42 - Scientific, technological and industrial services, research and design
Goods & Services
Designing components and equipment for nuclear micro
reactors; scientific development of nuclear micro reactors;
scientific researching of nuclear micro reactors.
2.
SEGMENTED FUEL ASSEMBLY FOR USE IN A NUCLEAR REACTOR
A segmented fuel assembly (100) for use in a nuclear reactor is disclosed. The segmented fuel assembly comprises a lower nozzle (110), an upper nozzle (120), a plurality of guide tubes (130) positioned intermediate the lower nozzle and the upper nozzle, and a plurality of fuel segments (150) positioned intermediate the upper nozzle and the lower nozzle. The plurality of guide tubes are arranged in a first array. Each guide tube defines a longitudinal axis. Each fuel segment comprises a body (152) defining a plurality of coolant flow channels (156) and a plurality of guide tube openings (154). The guide tube openings are arranged in a second array corresponding to the first array. The guide tubes are positioned in the guide tube openings.
A segmented fuel assembly for use in a nuclear reactor is disclosed. The segmented fuel assembly comprises a lower nozzle, an upper nozzle, a plurality of guide tubes positioned intermediate the lower nozzle and the upper nozzle, and a plurality of fuel segments positioned intermediate the upper nozzle and the lower nozzle. The plurality of guide tubes are arranged in a first array. Each guide tube defines a longitudinal axis. Each fuel segment comprises a body defining a plurality of coolant flow channels and a plurality of guide tube openings. The guide tube openings are arranged in a second array corresponding to the first array. The guide tubes are positioned in the guide tube openings.
G21C 3/33 - Supporting or hanging of elements in the bundleMeans forming part of the bundle for inserting it into, or removing it from, the coreMeans for coupling adjacent bundles
09 - Scientific and electric apparatus and instruments
42 - Scientific, technological and industrial services, research and design
Goods & Services
Downloadable software for design and safety analyses of
chemical and nuclear facilities; downloadable software for
safety, accident, design, and environmental analyses of
chemical and nuclear facilities to determine facility
safety; downloadable software for predicting and tracking
the environmental conditions of nuclear facilities;
downloadable software for modeling the impact of various
scenarios in nuclear facilities, namely, the impacts of
imperfect ventilation, power outages, explosions, fires, and
soot loading; downloadable software for modeling nuclear
facilities to calculate temperatures, pressures, flow rates,
gas and aerosol compositions; downloadable software for
modeling nuclear facilities with stratified environmental
conditions. Providing on-line non-downloadable software for design and
safety analyses of chemical and nuclear facilities;
providing on-line non-downloadable software for safety,
accident, design, and environmental analyses of chemical and
nuclear facilities to determine facility safety; providing
on-line non-downloadable software for predicting and
tracking the environmental conditions of nuclear facilities;
providing on-line non-downloadable software for modeling the
impact of various scenarios in nuclear facilities, namely,
the impacts of imperfect ventilation, power outages,
explosions, fires, and soot loading; providing on-line
non-downloadable software for modeling nuclear facilities to
calculate temperatures, pressures, flow rates, gas and
aerosol compositions; providing on-line non-downloadable
software for modeling nuclear facilities with stratified
environmental conditions.
5.
FIBER REINFORCED MULTI-LAYERED WEAR AND CORROSION COATINGS OF ZIRCONIUM ALLOY NUCLEAR FUEL CLADDING
A covering for reinforcing a base layer of a nuclear fuel cladding is provided. The covering comprises a first layer configured to cover a first portion of the outer surface of the base layer of the nuclear fuel cladding, a second layer surrounding the first layer and the base layer and a third layer surrounding the second layer. The first layer comprises a fiber based material, the second layer comprises an interfacing material and the third layer comprises Chromium. A reinforced cladding for nuclear fuel and a method for producing a reinforced nuclear fuel cladding are also provided.
A fuel element (100) for a nuclear reactor, the fuel element comprising non-fissile particles (110) dispersed throughout fissile fuel (120), the non-fissile particles comprising a core comprising neutron absorbing material, wherein the neutron absorbing material is positioned at an innermost radial portion of the core, wherein the core is configured to remain stable at a temperature no less than 1000 °C; and an outer layer surrounding the core, the outer layer comprising silicon carbide.
A neutron flux detector comprising a source material and a solid state radiation detector is disclosed. The source material is configured to produce gamma photons greater than or equal to 6.8 MeV during neutron capture. The solid state radiation detector comprises a Schottky diode and an emitter layer comprising a Compton and photoelectron source material. The emitter layer is configured to receive the gamma photons produced by the source material. The emitter layer is spaced apart from the Schottky diode a distance such that a gap is defined between the emitter layer and the Schottky diode. The distance is selected such that only electrons produced by the emitter layer as a result of the emitter layer absorbing the gamma photons will contribute to a measured output signal of the Schottky diode.
Disclosed is nuclear reactor fuel rod for use in a nuclear reactor. The nuclear reactor fuel rod comprises a sleeve defining a longitudinal axis. The sleeve includes a first end portion and a second end portion. The nuclear reactor fuel rod further includes a first end cap mechanically coupled to the first end portion of the sleeve and a second end cap mechanically coupled to the second end portion of the sleeve. The second end cap is configured to slide along the longitudinal axis relative to the sleeve. The nuclear reactor fuel rod further includes a fuel compact located inside of the sleeve between the first end cap and the second end cap.
09 - Scientific and electric apparatus and instruments
37 - Construction and mining; installation and repair services
42 - Scientific, technological and industrial services, research and design
Goods & Services
Downloadable computer software for use in the field of nuclear energy, namely, for monitoring and optimization of nuclear reactor cores; downloadable computer software for analyzing power distributions or nuclear reactor cores; downloadable computer software for on-line monitoring of core power distribution in the field of nuclear energy; downloadable computer software for use in the field of nuclear energy, namely, for safety, accident, and environmental analysis of nuclear reactor cores; downloadable operating system programs for nuclear reactor cores; recorded operating system programs for nuclear reactor cores Technical support services, namely, troubleshooting in the nature of the repair of computer hardware for nuclear reactor cores Technical support services, namely, troubleshooting of computer software problems for nuclear reactor cores; Technical support services, namely, troubleshooting in the nature of diagnosing computer hardware and software problems for nuclear reactor cores; Computer software installation and maintenance for nuclear reactor cores; Development of computer codes for others for nuclear reactor cores
10.
AUTOMATED IN-VESSEL NEUTRON FLUX DETECTOR SYSTEM EMBEDDED IN CONTROL DRUM ASSEMBLY
A measurement device for determining a power level of a nuclear reactor core is provided, the measurement device comprising an in-vessel detector assembly. The in-vessel detector assembly comprises a rotatable housing defining a cavity therein and a detector element positioned in a first angular portion of the cavity of the housing. A control drum for a nuclear reactor core and a system for monitoring a power level of a nuclear reactor are also provided.
11.
RADIOISOTOPE PRODUCTION TARGET FOR PRODUCING RADIOISOTOPES USING PHOTONEUTRON PRODUCTION PROCESS
An irradiation target for producing a radioisotope is provided. The irradiation target comprises an outer tube extending along a first axis and an inner tube extending along a second axis. The inner tube comprises an outer surface surrounded by the inner surface of the outer tube, and a primary irradiation target material. The inner surface of the outer tube and the outer surface of the inner tube define an intermediate cavity therebetween. The irradiation target further comprises a secondary irradiation target material positioned within the intermediate cavity. An irradiation target assembly and a method for producing a radioisotope is also provided.
G21G 1/02 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
G21K 5/08 - Holders for targets or for objects to be irradiated
A sludge lance system for cleaning a tube bundle of a steam generator is disclosed. The sludge lance system comprises a mount, an index drive, and a sludge lance comprising a longitudinal rail, a manifold, an oscillator assembly, and a distal head. The oscillator assembly comprises a rotary output shaft. The distal head comprises a body portion, a first nozzle body on a first side of the distal head, and a second nozzle body on a second side of the distal head opposite the first side. The first nozzle body is rotatable relative to the body portion about a first longitudinal axis in a first direction in response to a rotation of the rotary output shaft. The second nozzle body is rotatable relative to the body portion about a second longitudinal axis in a second direction opposite the first direction in response to the rotation of the rotary output shaft.
A process for separating hydrogen isotope-based compounds is provided. The process comprises preparing a feed stream for a distillation process, feeding the feed stream into a column of a distillation unit, recovering a first fraction from the distillation unit, and recovering a second fraction from the distillation unit. The feed stream comprises hydrogen fluoride, deuterium fluoride, and tritium fluoride. The column is configured to operate at a pressure in a range of 0.1 atmospheres to 2 atmospheres. The first fraction is a TF-rich fraction and the second fraction is a DF-rich fraction. A nuclear fuel composition produced with the process for separating hydrogen isotope-based compounds, a process for producing a fuel from a product stream of a fusion reactor are also provided, and a distillation unit for fractionating fluorides of hydrogen isotopes of a feed stream are also provided.
