear reactor; moving the repair apparatus to a defect location; depositing a protective weld layer over the defect by sequentially depositing weld droplets atop a weld pool on the tubular structure, wherein the protective weld layer bonds to the tubular structure surrounding the defect.
A filtering apparatus for a fluid intake of a nuclear power generation facility comprise primary and secondary frames. The primary frame defines an enclosed volume having least one inlet opening, and at least one outlet opening in fluid communication with the fluid intake. A primary filter is supported on the primary frame and covers the inlet opening such that fluid passes into the enclosed volume through the primary filter. The secondary frame is located within the volume enclosed by the primary frame. A secondary filter is supported on the secondary frame and defines an enclosed flow passage in communication with the outlet opening, such that fluid passes into the at least one outlet opening through the secondary filter and the enclosed flow passage.
A filtering apparatus for a fluid intake of a nuclear power generation facility comprise primary and secondary frames. The primary frame defines an enclosed volume having least one inlet opening, and at least one outlet opening in fluid communication with the fluid intake. A primary filter is supported on the primary frame and covers the inlet opening such that fluid passes into the enclosed volume through the primary filter. The secondary frame is located within the volume enclosed by the primary frame. A secondary filter is supported on the secondary frame and defines an enclosed flow passage in communication with the outlet opening, such that fluid passes into the at least one outlet opening through the secondary filter and the enclosed flow passage.
Detecting and/or positioning annulus spacers, to maintain the annular space between a pressure tube within a calandria tube of a nuclear reactor, includes vibrating the tube with a transducer to induce motion of the annulus spacer, measuring vibration of the tube for a first response and a second response, computing a first frequency-domain response function for the first response and a second frequency-domain response function for the second response, and measuring a relative phase and amplitude shift between the first and second frequency-domain response functions to determine movement of the annulus spacer.
Detecting and/or positioning annulus spacers, to maintain the annular space between a pressure tube within a calandria tube of a nuclear reactor, includes vibrating the tube with a transducer to induce motion of the annulus spacer, measuring vibration of the tube for a first response and a second response, computing a first frequency-domain response function for the first response and a second frequency-domain response function for the second response, and measuring a relative phase and amplitude shift between the first and second frequency-domain response functions to determine movement of the annulus spacer.
Systems and methods for transmitting communications to and from tooling for a nuclear reactor are provided. Some systems include first and second tools including first and second tool controllers positioned on a platform located adjacent a face of the nuclear reactor, and a tooling controller communicatively coupled to the first and second tool controllers, wherein the tooling controller is configured to receive a communication from the second tool controller, wherein the communication includes an identifier of an operating state of the second tool, generate a control signal for controlling the first tool based at least in part on the identifier of the operating state of the second tool, and transmit the control signal to the first tool controller. Some systems include a display, memory and a processor configured to render a reactor equipment representation comprising status indicators, receive status messages, and update status indicators based upon the status messages.
G21C 19/00 - Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
G21C 19/20 - Arrangements for introducing objects into the pressure vesselArrangements for handling objects within the pressure vesselArrangements for removing objects from the pressure vessel
Systems and methods for inspecting an interior surface of an element within a nuclear reactor. One system includes an inspection tool including a camera, a tool control system communicating with the inspection tool to control a rotational position of the inspection, and a workstation. The workstation is configured to receive image data captured with the camera at each of a plurality of rotational positions of the inspection tool and generate a panoramic image based on the image data. The workstation is also configured to automatically detect at least one defect within the panoramic image, and generate and output an inspection report, the inspection report including the panoramic image and data regarding the at least one defect.
Systems and methods for transmitting communications to and from tooling for a nuclear reactor are provided. Some systems include first and second tools including first and second tool controllers positioned on a platform located adjacent a face of the nuclear reactor, and a tooling controller communicatively coupled to the first and second tool controllers, wherein the tooling controller is configured to receive a communication from the second tool controller, wherein the communication includes an identifier of an operating state of the second tool, generate a control signal for controlling the first tool based at least in part on the identifier of the operating state of the second tool, and transmit the control signal to the first tool controller. Some systems include a display, memory and a processor configured to render a reactor equipment representation comprising status indicators, receive status messages, and update status indicators based upon the status messages.
25.
