Annular nuclear fuel rods (100) are disclosed. The annular nuclear fuel rods include an outer cladding tube (102) made of ceramic composite or cermet composite, an inner cladding tube (104) made of ceramic composite or cermet composite, a nuclear fuel region (106) located between the outer cladding tube and inner cladding tube, and an open channel (108) for liquid coolant to flow.
G21C 3/07 - Enveloppes; Chemises caractérisées par le matériau, p.ex. alliages
G21C 3/04 - Eléments combustibles - Détails de structure
G21C 3/64 - Combustible céramique en dispersion, p.ex. cermet
2.
A METHOD AND DEVICE TO CONTROL THE MOVEMENT OF CAPSULES CONTAINING COBALT MATERIAL LOCATED INSIDE CONTAINERS MADE OF NON-FERROMAGNETIC MATERIALS USING THE APPLICATION OF ELECTROMAGNETIC FORCE
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 - Appareils pour enlever des objets ou matériaux radioactifs de l'aire de décharge du réacteur, p.ex. pour les porter à un emplacement de stockage; Appareils pour manipuler des objets ou matériaux radioactifs à l'intérieur d'un emplacement de stockage ou les extraire de celui-ci
G21G 1/02 - Dispositions pour la conversion des éléments chimiques par rayonnement électromagnétique, radiations corpusculaires ou bombardement par des particules, p.ex. production d'isotopes radioactifs dans les réacteurs nucléaires
3.
MODULAR THERMAL AND RADIATION SHIELDING WITH PASSIVE HEAT REMOVAL
A housing assembly (200) configured to house a reactor is disclosed. The housing assembly (200) includes a plurality of modular walls (202, 204) configured to surround the reactor and a passive temperature control system (230). The plurality of modular walls includes (202, 204) a first modular wall (202). The passive temperature control system (230) is coupled to the first modular wall (202). The passive temperature control system (230) is configured to transfer heat between the reactor and an area around the housing assembly (200).
G21C 15/257 - Cyclage du fluide réfrigérant utilisant des tubes caloporteurs
G21F 5/10 - Dispositifs d'évacuation de chaleur spécialement adaptés à ces récipients, p.ex. utilisant une circulation de fluide ou des ailettes de refroidissement
4.
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.
Devices, systems, and methods for power generation using irradiators (102) and other gamma ray sources are disclosed herein. In various aspects, an irradiator-based power generation device (100) is disclosed. The power generation device can include a radiator layer (104) configured to at least partially surround an irradiator (102), wherein the radiator layer (104) comprises a radiator material configured to emit delta radiation in response to exposure to gamma radiation; an electrical insulation layer (108) configured to surround the radiator layer (104), wherein the electrical insulation layer (108) comprises an electrical insulation material configured to allow delta radiation to penetrate therethrough; and a collector layer (110) configured to surround the electrical insulation layer (108), wherein the collector layer (110) comprises a collector material configured to collect delta radiation.
Disclosed is an apparatus, system, and method for monitoring a position of a control rod disposed in a nuclear reactor vessel in a radioactive environment. A data processing unit located outside a containment structure includes a processor and a memory storing executable instructions. A nuclear reactor vessel includes a plurality of control rods proximate to the control rod and a coil stack of a plurality of control rod position indicator coils. A data cabinet mounted on the nuclear reactor vessel head inside the containment structure includes an analog multiplexer and a communication circuit. The processor executes the instructions to select a control rod position indicator coil through the analog multiplexer, pass a signal from the control rod position indicator coil through the analog multiplexer, receive the signal from the analog multiplexer through the communication circuit, and determine a position of the control rod based on the received signal.