An irradiation target for producing a radioisotope is provided. The irradiation target comprises an outer tube extending along a first axis and an inner tube extending along a second axis. The inner tube comprises an outer surface surrounded by the inner surface of the outer tube, and a primary irradiation target material. The inner surface of the outer tube and the outer surface of the inner tube define an intermediate cavity therebetween. The irradiation target further comprises a secondary irradiation target material positioned within the intermediate cavity. An irradiation target assembly and a method for producing a radioisotope is also provided.
G21G 1/02 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
G21G 1/06 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes outside of nuclear reactors or particle accelerators by neutron irradiation
G21G 1/12 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes outside of nuclear reactors or particle accelerators by electromagnetic irradiation, e.g. with gamma or X-rays
H05H 6/00 - Targets for producing nuclear reactions
A sludge lance system for cleaning a tube bundle of a steam generator is disclosed. The sludge lance system comprises a mount, an index drive, and a sludge lance comprising a longitudinal rail, a manifold, an oscillator assembly, and a distal head. The oscillator assembly comprises a rotary output shaft. The distal head comprises a body portion, a first nozzle body on a first side of the distal head, and a second nozzle body on a second side of the distal head opposite the first side. The first nozzle body is rotatable relative to the body portion about a first longitudinal axis in a first direction in response to a rotation of the rotary output shaft. The second nozzle body is rotatable relative to the body portion about a second longitudinal axis in a second direction opposite the first direction in response to the rotation of the rotary output shaft.
Energy storage plants; pumped thermal electricity storage plants; pumped thermal electrical energy storage plants; long duration energy storage plants; energy storage systems comprised of supercritical co2 heat pumps, supercritical co2 heat engines, hot reservoirs, cold reservoirs, and thermal batteries; pumped thermal electrical energy storage systems comprised of supercritical co2 heat pumps, supercritical co2 heat engines, hot reservoirs, cold reservoirs, and thermal batteries; long duration energy storage systems comprised of supercritical co2 heat pumps, supercritical co2 heat engines, hot reservoirs, cold reservoirs, and thermal batteries
Energy storage plants; pumped thermal electricity storage plants; pumped thermal electrical energy storage plants; long duration energy storage plants; energy storage systems comprised of supercritical co2 heat pumps, supercritical co2 heat engines, hot reservoirs, cold reservoirs, and thermal batteries; pumped thermal electrical energy storage systems comprised of supercritical co2 heat pumps, supercritical co2 heat engines, hot reservoirs, cold reservoirs, and thermal batteries; long duration energy storage systems comprised of supercritical co2 heat pumps, supercritical co2 heat engines, hot reservoirs, cold reservoirs, and thermal batteries
09 - Scientific and electric apparatus and instruments
42 - Scientific, technological and industrial services, research and design
Goods & Services
(1) Downloadable software for design and safety analyses of chemical and nuclear facilities; downloadable software for safety, accident, design, and environmental analyses of chemical and nuclear facilities to determine facility safety; downloadable software for predicting and tracking the environmental conditions of nuclear facilities; downloadable software for modeling the impact of various scenarios in nuclear facilities, namely, the impacts of imperfect ventilation, power outages, explosions, fires, and soot loading; downloadable software for modeling nuclear facilities to calculate temperatures, pressures, flow rates, gas and aerosol compositions; downloadable software for modeling nuclear facilities with stratified environmental conditions. (1) Providing on-line non-downloadable software for design and safety analyses of chemical and nuclear facilities; providing on-line non-downloadable software for safety, accident, design, and environmental analyses of chemical and nuclear facilities to determine facility safety; providing on-line non-downloadable software for predicting and tracking the environmental conditions of nuclear facilities; providing on-line non-downloadable software for modeling the impact of various scenarios in nuclear facilities, namely, the impacts of imperfect ventilation, power outages, explosions, fires, and soot loading; providing on-line non-downloadable software for modeling nuclear facilities to calculate temperatures, pressures, flow rates, gas and aerosol compositions; providing on-line non-downloadable software for modeling nuclear facilities with stratified environmental conditions.
19.
DETECTION APPARATUS COMPRISING A RESONANT ELECTRICAL CIRCUIT LOCATED WITHIN A NUCLEAR FUEL ROD
A detection apparatus includes a resonant electrical circuit supported within an interior of a nuclear fuel rod generates a response pulse in response to an excitation pulse and transmits the response pulse through a cladding of the fuel rod to another location within a reactor in which the fuel rod is housed and without any breach in the cladding. A characteristic of the response pulse is indicative of a condition of the fuel rod. The detection apparatus also includes a transmitter positioned outside the cladding, in the reactor, in the vicinity of the fuel rod and configured to generate the excitation pulse and transmit the excitation pulse through the cladding to the resonant electrical circuit. A receiver is supported within the reactor outside of the cladding and, in response to the response pulse, communicates a signal to an electronic processing apparatus outside of the reactor.
G21C 17/10 - Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
G01L 7/04 - Measuring the steady or quasi-steady pressure of a fluid or a fluent solid material by mechanical or fluid pressure-sensitive elements in the form of elastically-deformable gauges in the form of flexible, deformable tubes, e.g. Bourdon gauges
G01N 29/036 - Analysing fluids by measuring frequency or resonance of acoustic waves
G21C 3/16 - Details of the construction within the casing
G21C 17/06 - Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
H04Q 9/00 - Arrangements in telecontrol or telemetry systems for selectively calling a substation from a main station, in which substation desired apparatus is selected for applying a control signal thereto or for obtaining measured values therefrom
20.
A CONTINUOUSLY VARIABLE ELECTRONIC LOAD TESTER FOR USE WITH NUCLEAR INSTRUMENTATION SYSTEM HIGH VOLTAGE POWER SUPPLIES
A variable electronic load tester circuit comprising a control circuit and a variable electronic load circuit coupled to the control circuit to receive a voltage from a power supply and present a load to the power supply. The variable electronic load circuit comprises a plurality of transistors connected in series and operable as variable resistors. The control circuit is to control a resistance of the variable resistors to control the load presented to the power supply. The control circuit comprises an error amplifier to compare a first voltage to a feedback signal and an output signal indicative of a difference between the first voltage and the feedback signal. The output signal is to control the resistance of the variable electronic load circuit to vary the load presented to the power supply. The feedback signal is proportional to a current flowing through the variable electronic load circuit.
A variable electronic load tester circuit comprising a control circuit and a variable electronic load circuit coupled to the control circuit to receive a voltage from a power supply and present a load to the power supply. The variable electronic load circuit comprises a plurality of transistors connected in series and operable as variable resistors. The control circuit is to control a resistance of the variable resistors to control the load presented to the power supply. The control circuit comprises an error amplifier to compare a first voltage to a feedback signal and an output signal indicative of a difference between the first voltage and the feedback signal. The output signal is to control the resistance of the variable electronic load circuit to vary the load presented to the power supply. The feedback signal is proportional to a current flowing through the variable electronic load circuit.
A core component assembly for insertion into a fuel assembly of a nuclear reactor is disclosed. The core component assembly includes a baseplate, a connector, and a crimp nut. The baseplate includes a first side and a second side. An aperture is defined through the baseplate between the first side and the second side. The connector includes a bayonet, a threaded portion disposed beneath the bayonet, an annular shoulder disposed beneath the threaded portion, a gripping area disposed beneath the annular shoulder, and a hole disposed beneath the gripping area. The crimp nut includes a crimp sleeve and a threaded opening and is aligned with the aperture of the baseplate and welded to the first side of the baseplate. The threaded portion of the connector is threaded into the threaded opening of the crimp nut to attach the connector to the baseplate and position the bayonet within the crimp sleeve.
G21G 1/02 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
G21C 5/02 - Moderator or core structureSelection of materials for use as moderator Details
G21C 23/00 - Adaptations of reactors to facilitate experimentation or irradiation
G21G 1/00 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes
23.
Core Component Rodlet for Irradiating Isotope Targets in Pressurized Water Reactor Conditions
A rodlet for insertion into a fuel assembly guide tube of a fuel assembly in a pressurized water nuclear reactor is disclosed. The rodlet includes a capsule for housing a material to be irradiated, a backfill region disposed between the capsule and the material, and an outer tube comprising a plurality of apertures defined therein. The capsule defines a wall that surrounds the material. The outer tube is to house the capsule. The outer tube defines a first annulus and a second annulus. The first annulus includes a first width defined between the capsule and the outer tube. The second annulus includes a second width defined between the outer tube and the fuel assembly guide tube.