SYSTEM AND METHOD FOR VOLUME REDUCTION OF NUCLEAR REACTOR COMPONENTS
A volume reduction system for nuclear reactor components includes a feed unit to receive a radioactive tube from a nuclear reactor. The system also includes a segmenting unit to receive the tube from the feed unit. The segmenting unit includes a cutting element that segments the tube into segmented pieces. The system also includes a shredder unit to receive segmented pieces of the tube and shred the segmented pieces.
G21C 19/00 - Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
G21F 5/005 - Containers for solid radioactive wastes, e.g. for ultimate disposal
26.
INSPECTION TOOL AND METHOD FOR NUCLEAR REACTOR FUEL CHANNEL ASSEMBLY
Systems and methods for inspecting an interior surface of an element within a nuclear reactor. One system includes an inspection tool including a camera, a tool control system communicating with the inspection tool to control a rotational position of the inspection, and a workstation. The workstation is configured to receive image data captured with the camera at each of a plurality of rotational positions of the inspection tool and generate a panoramic image based on the image data. The workstation is also configured to automatically detect at least one defect within the panoramic image, and generate and output an inspection report, the inspection report including the panoramic image and data regarding the at least one defect.
A device for removing a rolled joint insert from between a calandria tube of a fuel channel assembly of a nuclear reactor and a tube sheet of the nuclear reactor, the rolled joint insert radially securing the calandria tube to the tube sheet. The device includes a body extending axially from a first end to a second end, opposite the first end; a heater for heating a rolled joint insert to a first temperature; a cooler for cooling the rolled joint insert to a second temperature; a ledge for axially engaging the rolled joint insert; and a gripper for gripping the calandria tube. The heater, the cooler, the ledge and the gripper are in axial alignment along the body of the device.
G21C 19/20 - Arrangements for introducing objects into the pressure vesselArrangements for handling objects within the pressure vesselArrangements for removing objects from the pressure vessel
28.
SYSTEM AND METHOD FOR ALIGNING NUCLEAR REACTOR TUBES AND END FITTINGS USING TUBE ROTATION
A method for orienting a pressure tube of a nuclear reactor relative to a calandria tube of the nuclear reactor. The method includes the steps of rotating the pressure tube with respect to the calandria tube to orient a bow of the pressure tube with respect to a bow of the calandria tube; inserting the pressure tube into the calandria tube; rotating the pressure tube with respect to the calandria tube to orient the bow of the pressure tube with respect to the bow of the calandria tube; and securing the pressure tube in the operational position.
G21C 19/20 - Arrangements for introducing objects into the pressure vesselArrangements for handling objects within the pressure vesselArrangements for removing objects from the pressure vessel
29.
SYSTEM AND METHOD FOR ALIGNING NUCLEAR REACTOR TUBES AND END FITTINGS USING TUBE GEOMETRY
A method for positioning a calandria tube within a calandria vessel of a nuclear reactor. The method includes determining a restrained bow of the calandria tube; determining an unrestrained bow of the calandria tube; calculating a vector sum of the restrained bow of the calandria tube and the restrained bow of the calandria bow; and positioning the calandria tube with respect to the nuclear reactor to orient the vector sum in an operational position.
G21C 19/00 - Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
30.
SYSTEM AND METHOD FOR ALIGNING NUCLEAR REACTOR TUBES AND END FITTINGS USING TUBE GEOMETRY
A method for positioning a calandria tube within a calandria vessel of a nuclear reactor. The method includes determining a restrained bow of the calandria tube; determining an unrestrained bow of the calandria tube; calculating a vector sum of the restrained bow of the calandria tube and the restrained bow of the calandria bow; and positioning the calandria tube with respect to the nuclear reactor to orient the vector sum in an operational position.
G21C 19/00 - Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
31.
CALANDRIA TUBE INSERT RELEASE AND REMOVAL TOOL AND METHOD
A device for removing a rolled joint insert from between a calandria tube of a fuel channel assembly of a nuclear reactor and a tube sheet of the nuclear reactor, the rolled joint insert radially securing the calandria tube to the tube sheet. The device includes a body extending axially from a first end to a second end, opposite the first end; a heater for heating a rolled joint insert to a first temperature; a cooler for cooling the rolled joint insert to a second temperature; a ledge for axially engaging the rolled joint insert; and a gripper for gripping the calandria tube. The heater, the cooler, the ledge and the gripper are in axial alignment along the body of the device.