G21C 17/12 - Combinaison structurelle de l'élément combustible, de la barre de commande, du cœur du réacteur, ou de la structure du modérateur avec des instruments sensibles, p.ex. pour la mesure de la radioactivité, des contraintes l'élément sensible faisant partie de l'élément de commande
A nuclear reactor core mechanical support bracket is disclosed. The support bracket includes a housing, a spring disposed internally within the housing, a shaft slidingly disposed within the housing and to engage the spring to compress and decompress the spring as the shaft travels in and out of the housing, a shaft travel pin to control the travel of the shaft, and a flange to mount the support bracket to a canister of a nuclear reactor. The shaft includes an inset configured to interface with a nuclear reactor core component.
A method of decontaminating an object removed from a nuclear power plant utilizing a decontamination system is disclosed. The decontamination system includes a platform, an imaging system, a robotic arm including an end effector configured to discharge a decontamination medium, and a control system operably coupled to the imaging system and the robotic arm. The method includes placing the object on the platform, scanning, by the imaging system, the object, generating, by the control system, a three-dimensional model of the object based on the scanned object, planning, by the control system, a decontamination path based on the generated three-dimensional model, controlling, by the control system, a position of the robotic arm according to the planned decontamination path, and discharging, by the end effector, the decontamination medium onto the object at a plurality of positions along the planned decontamination path.
Methods of manufacture for nuclear batteries are provided. The method comprises inserting a radiation source material into a cavity defined within a first component to form a radiation source layer. The first component comprises a first electrical insulator layer defining the cavity and a first casing layer disposed over the first electrical insulator layer. The method comprises contacting the first casing layer with a second casing layer of a second component to form an assembly. The second component comprises a second electrical insulator layer and the second casing layer disposed in contact with the second electrical insulator layer. The method comprises swaging the assembly to form the nuclear battery.
In one aspect, a reactor unit cell (202) is disclosed. The reactor unit cell includes a graphite moderator structure (204), a heat pipe (208) positioned in the graphite moderator structure, and a fuel assembly (210) positioned in the graphite moderator structure. The fuel assembly comprises a beryllium-oxide sleeve (212) and nuclear fuel (214) positioned in the beryllium-oxide sleeve.
G21C 3/07 - Enveloppes; Chemises caractérisées par le matériau, p.ex. alliages
G21C 1/32 - Réacteurs du type intégré, c. à d. réacteurs dans lesquels des parties associées de façon fonctionnelle avec le réacteur, mais non essentielles à la réaction, p.ex. des échangeurs de chaleur, sont disposées à l'intérieur de l'enveloppe avec le cœur
G21C 15/08 - Aménagement ou disposition de passages dans lesquels la chaleur est transférée au réfrigérant, p.ex. pour la circulation du réfrigérant à travers les supports des éléments combustibles provenant du matériau modérateur
G21C 15/257 - Cyclage du fluide réfrigérant utilisant des tubes caloporteurs
11.
SYSTEMS AND METHODS FOR WIRELESS REMOTE CONTROL OF AUTOMATED EQUIPMENT
Systems and methods for the remote control of automated equipment are disclosed herein. The systems and methods include automated equipment configured to execute a process in a restricted location by performing operations based on predetermined programming. In some embodiments, the process is a welding process and the restricted location is a nuclear containment building. The system and methods also include cellular routers configured to enable communication of operating parameters between the automated equipment and a human machine interface (HMI). An operator is able to remotely modify operations of the automated equipment, without being inside of or at the site of the restricted location, by changing the operating parameters using the HMI.
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 17/06 - Dispositifs ou dispositions pour la surveillance ou le test du combustible ou des éléments combustibles en dehors du cœur du réacteur, p.ex. pour la consommation ou pour la contamination
G21C 23/00 - Dispositions dans les réacteurs pour faciliter les expériences ou l'irradiation
G21G 1/02 - Dispositions pour la conversion des éléments chimiques par rayonnement électromagnétique, radiations corpusculaires ou bombardement par des particules, p.ex. production d'isotopes radioactifs dans les réacteurs nucléaires
13.