G21C 3/326 - Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different compositionComprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
G21C 3/322 - Means to influence the coolant flow through or around the bundles
G21C 3/33 - Supporting or hanging of elements in the bundleMeans forming part of the bundle for inserting it into, or removing it from, the coreMeans for coupling adjacent bundles
Disclosed is an apparatus and method for conditioning fluid flow in a nuclear power plant steam generator. A flow conditioning device includes an outer enclosure defining a plurality of entrance apertures arranged in an array and a plurality of exit apertures arranged in an array. A plurality of baffle plates are defined within the outer housing. The baffle plates define flow channels in fluid communication with the entrance and exit apertures to create a flow path of alternating directions. The flow channels receive fluid flow from the plurality of entrance apertures, direct the fluid flow from the entrance apertures in alternating directions through the flow channels to impart turning and frictional pressure loss to the fluid flow, and direct exiting fluid flow through the exit apertures into the tubelane region of the steam generator.
F22B 1/16 - Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being hot liquid or hot vapour, e.g. waste liquid, waste vapour
F22B 37/00 - Component parts or details of steam boilers
01 - Chemical and biological materials for industrial, scientific and agricultural use
11 - Environmental control apparatus
Goods & Services
Fuel for nuclear reactors; Uranium fuel for use in commercial nuclear power plants. Nuclear generators; Structural parts for pressurized water nuclear reactors, namely, fuel assemblies and structural parts therefor; Nuclear reactors; Fuel assemblies, namely, fuel in the form of a structured group of fuel rods that are accident tolerant for nuclear power plants.
09 - Scientific and electric apparatus and instruments
42 - Scientific, technological and industrial services, research and design
Goods & Services
Downloadable computer software using artificial intelligence
(AI) for machine learning and visual recognition for use in
the field of nuclear energy; recorded computer software
using artificial intelligence (AI) for machine learning and
visual recognition for use in the field of nuclear energy;
computer software platforms, downloadable, for machine
learning and visual recognition for use in the field of
nuclear energy; downloadable computer software for analyzing
data related to nuclear reactors. Providing on-line non-downloadable software using artificial
intelligence (AI) for machine learning and visual
recognition for use in the field of nuclear energy;
artificial intelligence as a service (AIaaS) services
featuring software using artificial intelligence (AI) for
machine learning and visual recognition for use in the field
of nuclear energy; providing temporary use of on-line
non-downloadable software and applications using artificial
intelligence (AI) for machine learning and visual
recognition for use in the field of nuclear energy;
providing on-line non-downloadable software for analyzing
data related to nuclear reactors.
09 - Scientific and electric apparatus and instruments
42 - Scientific, technological and industrial services, research and design
Goods & Services
Downloadable chatbot software using large language models (LLMs) for use in the field of nuclear energy; Downloadable computer software using artificial intelligence (AI) for use with nuclear reactors, nuclear power plants, and nuclear energy systems; Downloadable computer software using artificial intelligence (AI) for use in the field of nuclear energy; Downloadable computer software using artificial intelligence (AI) for integration into nuclear reactors, nuclear power plants, and nuclear energy systems; Downloadable computer software using artificial intelligence (AI) for the maintenance, inspection, optimization, and operation of nuclear reactors, nuclear power plants, and nuclear energy systems; Downloadable computer software using artificial intelligence (AI) for use in the manufacture of nuclear reactors and nuclear energy systems; Downloadable computer software using artificial intelligence (AI) for use in the design, manufacturing, and construction of nuclear reactors, nuclear power plants, and nuclear energy systems; Downloadable computer software using artificial intelligence (AI) for machine learning, text recognition, text generation, language interpretation, summarizing language, text translation, and response generation Providing temporary use of online non-downloadable chatbot software using large language models (LLMs) for use in the field of nuclear energy; Providing on-line non-downloadable software using artificial intelligence (AI) for use with nuclear reactors, nuclear power plants, and nuclear energy systems;; Providing on-line non-downloadable software using artificial intelligence (AI) for use in the field of nuclear energy; Artificial intelligence as a service (AIAAS) services featuring software using artificial intelligence (AI) for integration into nuclear reactors, nuclear power plants, and nuclear energy systems; Artificial intelligence as a service (AIAAS) services featuring software using artificial intelligence (AI) for the maintenance, inspection, optimization, and operation of nuclear reactors, nuclear power plants, and nuclear energy systems; Artificial intelligence as a service (AIAAS) services featuring software using artificial intelligence (AI) for use in the manufacture of nuclear reactors and nuclear energy systems; Artificial intelligence as a service (AIAAS) services featuring software using artificial intelligence (AI) for use in the design, manufacturing, and construction of nuclear reactors, nuclear power plants, and nuclear energy systems; Artificial intelligence as a service (AIAAS) services featuring software using artificial intelligence (AI) for machine learning, text recognition, text generation, language interpretation, summarizing language, text translation, and response generation
28.
RECOVERY OF URANIUM METAL USING EUTECTIC COMPOSITIONS
44444 which drives the temperature of the reactor to a raised temperature to form a slag phase and a metal phase separate from the slag phase in the reactor.
A plug for plugging a hole in a wall of a core barrel of a nuclear reactor, the plug comprising a body defining a plug portion, a clamping bar rotatably connected to the body and spaced apart from the plug portion, and a screw rotatable relative to the body and operably engaged with the clamping bar is disclosed. The screw is rotatable in a first direction to rotate the clamping bar from an insertion configuration to a clamping configuration. In the insertion configuration the clamping bar and the plug portion are aligned with each other and with the hole. In the clamping configuration, the clamping bar abuts one or more than one portion of the body to restrict rotation of the clamping bar in the first direction such that rotation of the screw in the first direction translates the clamping bar.
A method for controlling reactivity in a nuclear reactor is provided. The method comprises circulating coolant through the nuclear reactor. A composition of the coolant comprises water and gadolinium. The gadolinium is present in the coolant at a concentration suitable for controlling a neutronic reactivity of the nuclear reactor. A method for adjusting reactivity in a nuclear reactor and a coolant composition for a nuclear reactor are also provided.
G21C 7/06 - 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
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 method of recovering uranium (U) metal from uranium tetrafluoride (UF4) using a furnace including a reactor is disclosed. The method comprises placing UF4, a first material, and a second material that is different from the first material into the reactor. A eutectic composition comprising the first material, the second material, and fluoride has a melting point that is less than the melting point of U. The method further comprises raising the initial temperature of the UF4, the first material, and the second material to initiate a reaction between the first material, the second material, and the UF4 which drives the temperature of the reactor to a raised temperature to form a slag phase and a metal phase separate from the slag phase in the reactor.
Component parts of nuclear reactor cores, namely, nuclear
fuel assemblies capable of monitoring selected parameters
within the nuclear reactor core and wirelessly transmitting
the monitored parameters to a remote receiver.
33.
GADOLINIUM OXIDE NANO PARTICLES IN COOLANT FOR REACTIVITY CONTROL
A method for controlling reactivity in a nuclear reactor is provided. The method comprises circulating coolant through the nuclear reactor. A composition of the coolant comprises water and gadolinium. The gadolinium is present in the coolant at a concentration suitable for controlling a neutronic reactivity of the nuclear reactor. A method for adjusting reactivity in a nuclear reactor and a coolant composition for a nuclear reactor are also provided.
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 7/24 - Selection of substances for use as neutron-absorbing material
34.
EXPANDABLE PLUG AND PRESSURE TOOL FOR USE IN METALLIC WICK PORE SIZE TESTING
Disclosed is a device for performing pore size testing on a mesh wick. The device includes a housing and a tube positioned through the housing. The housing includes an internal surface. The tube includes an exterior surface. The exterior surface of the tube and the internal surface of the housing cooperatively define an internal cavity therebetween. The device further includes an inlet pipe extending from the housing. The inlet pipe connects to the internal cavity to allow a fluid to enter the internal cavity through the inlet pipe. The device further includes an expandable bladder positioned around a portion of the housing. The expandable bladder includes a first end and a second end. The portion of the housing is to allow the fluid to exit the internal cavity through the housing into the expandable bladder which causes the expandable bladder to expand.
Disclosed is a device for performing pore size testing on a mesh wick. The device includes a housing and a tube positioned through the housing. The housing includes an internal surface. The tube includes an exterior surface. The exterior surface of the tube and the internal surface of the housing cooperatively define an internal cavity therebetween. The device further includes an inlet pipe extending from the housing. The inlet pipe connects to the internal cavity to allow a fluid to enter the internal cavity through the inlet pipe. The device further includes an expandable bladder positioned around a portion of the housing. The expandable bladder includes a first end and a second end. The portion of the housing is to allow the fluid to exit the internal cavity through the housing into the expandable bladder which causes the expandable bladder to expand.
A tool for uncoupling and coupling an extension shaft assembly from a control element assembly of a nuclear reactor during reactor servicing is disclosed. The extension shaft assembly is transitionable between a coupled configuration where the extension shaft assembly is coupled to the control element assembly and an uncoupled configuration where the extension shaft assembly is uncoupled from the control element assembly. The tool comprises a support structure selectively attachable to the extension shaft assembly, a linear actuator, a microcontroller, a power source connector, a plunger shaft selectively attachable to the extension shaft assembly, and a sensor coupled to the microcontroller and the linear actuator. The sensor monitors a parameter indicative of a force experienced by the extension shaft assembly during at least one of a first actuation stroke or a second actuation stroke of a linear drive of the linear actuator.