G21C 19/20 - Arrangements for introducing objects into the pressure vesselArrangements for handling objects within the pressure vesselArrangements for removing objects from the pressure vessel
32.
SYSTEM AND METHOD FOR ALIGNING NUCLEAR REACTOR TUBES AND END FITTINGS USING TUBE ROTATION
A method for orienting a pressure tube of a nuclear reactor relative to a calandria tube of the nuclear reactor. The method includes the steps of rotating the pressure tube with respect to the calandria tube to orient a bow of the pressure tube with respect to a bow of the calandria tube; inserting the pressure tube into the calandria tube; rotating the pressure tube with respect to the calandria tube to orient the bow of the pressure tube with respect to the bow of the calandria tube; and securing the pressure tube in the operational position.
G21C 19/20 - Arrangements for introducing objects into the pressure vesselArrangements for handling objects within the pressure vesselArrangements for removing objects from the pressure vessel
33.
PRESSURE TUBE-TO-END FITTING COUPLING AND METHOD OF ASSEMBLING NUCLEAR REACTOR FUEL CHANNEL ASSEMBLY
A nuclear reactor core comprises a calandria having a shell and a tube sheet defining an aperture, a calandria tube coupled to the tube sheet and extending into the shell, a lattice tube coupled to the tube sheet and extending away from the shell, an end fitting body positioned at least partially in the lattice tube, a pressure tube positioned at least partially in the calandria tube and have an end secured to the end fitting body; and an end fitting liner positioned at least partially in the end fitting body coaxial with the pressure tube. An end of the end fitting liner adjacent the pressure tube includes a first inner surface having a roller clearance counter bore. The counter bore provides clearance to avoid contact between a rolling tool and the end fitting assembly.
G21C 1/08 - Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling-water reactor, integral-superheat reactor, pressurised-water reactor
34.
SYSTEM AND METHOD FOR VOLUME REDUCTION OF NUCLEAR REACTOR COMPONENTS
A volume reduction system for nuclear reactor components includes a feed unit to receive a radioactive tube from a nuclear reactor. The system also includes a segmenting unit to receive the tube from the feed unit. The segmenting unit includes a cutting element that segments the tube into segmented pieces. The system also includes a shredder unit to receive segmented pieces of the tube and shred the segmented pieces.
G21C 19/00 - Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
G21F 5/005 - Containers for solid radioactive wastes, e.g. for ultimate disposal
35.
APPARATUS AND METHOD FOR LOCATING A CALANDRIA TUBE
A method of inserting a calandria tube in a reactor includes engaging an insertion tool with an inner surface of the calandria tube, inserting a portion of the calandria tube through a first calandria tube sheet bore via the insertion tool, inserting a guide tool into the inner surface of the calandria tube and guiding a portion of the calandria tube through a second calandria tube sheet bore via the insertion tool and the guide tool.
G21C 19/20 - Arrangements for introducing objects into the pressure vesselArrangements for handling objects within the pressure vesselArrangements for removing objects from the pressure vessel
36.
APPARATUS AND METHOD FOR LOCATING A CALANDRIA TUBE
A method of inserting a calandria tube in a reactor includes engaging an insertion tool with an inner surface of the calandria tube, inserting a portion of the calandria tube through a first calandria tube sheet bore via the insertion tool, inserting a guide tool into the inner surface of the calandria tube and guiding a portion of the calandria tube through a second calandria tube sheet bore via the insertion tool and the guide tool.
G21C 19/20 - Arrangements for introducing objects into the pressure vesselArrangements for handling objects within the pressure vesselArrangements for removing objects from the pressure vessel
37.
PRESSURE TUBE-TO-END FITTING COUPLING AND METHOD OF ASSEMBLING NUCLEAR REACTOR FUEL CHANNEL ASSEMBLY
A nuclear reactor core comprises a calandria having a shell and a tube sheet defining an aperture, a calandria tube coupled to the tube sheet and extending into the shell, a lattice tube coupled to the tube sheet and extending away from the shell, an end fitting body positioned at least partially in the lattice tube, a pressure tube positioned at least partially in the calandria tube and have an end secured to the end fitting body; and an end fitting liner positioned at least partially in the end fitting body coaxial with the pressure tube. An end of the end fitting liner adjacent the pressure tube includes a first inner surface having a roller clearance counter bore. The counter bore provides clearance to avoid contact between a rolling tool and the end fitting assembly.