ENHANCED GRAPHITE NEUTRON REFLECTOR WITH BERYLLIUM OXIDE INCLUSIONS
A nuclear reactor (100) is disclosed that includes a reactor core (102) and a reflector assembly (150) that surrounds the reactor core. The reflector assembly includes a stationary reflector component (152) that includes a graphite support structure (156) including a plurality of channels (158) defined therein and a plurality of beryllium-oxide pins (160) positioned in the channels.
An adjustable core assembly for a nuclear reactor is disclosed herein. The adjustable core can include a plurality of reactivity control cells configured to accommodate a reactivity control rod, and a plurality of unit cells. The plurality of unit cells defines a radial dimension corresponding to an initial power output of the core. Each unit cell of the plurality of unit cells is configured to accommodate fuel configured to generate energy and a heat pipe configured to transfer thermal energy away from the core. Each unit cell of the plurality unit cells can be coupled to an adjacent unit cell in a radial direction, thereby altering the radial dimension, wherein the altered radial dimension corresponds to an adjusted power output of the core, and wherein the adjusted power output of the core is different than the initial power output of the core.
G21C 15/257 - Cyclage du fluide réfrigérant utilisant des tubes caloporteurs
G21C 1/32 - Réacteurs du type intégré, c. à d. réacteurs dans lesquels des parties associées de façon fonctionnelle avec le réacteur, mais non essentielles à la réaction, p.ex. des échangeurs de chaleur, sont disposées à l'intérieur de l'enveloppe avec le cœur
15.
DEVICES, SYSTEMS, AND METHODS FOR CONFIGURING THE LAYOUT OF UNIT CELL OF A REACTOR CORE
A configurable unit cell of a core of a nuclear reactor is disclosed herein. The configurable unit cell includes a core block material and a plurality of interchangeable components configured to affect a performance parameter of the core of the nuclear reactor. The configurable unit cell further includes a plurality of channels defined within the core block material. Each channel of the plurality of channels is configured to engage an interchangeable component of the plurality of interchangeable components in an operating configuration. Each channel of the plurality of channels is separated from an adjacent channel of the plurality of channels by a predetermined pitch.
G21C 3/322 - Moyens pour influencer l'écoulement du réfrigérant à travers ou autour des faisceaux
G21C 5/02 - Structure du modérateur ou du cœur; Emploi de matériaux spécifiés comme modérateur - Détails
G21C 5/12 - Structure du modérateur ou du cœur; Emploi de matériaux spécifiés comme modérateur caractérisée par la composition, p.ex. le modérateur contenant des substances additionnelles qui assurent une meilleure résistance du modérateur
G21C 11/06 - Ecrans réflecteurs, c. à d. pour minimiser la perte de neutrons
G21C 15/08 - Aménagement ou disposition de passages dans lesquels la chaleur est transférée au réfrigérant, p.ex. pour la circulation du réfrigérant à travers les supports des éléments combustibles provenant du matériau modérateur
G21C 15/257 - Cyclage du fluide réfrigérant utilisant des tubes caloporteurs
16.
DEVICES, SYSTEMS, AND METHODS FOR REMOVING HEAT FROM A NUCLEAR REACTOR CORE
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.
A device configured to measure radioactivity emitted by a plurality of radionuclides is disclosed herein. The device includes a gamma detector and a source cage with an outer ring that defines a volume and includes an orientation feature and a plurality of holes configured to receive a radionuclide of the plurality of radionuclides. The device also includes a frame that includes an arm and a central rod, wherein the arm is configured to be coupled to the outer ring and includes an orientation pin. The central rod can be positioned relative to the volume when the arm is coupled to the outer ring of source cage. The orientation feature of the source cage is configured to engage the orientation pin of the arm and, when the orientation pin engages the orientation feature, the central rod is in a predetermined location relative to the volume.
G01N 35/00 - Analyse automatique non limitée à des procédés ou à des matériaux spécifiés dans un seul des groupes ; Manipulation de matériaux à cet effet
G01T 7/02 - Moyens de collection pour recevoir ou conserver des échantillons à examiner
18.