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
B23P 19/04 - Machines for simply fitting together or separating metal parts or objects, or metal and non-metal parts, whether or not involving some deformationTools or devices therefor so far as not provided for in other classes for assembling or disassembling parts
09 - Scientific and electric apparatus and instruments
42 - Scientific, technological and industrial services, research and design
Goods & Services
(1) Downloadable computer software using artificial intelligence (AI) for machine learning and visual recognition for use in the field of nuclear energy; recorded computer software using artificial intelligence (AI) for machine learning and visual recognition for use in the field of nuclear energy; computer software platforms, downloadable, for machine learning and visual recognition for use in the field of nuclear energy; downloadable computer software for analyzing data related to nuclear reactors. (1) Providing on-line non-downloadable software using artificial intelligence (AI) for machine learning and visual recognition for use in the field of nuclear energy; artificial intelligence as a service (AIaaS) services featuring software using artificial intelligence (AI) for machine learning and visual recognition for use in the field of nuclear energy; providing temporary use of on-line non-downloadable software and applications using artificial intelligence (AI) for machine learning and visual recognition for use in the field of nuclear energy; providing on-line non-downloadable software for analyzing data related to nuclear reactors.
(1) Component parts of nuclear reactor cores, namely, nuclear fuel assemblies capable of monitoring selected parameters within the nuclear reactor core and wirelessly transmitting the monitored parameters to a remote receiver.
09 - Scientific and electric apparatus and instruments
42 - Scientific, technological and industrial services, research and design
Goods & Services
Downloadable computer software using artificial intelligence (AI) for machine learning and visual recognition for use in the field of nuclear energy; Recorded computer software using artificial intelligence (AI) for machine learning and visual recognition for use in the field of nuclear energy; Computer software platforms, downloadable, for machine learning and visual recognition for use in the field of nuclear energy; Downloadable computer software for analyzing data related to nuclear reactors Providing on-line non-downloadable software using artificial intelligence (AI) for machine learning and visual recognition for use in the field of nuclear energy; Artificial intelligence as a service (AIAAS) services featuring software using artificial intelligence (AI) for machine learning and visual recognition for use in the field of nuclear energy; Providing temporary use of on-line non-downloadable software and applications using artificial intelligence (AI) for machine learning and visual recognition for use in the field of nuclear energy; Providing on-line non-downloadable software for analyzing data related to nuclear reactors
41.
ULTRASONIC TESTING PROBE, COUPLANT DELIVERY SYSTEM, AND ULTRASONIC TESTING APPARATUS
An ultrasonic testing apparatus structured to perform an ultrasonic inspection on a workpiece. The ultrasonic testing apparatus comprises an ultrasonic testing probe structured to generate an ultrasonic output directed toward the workpiece and to receive an ultrasonic input from the workpiece that is responsive to the output; a couplant delivery system comprising a couplant supply, the couplant delivery system further comprising an actuator which, when operated, is structured to apply from the couplant supply an amount of a couplant to at least one of the workpiece and the ultrasonic testing probe; and a control apparatus electrically connected with the ultrasonic testing probe and with the couplant delivery system, the control apparatus being structured to receive the ultrasonic input and being further structured to operate the actuator. A couplant delivery system that is operable with an ultrasonic testing apparatus that is structured to perform an ultrasonic inspection on a workpiece.
G01N 29/28 - Investigating or analysing materials by the use of ultrasonic, sonic or infrasonic wavesVisualisation of the interior of objects by transmitting ultrasonic or sonic waves through the object Details providing acoustic coupling
A heat exchanger for a nuclear reactor is provided. The heat exchanger comprises a first layer for flowing a first process fluid and a second layer for flowing a second process fluid. The first layer is comprised of a first material and the second layer is comprised of a second material differing in composition from the first material. The first layer and the second layer are stacked on each other in a core of the heat exchanger and the first layer and the second layer are bonded to each other. A heat exchanger for a nuclear reactor and a method for producing a heat exchanger are also provided.
A neutron flux detector comprising a source material and a solid state radiation detector is disclosed. The source material is configured to produce gamma photons greater than or equal to 6.8 MeV during neutron capture. The solid state radiation detector comprises a Schottky diode and an emitter layer comprising a Compton and photoelectron source material. The emitter layer is configured to receive the gamma photons produced by the source material. The emitter layer is spaced apart from the Schottky diode a distance such that a gap is defined between the emitter layer and the Schottky diode. The distance is selected such that only electrons produced by the emitter layer as a result of the emitter layer absorbing the gamma photons will contribute to a measured output signal of the Schottky diode.
A heat exchanger for a nuclear reactor is provided. The heat exchanger comprises a first layer for flowing a first process fluid and a second layer for flowing a second process fluid. The first layer is comprised of a first material and the second layer is comprised of a second material differing in composition from the first material. The first layer and the second layer are stacked on each other in a core of the heat exchanger and the first layer and the second layer are bonded to each other. A heat exchanger for a nuclear reactor and a method for producing a heat exchanger are also provided.
G21C 1/03 - Fast fission reactors, i.e. reactors not using a moderator cooled by a coolant not essentially pressurised, e.g. pool-type reactors
G21C 1/32 - Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core
G21C 15/02 - 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
F28D 9/00 - Heat-exchange apparatus having stationary plate-like or laminated conduit assemblies for both heat-exchange media, the media being in contact with different sides of a conduit wall
F28D 21/00 - Heat-exchange apparatus not covered by any of the groups
45.
METHOD OF MAGNETICALLY REMOVING AN IRRADIATED CAPSULE FROM A BURNABLE ABSORBER RODLET
An apparatus for removing irradiated Co-60 capsules from a plurality of burnable absorber rodlets. The apparatus comprises a solenoid that induces an electromagnetic flux into a Co-60 capsule and locks the Co-60 capsule in parallel with the apparatus. The apparatus is slideable along a longitudinal axis of the burnable absorber rodlet and causes the Co-60 capsule to overcome a plurality of forces exerted on it.
G21C 19/32 - Apparatus for removing radioactive objects or materials from the reactor discharge area, e.g. to a storage placeApparatus for handling radioactive objects or materials within a storage place or removing them therefrom
G21C 3/326 - Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different compositionComprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
G21C 7/04 - Control of nuclear reaction by using self-regulating properties of reactor materials of burnable poisons
G21C 19/19 - Reactor parts specifically adapted to facilitate handling, e.g. to facilitate charging or discharging of fuel elements
G21C 23/00 - Adaptations of reactors to facilitate experimentation or irradiation
G21G 1/02 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
09 - Scientific and electric apparatus and instruments
42 - Scientific, technological and industrial services, research and design
Goods & Services
Downloadable software for design and safety analyses of chemical and nuclear facilities; Downloadable software for safety, accident, design, and environmental analyses of chemical and nuclear facilities to determine facility safety; Downloadable software for predicting and tracking the environmental conditions of nuclear facilities; Downloadable software for modeling the impact of various scenarios in nuclear facilities, namely, the impacts of imperfect ventilation, power outages, explosions, fires, and soot loading; Downloadable software for modeling nuclear facilities to calculate temperatures, pressures, flow rates, gas and aerosol compositions; Downloadable software for modeling nuclear facilities with stratified environmental conditions Providing on-line non-downloadable software for design and safety analyses of chemical and nuclear facilities; Providing on-line non-downloadable software for safety, accident, design, and environmental analyses of chemical and nuclear facilities to determine facility safety; Providing on-line non-downloadable software for predicting and tracking the environmental conditions of nuclear facilities; Providing on-line non-downloadable software for modeling the impact of various scenarios in nuclear facilities, namely, the impacts of imperfect ventilation, power outages, explosions, fires, and soot loading; Providing on-line non-downloadable software for modeling nuclear facilities to calculate temperatures, pressures, flow rates, gas and aerosol compositions; Providing on-line non-downloadable software for modeling nuclear facilities with stratified environmental conditions
University of Pittsburgh - of the Commonwealth System of Higher Education (USA)
Inventor
Heibel, Michael D.
Lopresti, Brian J.
Congedo, Thomas V.
Abstract
Devices, systems, and methods to produce Ac-225 from Ra-226 using gamma-radiation generator are disclosed herein. The gamma radiation generator can utilize an electronic neutron generator or a nuclear reactor to produce high energy prompt-capture gamma-radiation. The Ra-226 is irradiated by the gamma radiation to produce Ra-225, which decays to produce Ac-225. The method of using electronic neutron generator and an irradiation target material such as Gd-157 to produce high energy gamma radiation without using a continuously decaying radioisotope such as Co-60 could significantly reduce the cost and increase the safety associated with the production of high energy gamma radiation and Ac-225.