G21C 1/08 - Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling-water reactor, integral-superheat reactor, pressurised-water reactor
38.
COMMUNICATIONS SYSTEMS AND METHODS FOR NUCLEAR REACTOR TOOLING
Systems and methods for transmitting communications to and from tooling for a nuclear reactor are provided. Some systems include first and second tools including first and second tool controllers positioned on a platform located adjacent a face of the nuclear reactor, and a tooling controller communicatively coupled to the first and second tool controllers, wherein the tooling controller is configured to receive a communication from the second tool controller, wherein the communication includes an identifier of an operating state of the second tool, generate a control signal for controlling the first tool based at least in part on the identifier of the operating state of the second tool, and transmit the control signal to the first tool controller. Some systems include a display, memory and a processor configured to render a reactor equipment representation comprising status indicators, receive status messages, and update status indicators based upon the status messages.
G21C 19/00 - Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
G21C 19/20 - Arrangements for introducing objects into the pressure vesselArrangements for handling objects within the pressure vesselArrangements for removing objects from the pressure vessel
An apparatus and a method for inspecting an interior surface and an exterior surface of an element of a fuel channel assembly within a nuclear reactor are disclosed. To inspect the surface of the element, the apparatus and the element are relatively positioned such that the element is in a subject area. A reflector assembly reflects the subject area or a portion of the subject area to be in a field of view of an imaging device, which captures image data of its field of view. The reflector assembly has at least one of a first reflector and a second reflector. The first reflector reflects the outer surface of the element to be in the field of view of the imaging device. The second reflector reflects the inner surface of the element to be in the field of view of the imaging device.
An apparatus and a method for inspecting an interior surface and an exterior surface of an element of a fuel channel assembly within a nuclear reactor are disclosed. To inspect the surface of the element, the apparatus and the element are relatively positioned such that the element is in a subject area. A reflector assembly reflects the subject area or a portion of the subject area to be in a field of view of an imaging device, which captures image data of its field of view. The reflector assembly has at least one of a first reflector and a second reflector. The first reflector reflects the outer surface of the element to be in the field of view of the imaging device. The second reflector reflects the inner surface of the element to be in the field of view of the imaging device.
Methods and systems for cleaning inner surfaces of tubes in a heat exchanger. Some systems include a cleaning device having a nozzle configured to inject cleaning fluid into first and second tubes to perform different first and second cleaning cycles on the tubes, respectively, a controller configured to determine delivery parameters for the cleaning cycles based on a characteristic of each tube, and to control the cleaning device to perform the cleaning cycles based on the delivery parameters. Some methods include determining, with a controller, a tube in the heat exchanger engaged with a nozzle of a cleaning device for injecting a cleaning fluid into the tube during a cleaning cycle, a characteristic of the tube, and a delivery parameter of the cleaning cycle for the tube based on the characteristic of the tube; and performing the cleaning cycle for the tube based on the delivery parameter.
Methods and systems for cleaning inner surfaces of tubes in a heat exchanger. Some systems include a cleaning device having a nozzle configured to inject cleaning fluid into first and second tubes to perform different first and second cleaning cycles on the tubes, respectively, a controller configured to determine delivery parameters for the cleaning cycles based on a characteristic of each tube, and to control the cleaning device to perform the cleaning cycles based on the delivery parameters. Some methods include determining, with a controller, a tube in the heat exchanger engaged with a nozzle of a cleaning device for injecting a cleaning fluid into the tube during a cleaning cycle, a characteristic of the tube, and a delivery parameter of the cleaning cycle for the tube based on the characteristic of the tube; and performing the cleaning cycle for the tube based on the delivery parameter.
Fuel bundles for nuclear reactors are provided, and can include a fuel element containing U-233, U-235, PU-239, and/or PU-241 fissile material, along with at least two neutron absorbers consisting of Gd, Dy, Hf, Er, and/or Eu, wherein the fissile material(s) and the at least two neutron absorbers are homogeneously mixed in the fuel element. Fuel bundles for nuclear reactors are also provided that include fuel elements having inner elements and outer elements, wherein at least one of the inner elements includes a homogeneous mixture of a fissile material and at least two neutron absorbers. Fuel elements for nuclear reactors are also provided, and can include U-233, U-235, PU-239, and/or PU-241 fissile material, along with at least two neutron absorbers consisting of Gd, Dy, Hf, Er, and/or Eu, wherein the fissile material(s) and the at least two neutron absorbers are homogeneously mixed in the fuel element.