COATED FUEL PELLETS WITH ENHANCED WATER AND STEAM OXIDATION RESISTANCE
Disclosed herein is a method comprising coating a fissile, uranium-containing ceramic material (72) with a water-resistant layer (74), the layer being non-reactive with the fissile, uranium-containing ceramic material. The coating is applied to a surface of the fissile, uranium-containing ceramic material. Also disclosed is a fuel for use in a nuclear reactor.
G21C 3/20 - Eléments combustibles - Détails de structure - Détails de structure à l'intérieur de l'enveloppe avec une intercouche non active entre l'enveloppe et le matériau actif
G21C 3/04 - Eléments combustibles - Détails de structure
G21C 7/04 - Commande de la réaction nucléaire par utilisation des propriétés autorégulatrices des matériaux du réacteur de poisons combustibles
G21C 21/02 - Fabrication des éléments combustibles ou surrégénérateurs à l'intérieur de gaines non-actives
19.
METHOD AND SYSTEM 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.
G21C 19/22 - Dispositions pour avoir accès à l'intérieur de l'enceinte sous pression pendant le fonctionnement du réacteur
G21G 1/02 - Dispositions pour la conversion des éléments chimiques par rayonnement électromagnétique, radiations corpusculaires ou bombardement par des particules, p.ex. production d'isotopes radioactifs dans les réacteurs nucléaires
20.
SELF-POWERED NUCLEAR RADIATION DETECTOR AND METHOD OF CORRECTING A TEMPERATURE-RELATED CHANGE OF AN OUTPUT SIGNAL OF SAME
A self-powered nuclear radiation detector. The self-powered nuclear radiation detector includes a cable assembly, a temperature compensation assembly, and a metallic outer sheath. The cable assembly includes a metallic signal lead, an insulative material surrounding the metallic signal lead, and a metallic sheath surrounding the insulative material. The temperature compensation assembly includes a second metallic signal lead, a second insulative material surrounding the second metallic signal lead, and a second metallic sheath surrounding the second insulative material. The metallic outer sheath surrounds the cable assembly and the temperature compensation assembly.
A manipulator configured to navigate a heat exchanger including a plurality of tubes extending through a tubesheet is disclosed herein, the manipulator including a first end effector, a second end effector, and an articulation assembly. The first end effector is configured to accommodate an instrument configured to service the heat exchanger and includes a first actuator configured to extend a first gripper into a tube of the plurality of tubes. The second end effector includes a second actuator configured to extend a second gripper into a tube of the plurality of tubes. The first and second gripper are configured to secure the manipulator to the tubesheet, and, when the second gripper is securing the manipulator to the tubesheet, the articulation assembly is configured to enable the first end effector to move relative to the second end effector in a plane that is parallel to the tubesheet.
B25J 9/04 - Manipulateurs à commande programmée caractérisés par le mouvement des bras, p.ex. du type à coordonnées cartésiennes par rotation d'au moins un bras en excluant le mouvement de la tête elle-même, p.ex. du type à coordonnées cylindriques ou polaires
22.
METHODS AND SYSTEMS FOR SEPARATION OF THORIUM FROM URANIUM AND THEIR DECAY PRODUCTS
Methods and systems (300) for separation of thorium from uranium and their decay products are provided. The method comprises combining a nuclear fuel feedstock (102) comprising thorium and uranium with a first acid (104, 204) to form a first solution. The first solution is contacted an ion exchange resin (308) that is selective for thorium or uranium. The thorium or uranium is at least partially removed from the first solution by binding the thorium or uranium to the ion exchange resin (308) thereby forming a second solution (106 206). The second solution (106, 206) is combined with oxalic acid to precipitate uranium or thorium from the second solution to form a precipitate (110, 210). The precipitate (110, 210) is separated from the second solution (106, 206).
G21G 4/08 - Sources radioactives autres que les sources de neutrons caractérisées par des aspects de leur structure spécialement adaptées aux applications médicales
23.