G21G 1/12 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes outside of nuclear reactors or particle accelerators by electromagnetic irradiation, e.g. with gamma or X-rays
G21G 1/00 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes
48.
TEMPERATURE CONTROL DEVICE SURROUNDING EQUIPMENT PENETRATING A PRESSURIZED VESSEL
Disclosed is a nuclear reactor, comprising: a canister, a nuclear reactor core housed inside of the canister, and a controlled temperature housing attached to the canister. The nuclear reactor core comprises a control drum and a shaft extending from the control drum and out of the nuclear reactor core. Heat generated by the nuclear reactor core enters the controlled temperature housing. The controlled temperature housing comprises a proximal end attached to the canister, a first internal plate spaced from and positioned distal to the proximal end, a second internal plate spaced from and positioned distal to the first internal plate, and a motor mounted to the second internal plate. The shaft enters the controlled temperature housing through the proximal end and extends to the motor. The controlled temperature housing is to passively maintain the motor at a temperature equal to or below a predetermined temperature threshold.
01 - Chemical and biological materials for industrial, scientific and agricultural use
11 - Environmental control apparatus
Goods & Services
Fuel for nuclear reactors; Uranium fuel for use in commercial nuclear power plants Nuclear generators; Structural parts for pressurized water nuclear reactors, namely, fuel assemblies and structural parts therefor; Nuclear reactors; Fuel assemblies, namely, fuel in the form of a structured group of fuel rods that are accident tolerant for nuclear power plants
50.
RADIOISOTOPE ACTIVITY SURVEILLANCE APPARATUS, SYSTEM, AND METHOD
Disclosed are a radioisotope activity surveillance system and methods. The system includes a fuel rod assembly having a plurality of nuclear fuel rods and a target assembly having a top nozzle including an orifice plate and at least one target material rod fixedly coupled to the orifice plate. The least one target material rod is slidably disposed within the fuel rod assembly. A sensing assembly defines an opening sized and configured to receive the target assembly therethrough. The sensing assembly includes a self-powered detector assembly to detect radioisotope activity of the target rod material. Also disclosed is a method for measuring a self-powered detector signal to calculate radioisotope activity of a target assembly and a method for analyzing total activity of a desired radioisotope.
G21C 23/00 - Adaptations of reactors to facilitate experimentation or irradiation
G21G 1/02 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
01 - Chemical and biological materials for industrial, scientific and agricultural use
Goods & Services
Fuel for nuclear reactors.
52.
FIXED IN-CORE DETECTOR DESIGN USING SIC SCHOTTKY DIODES CONFIGURED WITH A HIGH AXIAL AND RADIAL SENSOR DENSITY AND ENHANCED FISSION GAMMA MEASUREMENT SENSITIVITY
A system for measuring gamma spectroscopy of a neutron irradiated material includes a plurality of semiconductor sensors. Each of the semiconductor sensors includes a gamma ray receiving surface disposed above a Shottky layer in contact with an n-doped active layer. The receiving surface is configured to emit electrons upon irradiation by gamma rays. The receiving surface contacts an adjustable telescoping mount configured to adjust the distance between the receiving surface and the Shottky layer. The n-doped layer is fabricated to have a thickness designed to pass through electrons having greater than a defined energy. The combination of adjustable receiving surface and active layer thickness define a minimum and maximum energy response of each of the sensors. Multiple sensors may be integrated in an array in which each sensor has its own energy response. An array of such sensors can measure the gamma spectrum of a material irradiated with neutrons.
A method for detecting a leak in a cladding tube in a nuclear reactor is described. The method is well-suited for use in a reactor having a plurality of cladding tubes housed in a plurality of linearly arranged channels for flowing coolant past the cladding tubes. The method includes monitoring the channels for the occurrence of an increase in radiation above a selected base line indicative of the presence of at least one fission product in the coolant in at least one of the plurality of channels, and monitoring the channels for the occurrence of time dependent changes in the strength of radiation in the coolant above the base line along the length of the at least one of the plurality of channels. The leak location is calculated by triangulating the radiation readings from a fixed linear array of detectors positioned adjacent to the channels to determine the location of the strongest radiation reading and the location along the length of the channel where the increase in radiation occurred.
G01T 1/24 - Measuring radiation intensity with semiconductor detectors
G21C 17/10 - Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
H01L 31/10 - SEMICONDUCTOR DEVICES NOT COVERED BY CLASS - Details thereof in which radiation controls flow of current through the device, e.g. photoresistors characterised by at least one potential-jump barrier or surface barrier, e.g. phototransistors
H01L 31/115 - Devices sensitive to very short wavelength, e.g. X-rays, gamma-rays or corpuscular radiation
54.
SYSTEMS FOR PERIODICALLY MEASURING THE TOTAL GAMMA RADIATION ACTIVITY OF A TARGET RADIOISOTOPE BEING PRODUCED INSIDE THE CORE OF A NUCLEAR REACTOR
A system for measuring radiation activity of a target radioisotope being produced in a reactor core is disclosed. The system includes a cable assembly and a radiation detector. The cable assembly includes a housing, a target cable configured to position the housing, and a drive cable couplable and decouplable with the target cable. The target radioisotope is positioned within the housing. The drive cable is configured to drive the target cable. The radiation detector configured to periodically measure the radiation activity of the target radioisotope being produced.
G21G 1/02 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
G01T 1/167 - Measuring radioactive content of objects, e.g. contamination
Arrangements and devices for reducing and/or preventing wear of a thermal sleeve in a nuclear reactor are disclosed. Arrangements include a first structure provided on or in one the thermal sleeve and a second structure provided on or in the head penetration adapter. At least a portion of the first structure and at least another portion of the second structure interact to resist, reduce, and/or prevent rotation of the thermal sleeve about its central axis relative to the head penetration adapter. Devices include a base for coupling to a guide tube of the reactor and a plurality of protruding members extending upward from the base. Each member having a portion for engaging a corresponding portion of a guide funnel of the thermal sleeve.
G21C 13/036 - Joints between tubes and vessel walls, e.g. taking into account thermal stresses the tube passing through the vessel wall, i.e. continuing on both sides of the wall
G21C 13/04 - Arrangements for expansion and contraction
56.
USE OF BURNABLE ABSORBERS IN GRAPHITE MATRIX OF TRISO-FUELED COMPACTS IN NUCLEAR CORES
A composite fueled compact for a nuclear reactor is disclosed. The composite fueled compact comprises particles, a graphite matrix, and a neutron absorber. The particles comprise a fissile fuel. The graphite matrix defines a continuous phase surrounding the fissile fuel. The neutron absorber and the fissile fuel are configured to remain fixed in position relative to each other during reactor operation. A fuel assembly comprising a first group of stationary fueled compacts and a second group of stationary fueled compacts is also disclosed.
G21C 5/12 - Moderator or core structureSelection of materials for use as moderator characterised by composition, e.g. the moderator containing additional substances which ensure improved heat resistance of the moderator
G21C 7/24 - Selection of substances for use as neutron-absorbing material
G21C 1/07 - Pebble-bed reactorsReactors with granular fuel
57.
METHOD AND APPARATUS FOR INSPECTING A FUEL ASSEMBLY
A fuel assembly inspection system that utilizes a pressure transducer mounted to a utility's spent fuel handling tool to detect a relative change in depth of a fuel assembly during fuel inspections. The system then wirelessly transmits the signal to a fuel inspection recording system, which converts the signal to a relative height along the fuel assembly being viewed by a camera, and displays the relative height along with the applicable fuel assembly feature being viewed by the camera (e.g., nozzle, grid, span) via a text overlay on the video image of the inspection.
G21C 19/10 - Lifting devices or pulling devices adapted for co-operation with fuel elements or with control elements
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
H04N 5/77 - Interface circuits between an apparatus for recording and another apparatus between a recording apparatus and a television camera
Component parts of nuclear reactor cores, namely, nuclear fuel assemblies capable of monitoring selected parameters within the nuclear reactor core and wirelessly transmitting the monitored parameters to a remote receiver
59.
DEBRIS FILTERING ARRANGEMENT FOR NUCLEAR FUEL ASSEMBLY BOTTOM NOZZLE AND BOTTOM NOZZLE INCLUDING SAME
A filtering arrangement for use in a bottom nozzle of a fuel assembly in a nuclear reactor includes a top surface, a bottom surface, a plurality of vertical wall portions arranged in a generally squared grid-like pattern which extend between the bottom surface and the top surface and define a plurality of non-circular passages extending between the bottom surface and the top surface through the arrangement, and a plurality of first debris filters which are each positioned between the top surface and the bottom surface to generally span across a respective one of the plurality of passages.
G21C 3/32 - Bundles of parallel pin-, rod-, or tube-shaped fuel elements
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
60.