An apparatus for torsion testing of a helical specimen. A headstock includes a rotatable spindle. A tailstock is aligned with the spindle along a central axis. A pair of gripping assemblies grip first and second ends of the specimen, respectively, and are supported by the headstock and the tailstock. Each of the pair of gripping assemblies includes a mandrel having a portion which tapers toward a first end which is insertable into the helical specimen, a cup having a tapered bore configured to receive a second end of the mandrel along with the corresponding end of the helical specimen, and a fastener configured to engage the second end of the mandrel and pull the mandrel into the cup to pinch the helical specimen. A camera is aimed between the pair of gripping assemblies and operable to capture images of the helical specimen.
G01N 3/34 - Investigating strength properties of solid materials by application of mechanical stress by applying repeated or pulsating forces generated by mechanical means, e.g. hammer blows
45.
NUCLEAR FUEL CONTAINING A NEUTRON ABSORBER MIXTURE
Fuel bundles for nuclear reactors are provided, and can include a fuel element containing U-233, U-235, PU-239, and/or PU-241 fissile material, along with at least two neutron absorbers consisting of Gd, Dy, Hf, Er, and/or Eu, wherein the fissile material(s) and the at least two neutron absorbers are homogeneously mixed in the fuel element. Fuel bundles for nuclear reactors are also provided that include fuel elements having inner elements and outer elements, wherein at least one of the inner elements includes a homogeneous mixture of a fissile material and at least two neutron absorbers. Fuel elements for nuclear reactors are also provided, and can include U-233, U-235, PU-239, and/or PU-241 fissile material, along with at least two neutron absorbers consisting of Gd, Dy, Hf, Er, and/or Eu, wherein the fissile material(s) and the at least two neutron absorbers are homogeneously mixed in the fuel element.
Fuel bundles for nuclear reactors are provided, and can include a fuel element containing U-233, U-235, PU-239, and/or PU-241 fissile material, along with at least two neutron absorbers consisting of Gd, Dy, Hf, Er, and/or Eu, wherein the fissile material(s) and the at least two neutron absorbers are homogeneously mixed in the fuel element. Fuel bundles for nuclear reactors are also provided that include fuel elements having inner elements and outer elements, wherein at least one of the inner elements includes a homogeneous mixture of a fissile material and at least two neutron absorbers. Fuel elements for nuclear reactors are also provided, and can include U-233, U-235, PU-239, and/or PU-241 fissile material, along with at least two neutron absorbers consisting of Gd, Dy, Hf, Er, and/or Eu, wherein the fissile material(s) and the at least two neutron absorbers are homogeneously mixed in the fuel element.
Methods and systems for detecting an individual leaking fuel channel included in a reactor. One system includes a plurality of inlet lines and a plurality of outlet lines. Each of the plurality of inlet lines feeding annulus fluid in parallel to an annulus space of each of a first plurality of fuel channels included in the reactor, and each of the plurality of outlet lines collecting in parallel annulus fluid exiting an annulus space of each of a second plurality of fuel channels included in the reactor. In some embodiments, the system also includes a detector positioned at an outlet of each of the plurality of outlet lines configured to detect moisture in annulus fluid and identify a first position of an individual leaking fuel channel, and an isolation valve positioned at an inlet of each of the plurality of inlet lines operable to stop annulus fluid from circulating through one of the plurality of inlet lines and to identify a second position of the individual leaking fuel channel.
A system and method for detecting an individual leaking fuel channel included in a CANDUTM are provided. One system comprises: a plurality of inlet lines each feeding annulus fluid in parallel to annulus spaces of a corresponding plurality of fuel channels of a first grouping type; a plurality of outlet lines each collecting in parallel annulus fluid exiting the annulus spaces of a corresponding plurality of fuel channels of a second grouping type; a plurality of detectors each positioned at an outlet of one of the plurality of outlet lines and configured to detect moisture in the annulus fluid; and a plurality of isolation valves each positioned at an inlet of one of the plurality of inlet lines, each isolation valve operable to close and stop the annulus fluid from circulating through one of the plurality of inlet lines.