COMPACT PASSIVE DECAY HEAT REMOVAL SYSTEM FOR TRANSPORTABLE MICRO-REACTOR APPLICATIONS
A container for transporting a reactor is disclosed. The container includes a loop thermosiphon including a chamber, a heat exchanger fluidically coupled to the chamber, and an actuator including an unactuated state and an actuated state. The actuator is configured to automatically transition to the actuated state. The transition is based on an event occurring within the reactor. A working medium is configured to remove heat from the reactor in the actuated state.
A forming assembly configured to form a wick is disclosed. The forming assembly includes an expandable tube and a forming shell assembly. The expandable tube is hydraulically expandable to an expanded configuration. A wick mesh is configured to be wrapped about the expandable tube. The forming shell assembly includes a first forming shell comprising a first recess defined therein and a second forming shell comprising a second recess defined therein. The first recess and the second recess cooperate to define an outer diameter of the wick. The expandable tube and the wick mesh are positionable between the first recess and tire second recess, lire expandable tube and the forming shell assembly are configured to deform the wick mesh and form the wick based on the expandable tube hydraulically expanding towards the expanded configuration.
A forming assembly for forming a wick is disclosed. The forming assembly includes a tube inflatable to an inflated configuration. A wick mesh is configured to be wrapped about the tube. The forming assembly further includes a sheath positionable about the tube and the wick mesh. The tube and the sheath are configured to compress the wick mesh and form the wick based on the tube inflating towards the inflated configuration.
B21D 39/04 - Utilisation de procédés permettant d'assembler des objets ou des parties d'objets, p.ex. revêtement par des tôles, autrement que par placage; Dispositifs de mandrinage des tubes des tubes avec des barres
F28D 15/04 - Appareils échangeurs de chaleur dans lesquels l'agent intermédiaire de transfert de chaleur en tubes fermés passe dans ou à travers les parois des canalisations dans lesquels l'agent se condense et s'évapore, p.ex. tubes caloporteurs avec des tubes ayant une structure capillaire
26.
A 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 heat pipe is disclosed to include a container, a container lid which includes a groove defined therein, a wick, and an end plug operably coupled to the wick. The end plug includes a pin extending therefrom, and the groove of the container lid is configured to receive the pin.
F28D 15/04 - Appareils échangeurs de chaleur dans lesquels l'agent intermédiaire de transfert de chaleur en tubes fermés passe dans ou à travers les parois des canalisations dans lesquels l'agent se condense et s'évapore, p.ex. tubes caloporteurs avec des tubes ayant une structure capillaire
28.
HIGH TEMPERATURE HYDRIDE MODERATOR ENABLING COMPACT AND HIGHER POWER DENSITY CORES IN NUCLEAR MICRO-REACTORS
A reactor core block (200) is disclosed including a fuel channel (202), a heat pipe (204), a primary moderator matrix (206) configured to encompass the fuel channel (202) and the heat pipe (204), and a secondary moderator channel (208) configured to at least partially surround the fuel channel (202), the heat pipe (204), and the primary moderator matrix (206). The secondary moderator channel (208) is comprised of metal hydride.
G21C 15/257 - Cyclage du fluide réfrigérant utilisant des tubes caloporteurs
G21C 1/16 - Réacteurs hétérogènes, c. à d. dans lesquels le combustible et le modérateur sont séparés le modérateur n'étant pas substantiellement pressurisé, p.ex. réacteur à pile piscine le modérateur et le réfrigérant étant différents ou séparés, p.ex. réacteur sodium-graphite
G21C 5/12 - Structure du modérateur ou du cœur; Emploi de matériaux spécifiés comme modérateur caractérisée par la composition, p.ex. le modérateur contenant des substances additionnelles qui assurent une meilleure résistance du modérateur
G21D 5/02 - Réacteur et moteur structurellement combinés, p.ex. portatifs
29.