INCLINED FUEL TRANSFER SYSTEM BETWEEN CONTAINMENT AND FUEL HANDLING BUILDING
Disclosed is a fuel transfer system comprises a first housing, a second housing, and a fuel transfer tube connecting the first housing to the second housing, wherein the fuel transfer tube is disposed at an elevational angle. The fuel transfer system comprises a fuel transfer cart configured to slidably move from the first housing to the second housing through the fuel transfer tube.
G21C 19/18 - Apparatus for bringing fuel elements to the reactor charge area, e.g. from a storage place
G21C 19/19 - Reactor parts specifically adapted to facilitate handling, e.g. to facilitate charging or discharging of fuel elements
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
G21C 19/32 - Apparatus for removing radioactive objects or materials from the reactor discharge area, e.g. to a storage placeApparatus for handling radioactive objects or materials within a storage place or removing them therefrom
According to various aspects, the present disclosure provides pumps for pumping a liquid metal, systems for filling a container with a liquid metal, and methods for filling a container with a liquid metal. According to at least one aspect, a pump can include an actuator including a drive rod, a first plate, a second plate, guide rods extending between the first plate and the second plate, a traveling stage, and a bellows. The traveling stage can be operatively coupled to the drive rod and can be slidable along the guide rods intermediate the first plate and the second plate. The bellows can extend between the second plate and the traveling stage to define a bellows chamber. The actuator can be configured to slide the traveling stage to expand and contract the bellows to pump the liquid.
A reactor unit cell is disclosed including a graphite moderator structure, a heat pipe positioned in the graphite moderator structure, and a fuel assembly positioned in the graphite moderator structure. The fuel assembly comprises a beryllium-oxide sleeve and nuclear fuel positioned in the beryllium-oxide sleeve.
According to various aspects, the present disclosure provides pumps for pumping a liquid metal, systems for filling a container with a liquid metal, and methods for filling a container with a liquid metal. According to at least one aspect, a pump can include an actuator including a drive rod, a first plate, a second plate, guide rods extending between the first plate and the second plate, a traveling stage, and a bellows. The traveling stage can be operatively coupled to the drive rod and can be slidable along the guide rods intermediate the first plate and the second plate. The bellows can extend between the second plate and the traveling stage to define a bellows chamber. The actuator can be configured to slide the traveling stage to expand and contract the bellows to pump the liquid.
Disclosed is a fuel transfer system comprises a first housing, a second housing, and a fuel transfer tube connecting the first housing to the second housing, wherein the fuel transfer tube is disposed at an elevational angle. The fuel transfer system comprises a fuel transfer cart configured to slidably move from the first housing to the second housing through the fuel transfer tube.
G21C 19/10 - Lifting devices or pulling devices adapted for co-operation with fuel elements or with control elements
65.
Wireless power level and power distribution monitoring and control system for subcritical spent fuel assembly array using removable SiC neutron detector thimble tube
A power sensor system for monitoring a subcritical neutron generator is provided. The power sensor system comprises a self-powered sensor insert. The self-powered sensor insert comprises an insert thimble and a detector assembly. The insert thimble includes an outer housing, a power generator configured to produce an electrical power based on an incident radiation and a first electrical interface electrically connected to the power generator. The detector assembly includes a solid state radiation detector able to provide a detector signal directly proportional to a neutron flux level, a transmitter configured to wirelessly output a transmitter signal based on the detector signal and a second electrical interface configured to electrically couple to the first electrical interface. A power monitor system comprising a power sensor system and a control system and a method for optimizing a subcritical neutron generator are also provided.
A heat pipe configured to remove heat from a nuclear reactor core is disclosed herein. The heat pipe can include an inner housing defining an inner volume configured to accommodate a heat source and an outer housing configured about the inner housing and the heat source. A wick can be positioned between at least a portion of the inner housing and at least a portion of the outer housing, wherein the wick can include a capillary material, and wherein the wick can define an intermediate volume between the inner housing and the outer housing. A working fluid can be positioned within the intermediate volume, wherein the working fluid can evaporate at a first end of the heat pipe and condense at a second end of the heat pipe adjacent to a heat exchanger, and wherein the wick can return condensed working fluid to the first end of the heat pipe.
G21C 15/257 - Promoting flow of the coolant using heat-pipes
F28D 15/04 - Heat-exchange apparatus with the intermediate heat-transfer medium in closed tubes passing into or through the conduit walls in which the medium condenses and evaporates, e.g. heat-pipes with tubes having a capillary structure
F28D 21/00 - Heat-exchange apparatus not covered by any of the groups
67.
ADVANCED MANUFACTURING HEAT PIPE SEGMENT WITH INTEGRAL PRINTED WICK
A transition piece for joining heat pipe segments in a joining process is provided. The transition piece comprises a head section, a body section, a tail section and alignment tabs configured to facilitate a rotational alignment of an end of the body section and an end of a heat pipe segment during the joining process. The body section comprises a wick and an outer wall. Each of the alignment tabs comprises an end portion axially extending away from the body section. The body section and the alignment tabs are configured as an integral structure. A method for producing a transition piece of a heat pipe and a method for joining segments of a heat pipe are also provided.
F28D 15/02 - Heat-exchange apparatus with the intermediate heat-transfer medium in closed tubes passing into or through the conduit walls in which the medium condenses and evaporates, e.g. heat-pipes
F28D 15/04 - Heat-exchange apparatus with the intermediate heat-transfer medium in closed tubes passing into or through the conduit walls in which the medium condenses and evaporates, e.g. heat-pipes with tubes having a capillary structure
B33Y 80/00 - Products made by additive manufacturing
Disclosed is nuclear reactor fuel rod for use in a nuclear reactor. The nuclear reactor fuel rod comprises a sleeve defining a longitudinal axis. The sleeve includes a first end portion and a second end portion. The nuclear reactor fuel rod further includes a first end cap mechanically coupled to the first end portion of the sleeve and a second end cap mechanically coupled to the second end portion of the sleeve. The second end cap is configured to slide along the longitudinal axis relative to the sleeve. The nuclear reactor fuel rod further includes a fuel compact located inside of the sleeve between the first end cap and the second end cap.
A transition piece for joining heat pipe segments in a joining process is provided. The transition piece comprises a head section, a body section, a tail section and alignment tabs configured to facilitate a rotational alignment of an end of the body section and an end of a heat pipe segment during the joining process. The body section comprises a wick and an outer wall. Each of the alignment tabs comprises an end portion axially extending away from the body section. The body section and the alignment tabs are configured as an integral structure. A method for producing a transition piece of a heat pipe and a method for joining segments of a heat pipe are also provided.
F28D 15/04 - Heat-exchange apparatus with the intermediate heat-transfer medium in closed tubes passing into or through the conduit walls in which the medium condenses and evaporates, e.g. heat-pipes with tubes having a capillary structure
B33Y 80/00 - Products made by additive manufacturing
F28D 21/00 - Heat-exchange apparatus not covered by any of the groups
71.
Automated In-Vessel Neutron Flux Detector System Embedded in Control Drum Assembly
A measurement device for determining a power level of a nuclear reactor core is provided, the measurement device comprising an in-vessel detector assembly. The in-vessel detector assembly comprises a rotatable housing defining a cavity therein and a detector element positioned in a first angular portion of the cavity of the housing. A control drum for a nuclear reactor core and a system for monitoring a power level of a nuclear reactor are also provided.
Disclosed is a nuclear reactor system for use with a power grid. The nuclear reactor system comprising a nuclear reactor (100), an energy storage system (300) coupled to the nuclear reactor, and a control circuit (400) coupled to the nuclear reactor and the energy storage system. The control circuit is configured to monitor a power demand of the power grid (500), monitor a power output generated from the nuclear reactor, detect a change in the power demand, cause the energy storage system to temporarily compensate for the change in the power demand, and adjust the power output based on the change in the power demand.
G21D 3/08 - Regulation of any parameters in the plant
F01K 3/00 - Plants characterised by the use of steam or heat accumulators, or intermediate steam heaters, therein
F03D 9/00 - Adaptations of wind motors for special useCombinations of wind motors with apparatus driven therebyWind motors specially adapted for installation in particular locations
G21D 3/12 - Regulation of any parameters in the plant by adjustment of the reactor in response only to changes in engine demand
73.
Energy storage system for nuclear reactor remote installation
Disclosed is a nuclear reactor system for use with a power grid. The nuclear reactor system comprising a nuclear reactor, an energy storage system coupled to the nuclear reactor, and a control circuit coupled to the nuclear reactor and the energy storage system. The control circuit is configured to monitor a power demand of the power grid, monitor a power output generated from the nuclear reactor, detect a change in the power demand, cause the energy storage system to temporarily compensate for the change in the power demand, and adjust the power output based on the change in the power demand.
H02J 13/00 - Circuit arrangements for providing remote indication of network conditions, e.g. an instantaneous record of the open or closed condition of each circuitbreaker in the networkCircuit arrangements for providing remote control of switching means in a power distribution network, e.g. switching in and out of current consumers by using a pulse code signal carried by the network
74.
DEVICES, SYSTEMS, AND METHODS FOR ENHANCING THE IMPLEMENTATION OF CONTROL CIRCUITS FOR NUCLEAR INSTRUMENTATION AND CONTROL SYSTEMS
A nuclear instrumentation and control system is disclosed herein. The nuclear instrumentation and control system can include a housing and a plurality of selectively removable finished board assemblies configured to be installed within the hosing and electrically coupled to the instrumentation and control system nuclear reactor. At least one of the selectively removable finished board assemblies includes an input/output circuit. The nuclear instrumentation and control system can further include a daughter card including a control circuit, wherein the daughter card is configured to be selectively coupled to the at least one selectively removable base board of the plurality of selectively removable base boards via a mechanical connector and an electrical connector.
G06F 11/20 - Error detection or correction of the data by redundancy in hardware using active fault-masking, e.g. by switching out faulty elements or by switching in spare elements
75.
DEVICES, SYSTEMS, AND METHODS FOR COOLING A NUCLEAR REACTOR WITH HYDRIDE MODERATORS
A heat exchanger for cooling a nuclear reactor core is disclosed herein. The heat exchanger can include a first stage including an input configured to receive a working fluid from an external source into the heat exchanger, and a first plenum configured to envelope a moderator heat pipe extending from the nuclear reactor core. The heat exchanger can further include a second stage including an output configured to remove a working fluid from the heat exchanger to the external source, and a second plenum configured to envelope a power heat pipe extending from the nuclear reactor core, wherein the first plenum and the second plenum are in fluid communication and configured such that the external fluid must traverse the first plenum and over the moderator heat pipe before entering the second plenum and traversing over the power heat pipe.
G21C 1/32 - Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core
G21C 5/02 - Moderator or core structureSelection of materials for use as moderator Details
Devices, systems, and methods for delivering delta radiation using prompt neutron capture gamma radiation are disclosed herein. In one aspect, a device for delivering delta radiation can include a neutron generator, an electron emitter, and an irradiation target. The neutron generator may be configured to generate a neutron flux field. The an irradiation target can include an irradiation target material having a high thermal neutron cross section and can be configured to emit gamma radiation in response to exposure to the neutron flux field. The electron emitter can be configured to emit delta radiation in response to exposure to the gamma radiation. In some aspects, the irradiation target and the electron emitter can be configured to be positioned between the neutron generator and a surface of an object to deliver the delta radiation to a target region within the object.
An enclosure for producing a radioisotope from an irradiation target material in a thimble guide tube of a nuclear reactor core is provided. The enclosure is comprised of an enriched material and defines a cavity therein. The cavity of the enclosure is configured to house the irradiation target material. A target assembly for producing synthetic radioisotopes and a method for producing pharmaceutical radioisotopes with a target assembly are also provided.
G21G 1/06 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes outside of nuclear reactors or particle accelerators by neutron irradiation
G21G 1/00 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes
A target assembly for producing synthetic radioisotopes of Cobalt is provided. The target assembly comprises an enclosure and an irradiation target material. The enclosure defines a cavity therein and is comprised of an enriched material configured to have a short half-life upon being exposed to a neutron flux. The irradiation target material is comprised of a precursor to Cobalt-60. A method for producing a target assembly is also provided.
G21G 1/00 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes
B22F 10/28 - Powder bed fusion, e.g. selective laser melting [SLM] or electron beam melting [EBM]
B33Y 80/00 - Products made by additive manufacturing
G21G 1/02 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
79.
DEVICES, SYSTEMS, AND METHODS FOR COOLING A NUCLEAR REACTOR WITH HYDRIDE MODERATORS
A heat exchanger for cooling a nuclear reactor core is disclosed herein. The heat exchanger can include a first stage including an input configured to receive a working fluid from an external source into the heat exchanger, and a first plenum configured to envelope a moderator heat pipe extending from the nuclear reactor core. The heat exchanger can further include a second stage including an output configured to remove a working fluid from the heat exchanger to the external source, and a second plenum configured to envelope a power heat pipe extending from the nuclear reactor core, wherein the first plenum and the second plenum are in fluid communication and configured such that the external fluid must traverse the first plenum and over the moderator heat pipe before entering the second plenum and traversing over the power heat pipe.
G21C 5/12 - Moderator or core structureSelection of materials for use as moderator characterised by composition, e.g. the moderator containing additional substances which ensure improved heat resistance of the moderator
G21C 15/08 - 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 moderating material
G21C 15/257 - Promoting flow of the coolant using heat-pipes
42 - Scientific, technological and industrial services, research and design
Goods & Services
Nuclear micro reactors; nuclear small modular reactors. Engineering services in the field of nuclear micro reactors;
engineering services in the field of nuclear small modular
reactors; designing nuclear components for nuclear micro
reactors and equipment for nuclear micro reactors;
scientific development of nuclear reactors; scientific
research in the field of nuclear reactors.
81.
EFFECTIVE COATING MORPHOLOGY TO PROTECT ZR ALLOY CLADDING FROM OXIDATION AND HYDRIDING
A coating for protecting a Zirconium alloy based layer of a nuclear fuel rod cladding is provided. The coating comprises a primary layer. A microstructure of the primary layer is comprised of a number of grains and is randomized. The primary layer is configured with a density of about 94.5% or greater. A cladding for a nuclear fuel rod and a method for producing a cladding for a nuclear fuel rod are also provided.
A coating (100) for protecting a Zirconium alloy based layer (90) of a nuclear fuel rod cladding (38) is provided. The coating comprises a primary layer (102). A microstructure of the primary layer is comprised of a number of grains (84) and is randomized. The primary layer is configured with a density of about 94.5% or greater. A cladding for a nuclear fuel rod and a method for producing a cladding for a nuclear fuel rod are also provided.
An apparatus for translating and stopping an irradiation capsule assembly in an instrumentation tube is provided. The apparatus comprises a body adapted to be to slidably received within an inner diameter defined by an instrumentation tube. The body defines a cavity having an inner wall defining a diameter and a plurality of radially distributed apertures. At least one of the plurality of radially distributed apertures defines an edge. The body further comprises a proximal end defining an opening. The apparatus further comprises a radial spring slidably disposed within the cavity defined by the body. The radial spring comprises an endplate and a plurality of spring arms extending from the endplate and biased radially outwardly. Each one of the plurality of spring arms comprises a detent. A system for translating and stopping an irradiation capsule assembly in an instrumentation tube is also provided.
G21G 1/02 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
G21C 23/00 - Adaptations of reactors to facilitate experimentation or irradiation
84.
MODULAR THERMAL AND RADIATION SHIELDING WITH PASSIVE HEAT REMOVAL
A housing assembly configured to house a reactor is disclosed. The housing assembly includes a plurality of modular walls configured to surround the reactor and a passive temperature control system. The plurality of modular walls includes a first modular wall. The passive temperature control system is coupled to the first modular wall. The passive temperature control system is configured to transfer heat between the reactor and an area around the housing assembly.
Disclosed is a passively cooled nuclear reactor, comprising a heat exchanger and a nuclear reactor core disposed proximal to the heat exchanger. The nuclear reactor core comprising a fuel rod, a heat pipe located proximate to the fuel rod and extending from the nuclear reactor core into the heat exchanger, a moderator monolith configured to house and space the fuel rod and the heat pipe, and a thermal bond material disposed internally throughout the moderator monolith to surround the fuel rod and the heat pipe with the thermal bond material and to facilitate heat transfer from the nuclear reactor core to the heat exchanger.
G21C 1/32 - Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core
G21C 5/02 - Moderator or core structureSelection of materials for use as moderator Details
G21C 15/257 - Promoting flow of the coolant using heat-pipes
Disclosed is a passively cooled nuclear reactor, comprising a heat exchanger and a nuclear reactor core disposed proximal to the heat exchanger. The nuclear reactor core comprising a fuel rod, a heat pipe located proximate to the fuel rod and extending from the nuclear reactor core into the heat exchanger, a moderator monolith configured to house and space the fuel rod and the heat pipe, and a thermal bond material disposed internally throughout the moderator monolith to surround the fuel rod and the heat pipe with the thermal bond material and to facilitate heat transfer from the nuclear reactor core to the heat exchanger.
A cladding (100) for housing enriched nuclear fuel in a nuclear fuel assembly (10) is provided. The cladding comprises a base layer (110) comprised of Zirconium alloy and a coating (120) for the base layer. The base layer has a wall thickness of less than 1 millimeter. The coating comprises a primary layer comprised of Chromium or a Chromium alloy. The primary layer has a thickness in the range of about 5 to about 50 microns. A fuel rod (22) for a nuclear reactor core and a method for producing a fuel rod are also provided.