METAL WICK CRIMPING METHOD FOR HEAT PIPE INTERNALS
A wick assembly for use with a heat pipe is disclosed. The wick assembly includes an end plug including a wick receiving area, a wick, and a crimp. A portion of the wick is positioned about the wick receiving area. The crimp is positioned about the portion of the wick and the wick receiving area. The end plug, the portion of the wick, and the crimp are diffusion bonded.
F28D 15/04 - Appareils échangeurs de chaleur dans lesquels l'agent intermédiaire de transfert de chaleur en tubes fermés passe dans ou à travers les parois des canalisations dans lesquels l'agent se condense et s'évapore, p.ex. tubes caloporteurs avec des tubes ayant une structure capillaire
G21C 15/257 - Cyclage du fluide réfrigérant utilisant des tubes caloporteurs
A block style heat exchanger for a heat pipe reactor having a plurality of heat pipes extending from a reactor core. The heat exchanger includes a plurality of primary channels, each for receiving heat transferred from the core via one of the heat pipes. The primary channels extending within a block of one or more materials. The heat exchanger also includes a plurality of secondary channels defined within the block for transmitting a flow of the secondary heat transfer medium through the heat exchanger from an inlet to an outlet. The block is formed from one or both of: a plurality of plates bonded together, with each plate defining at least a portion of one or more of the plurality of primary channels and/or the plurality of secondary channels, and/or a unitary piece of material formed from an additive manufacturing process.
A system for use in shutting down a nuclear reactor includes a housing that defines a region therein sealed from an ambient environment and a gate member disposed within the region in a manner such that the gate member segregates the region into a first compartment and a second compartment isolated from the first compartment. The gate member is formed from a material having a predetermined melting point. The system further includes a neutron absorbing material disposed within the first compartment and a dispersion mechanism disposed within the region. The dispersion mechanism structured to encourage the neutron absorbing material from the first compartment into the second compartment.
A runner assembly for mounting to, and rotating with, a pump shaft of a pump includes a support member to be fixed to the pump shaft; a seal face ring positioned on, and mounted to the support member by a support shroud coupled to the support member; and an outer O-ring positioned in an upward and radially outward facing notch defined in a top portion of the support member. The outer O-ring forms a static sealed joint between the top of the support member and the bottom of the seal face ring.
Disclosed herein is a method (300) pertaining to a power distribution of a reactor core of a nuclear installation, the method being executed on a general purpose computer. The method (300) comprises: measuring current values from a plurality of vanadium neutron detector assemblies (10) which are disposed in the reactor core of the nuclear installation (302); determining a measured relative core power distribution based upon the measured current values (304); producing a measured core power distribution based upon the measured relative core power distribution (306); and verifying that the reactor is operating within the licensed core operating limits based at least in part upon the measured core power distribution (308). Also disclosed herein is a vanadium neutron detector (1-5) assembly (10).
A motor control center circuit breaker replacement kit includes a standoff having a first plurality of mounting holes corresponding to existing holes on a bucket of the motor control center and a second plurality of holes corresponding to existing holes on a circuit breaker, a door interface panel having a third plurality of holes corresponding to existing holes on a door of the motor control center, the door interface panel having an opening formed therein having a size and shape corresponding to a handle operator associated with the circuit breaker, and a safety latch having a slot structured to receive a tab of the handle operator.
An ultrasonic testing probe operable to perform an ultrasonic inspection on a workpiece, the workpiece having an interior region. The testing probe comprises a support; an ultrasonic testing element that is structured to generate an ultrasonic output that is directed toward the workpiece and to receive an ultrasonic input from the workpiece that is responsive to the ultrasonic output, the ultrasonic testing element being movably situated on the support; a motor apparatus structured to be electrically connected with a control apparatus, the motor apparatus comprising a motor that is connected with the ultrasonic testing element and is structured to rotate the ultrasonic testing element with respect to the support; and a bladder that is structured to be movable between an initial state and an expanded state, the expanded bladder structured to be engaged with the workpiece within the interior region and to center the support in the interior region.