Devices, systems, and methods for power generation using irradiators and other gamma ray sources are disclosed herein. In various aspects, an irradiator-based power generation device is disclosed. The power generation device can include a radiator layer configured to at least partially surround an irradiator, wherein the radiator layer comprises a radiator material configured to emit delta radiation in response to exposure to gamma radiation; an electrical insulation layer configured to surround the radiator layer, wherein the electrical insulation layer comprises an electrical insulation material configured to allow delta radiation to penetrate therethrough; and a collector layer configured to surround the electrical insulation layer, wherein the collector layer comprises a collector material configured to collect delta radiation.
An enclosure for producing a radioisotope from an irradiation target material in a thimble guide tube of a nuclear reactor core is provided. The enclosure is comprised of an enriched material and defines a cavity therein. The cavity of the enclosure is configured to house the irradiation target material. A target assembly for producing synthetic radioisotopes and a method for producing pharmaceutical radioisotopes with a target assembly are also provided.
G21G 1/02 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
H05H 6/00 - Targets for producing nuclear reactions
A method of forming a wick assembly is disclosed including positioning an inner ring in a first wick, positioning the inner ring in a second wick, abutting an end of the first wick with an end of the second wick, positioning an outer ring about a portion of the first wick and a portion of the second wick, positioning a mandrel within the inner ring, positioning a die about the outer ring, and applying a force to the die, wherein the force couples the outer ring, the inner ring, the first wick, and the second wick together to form the wick assembly.
B21D 39/04 - Application of procedures in order to connect objects or parts, e.g. coating with sheet metal otherwise than by platingTube expanders of tubes with tubesApplication of procedures in order to connect objects or parts, e.g. coating with sheet metal otherwise than by platingTube expanders of tubes with rods
B21D 53/06 - Making other particular articles heat exchangers, e.g. radiators, condensers of metal tubes
B23K 20/02 - Non-electric welding by applying impact or other pressure, with or without the application of heat, e.g. cladding or plating by means of a press
F28D 15/04 - Heat-exchange apparatus with the intermediate heat-transfer medium in closed tubes passing into or through the conduit walls in which the medium condenses and evaporates, e.g. heat-pipes with tubes having a capillary structure
A target assembly for producing synthetic radioisotopes of Cobalt is provided. The target assembly comprises an enclosure and an irradiation target material. The enclosure defines a cavity therein and is comprised of an enriched material configured to have a short half-life upon being exposed to a neutron flux. The irradiation target material is comprised of a precursor to Cobalt-60. A method for producing a target assembly is also provided.
G21G 1/06 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes outside of nuclear reactors or particle accelerators by neutron irradiation
G21G 4/06 - Radioactive sources other than neutron sources characterised by constructional features
H05H 6/00 - Targets for producing nuclear reactions
93.
USE OF OXIDATION RESISTANT COATINGS TO INCREASE THIN WALLED CLADDING TENSILE STRENGTH TO INCREASE URANIUM LOADINGS
A cladding for housing enriched nuclear fuel in a nuclear fuel assembly is provided. The cladding comprises a base layer comprised of Zirconium alloy and a coating for the base layer. The base layer has a wall thickness of less than 1 millimeter. The coating comprises a primary layer comprised of Chromium or a Chromium alloy. The primary layer has a thickness in the range of about 5 to about 50 microns. A fuel rod for a nuclear reactor core and a method for producing a fuel rod are also provided.
An in-situ wick rolling and forming assembly configured to roll and form a wick for a heat pipe from a wick mesh. The in-situ wick rolling and forming assembly includes a first forming shell, a slotted mandrel, and an expandable member. The first forming shell is configured to form the wick in-situ after the rolling of the wick mesh. The first forming shell includes a first recess and a first parting surface. A first central axis of the first recess is positioned below the first parting surface. The slotted mandrel is removably positionable in the first recess.
B21F 33/00 - Tools or devices specially designed for handling or processing wire fabrics or the like
B22F 3/00 - Manufacture of workpieces or articles from metallic powder characterised by the manner of compacting or sinteringApparatus specially adapted therefor
B23P 15/26 - Making specific metal objects by operations not covered by a single other subclass or a group in this subclass heat exchangers
F28D 15/04 - Heat-exchange apparatus with the intermediate heat-transfer medium in closed tubes passing into or through the conduit walls in which the medium condenses and evaporates, e.g. heat-pipes with tubes having a capillary structure
G21C 15/257 - Promoting flow of the coolant using heat-pipes
95.
DEVICES, SYSTEMS, AND METHODS FOR THE ENHANCED OPERATION OF HYDRAULIC CONTROL UNITS OF A CONTROL ROD DRIVE MECHANISM TO REGULATE NUCLEAR FLUX IN A REACTOR CORE
A hydraulic control unit ("HCU") configured to control a control rod drive mechanism ("CRDM") configured to control the nuclear flux produced by a nuclear reactor is disclosed herein. The HCU can include a plurality of valves configured to attenuate a fluid pressure within the CRDM, wherein the attenuation of the fluid pressure is configured to cause a control rod of the CRDM to be inserted or withdrawn from a reactor vessel of the nuclear reactor, and a control circuit including a plurality of relay interfaces, wherein each relay of the plurality of relay interfaces is electrically coupled to a valve of the plurality of valves, a controller electrically coupled to the plurality of relay interfaces, and a communications circuit communicably coupled to a header controller, wherein the communications circuit is configured to transmit and receive signals between the controller and the header controller.
An in-core detector configured to measure a power distribution in a nuclear reactor is disclosed herein. The in-core detector includes a housing configured to be placed within a predetermined location of the nuclear reactor and a plurality of a gamma detectors. Each gamma detector of the plurality of gamma detectors includes a Schottky diode including an active semiconductor region and a Schottky contact, an Ohmic contact, a photoelectron source material configured to transfer electrons to the active region upon contact with gamma radiation, and a first and second lead. The plurality of gamma detectors are positioned within the housing such that each gamma detector of the plurality of gamma detectors is radially offset relative to an adjacent gamma detector of the plurality of gamma detectors, such that the first and second leads of each gamma detector are offset relative to the first and second leads of the adjacent gamma detector.
42 - Scientific, technological and industrial services, research and design
Goods & Services
(1) Nuclear micro reactors; nuclear small modular reactors. (1) Engineering services in the field of nuclear micro reactors; engineering services in the field of nuclear small modular reactors; designing nuclear components for nuclear micro reactors and equipment for nuclear micro reactors; scientific development of nuclear reactors; scientific research in the field of nuclear reactors.
98.
DEVICES, SYSTEMS, AND METHODS FOR THE ENHANCED OPERATION OF HYDRAULIC CONTROL UNITS OF A CONTROL ROD DRIVE MECHANISM TO REGULATE NUCLEAR FLUX IN A REACTOR CORE
A hydraulic control unit (“HCU”) configured to control a control rod drive mechanism (“CRDM”) configured to control the nuclear flux produced by a nuclear reactor is disclosed herein. The HCU can include a plurality of valves configured to attenuate a fluid pressure within the CRDM, wherein the attenuation of the fluid pressure is configured to cause a control rod of the CRDM to be inserted or withdrawn from a reactor vessel of the nuclear reactor, and a control circuit including a plurality of relay interfaces, wherein each relay of the plurality of relay interfaces is electrically coupled to a valve of the plurality of valves, a controller electrically coupled to the plurality of relay interfaces, and a communications circuit communicably coupled to a header controller, wherein the communications circuit is configured to transmit and receive signals between the controller and the header controller.
A method of removing an irradiated capsule from inside of a burnable absorber rodlet. The capsule can contain produced Co-60. The method includes inducing an electromagnetic flux into the capsule to magnetically lock the capsule with a capsule removal module. While locked, the capsule can be relatively moved along a longitudinal axis of the rodlet to remove the capsule from the rodlet.
G21C 19/32 - Apparatus for removing radioactive objects or materials from the reactor discharge area, e.g. to a storage placeApparatus for handling radioactive objects or materials within a storage place or removing them therefrom
G21C 7/04 - Control of nuclear reaction by using self-regulating properties of reactor materials of burnable poisons
G21C 19/19 - Reactor parts specifically adapted to facilitate handling, e.g. to facilitate charging or discharging of fuel elements
G21C 3/326 - Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different compositionComprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
G21C 23/00 - Adaptations of reactors to facilitate experimentation or irradiation
G21G 1/02 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
100.
SYSTEMS AND METHODS FOR CONTINUALLY MONITORING THE CONDITION OF NUCLEAR REACTOR INTERNALS
A system configured to monitor the structural health of reactor vessel internals of a nuclear reactor is disclosed herein. The system includes a memory configured to store historical information associated with past performance of the nuclear reactor, and an anomaly detection subsystem including a control circuit configured to receive a signal from a sensor. The anomaly detection subsystem is configured to determine, via the control circuit, a characteristic of a vibrational response of the reactor vessel internals based, at least in part, on the signal; access, via the control circuit, the historical information stored in the memory; compare, via the control circuit, the determined characteristic to the historical information stored in the memory; and determine, via the control circuit, a condition of the reactor vessel internals based, at least in part, on the comparison of the determined characteristic and the historical information.