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 - Recherche ou analyse des matériaux par l'emploi d'ondes ultrasonores, sonores ou infrasonores; Visualisation de l'intérieur d'objets par transmission d'ondes ultrasonores ou sonores à travers l'objet - Détails pour établir le couplage acoustique
37.
MODULAR RADIOISOTOPE PRODUCTION CAPSULES AND RELATED METHOD
A radioisotope production capsule is described. Each capsule includes generally an inner container for housing one of a target material and a neutron moderator, an outer container surrounding the inner container for housing the one of the target material and the neutron moderator not housed by the inner container, and cladding for isolating the target material from the neutron moderator. One or more modular capsules are placed in each of a plurality of plug fingers. Each single plug finger loaded with one or more capsules is inserted into a guide thimble of an array of guide thimbles in a fuel assembly.
G21G 1/02 - Dispositions pour la conversion des éléments chimiques par rayonnement électromagnétique, radiations corpusculaires ou bombardement par des particules, p.ex. production d'isotopes radioactifs dans les réacteurs nucléaires
38.
APPARATUS FOR PERFORMING IN-SITU ADHESION TEST OF COLD SPRAY DEPOSITS AND METHOD OF EMPLOYING
A testing arrangement and method of using in performing an in-situ adhesion test of a cold spray deposit on a surface of a structure. The testing arrangement includes a specimen member having a number of apertures defined therein and a loading arrangement coupled to the specimen member. The loading arrangement is configured to provide a mechanical force of a known magnitude to the specimen member. In performing an in-situ test of a cold spray deposit on a structure, the method includes positioning the testing arrangement with respect to a surface of the structure, depositing the cold spray deposit on the surface of the structure, and testing the adhesion of the cold spray deposit to the surface.
A sensor system for a fuel rod including a fuel pellet (150) stack, the sensor system including a wireless interrogator (50) disposed outside the fuel rod (2) and a passive sensor component (60) disposed within the fuel rod. The passive sensor component includes a receiver (62) structured to receive an interrogation signal and output an excitation signal in response to receiving the interrogation signal, a reference transmitter (64) structured to output a reference signal to the reference receiver (54) in response to the excitation signal, a sensing transmitter (66) structured to output a sensing signal to the sensing receiver (56) in response to the excitation signal, and a core (130) at least partially disposed within the sensing transmitter and coupled to move in conjunction with expansion or contraction of the fuel pellet stack, to move based on changes in pressure within the fuel rod, or to change temperature based on temperature changes within the fuel rod.
G21C 17/10 - Combinaison structurelle de l'élément combustible, de la barre de commande, du cœur du réacteur, ou de la structure du modérateur avec des instruments sensibles, p.ex. pour la mesure de la radioactivité, des contraintes
H04Q 9/00 - Dispositions dans les systèmes de commande à distance ou de télémétrie pour appeler sélectivement une sous-station à partir d'une station principale, sous-station dans laquelle un appareil recherché est choisi pour appliquer un signal de commande ou
A method is described herein that produces UN from UF6 in at most two steps comprising UF6 -intermediate -> UN. The principle of the reaction is that in a first step, UF6 would be reduced to UxNy, where x may be an integer selected from 1 and 3, and y is an integer selected from 1 and 2. Reduction occurs at or near the surface of a gaseous membrane electrode (18) where it is also in contact with a nitrogen bearing salt. In a second step, UxNy decomposes to UN and N2 gas, either in the same reactor (16, 216) as the first step or after removal to a separate unit (217) for further processing.
A rod position indication system is disclosed. The rod position indication system includes first coils and second coils disposed around a drive rod travel housing in an alternating arrangement, a first data encoder unit connected to each of the first coils and configured to generate a first reference signal, a second data encoder unit connected to the each of the second coils and configured to generate a second reference signal, and a processing circuit in signal communication with the first and second data encoder units. The processing circuit is configured to generate a logic comparison of the first and second reference signals, generate a logic signal based on first position data and second position data, and perform a logic operation on the logic signal and a result of the logic comparison.
G01D 5/00 - Moyens mécaniques pour le transfert de la grandeur de sortie d'un organe sensible; Moyens pour convertir la grandeur de sortie d'un organe sensible en une autre variable, lorsque la forme ou la nature de l'organe sensible n'imposent pas un moyen de conversion déterminé; Transducteurs non spécialement adaptés à une variable particulière
G01D 5/22 - Moyens mécaniques pour le transfert de la grandeur de sortie d'un organe sensible; Moyens pour convertir la grandeur de sortie d'un organe sensible en une autre variable, lorsque la forme ou la nature de l'organe sensible n'imposent pas un moyen de conversion déterminé; Transducteurs non spécialement adaptés à une variable particulière utilisant des moyens électriques ou magnétiques influençant la valeur d'un courant ou d'une tension en faisant varier l'inductance, p.ex. une armature mobile influençant deux bobines par une action différentielle
G21C 7/08 - Commande de la réaction nucléaire par application de matériau absorbant les neutrons, c. à d. matériau avec section efficace d'absorption excédant largement la section efficace de réflexion par déplacement des éléments de commande solides, p.ex. barres de commandes
42.
METHOD AND SYSTEM TO DETECT AND LOCATE THE IN-CORE POSITION OF FUEL BUNDLES WITH CLADDING PERFORATIONS IN CANDU-STYLE NUCLEAR REACTORS
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 cl adding tubes. The method includes monitoring channels for the occurrence of an increase in radiation above selected base lines indicative of the presence of at least one fission product in the coolant in at least one of the plurality7 of channels, 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 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 channel s 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 - Mesure de l'intensité de radiation avec des détecteurs à semi-conducteurs
G21C 17/10 - Combinaison structurelle de l'élément combustible, de la barre de commande, du cœur du réacteur, ou de la structure du modérateur avec des instruments sensibles, p.ex. pour la mesure de la radioactivité, des contraintes
H01L 31/108 - Dispositifs sensibles au rayonnement infrarouge, visible ou ultraviolet caractérisés par une seule barrière de potentiel ou de surface la barrière de potentiel étant du type Schottky
H01L 31/118 - Dispositifs sensibles au rayonnement d'ondes très courtes, p.ex. rayons X, rayons gamma ou rayonnement corpusculaire du type détecteurs à barrière de surface ou à jonction PN superficielle, p.ex. détecteurs de particules alpha à barrière de surface
A calibration system is disclosed. The calibration system includes a waveform generator configured to generate a periodic waveform and a control circuit in signal communication with the waveform generator. The control circuit includes an analog-to-digital converter configured to convert the periodic waveform to digital values and an electronic device in signal communication with the analog-to-digital converter. The electronic device is configured to verify calibration of (1) timing of the control circuit and (2) voltage levels of the control circuit based on the periodic waveform.
The invention relates to SiC ceramic matrix composite (CMC) claddings with metallic, ceramic and/or multilayer coatings applied on the outer surface for improved corrosion resistance and hermeticity protection. The coating includes one or more materials selected from FeCrAl, Y, Zr and Al-Cr alloys, Cr2O3, ZrO2 and other oxides, chromium carbides, CrN, Zr- and Y-silicates and silicides. The coatings are applied employing a variety of known surface treatment technologies including cold spray, thermal spray process, physical vapor deposition process (PVD), and slurry coating.
Systems and methods including a material that emits high energy beta particles to destroy cancer cells contained in cancerous tumor or tissue. Electronic neutron generators produce neutrons with energies that have a high probability to interact with the material yttrium-89 to produce yttrium-90. Yttrium-90 emits beta radiation with a maximum energy of about 2.25 MeV and a half-life of about 64 hours, which decays to stable zirconium. Stable yttrium-89 can be directly placed in or around cancerous tissue and irradiated with neutrons in the 0.1-15 KeV energy range to produce significant amounts of yttrium-90. The beta radiation emitted by yttrium-90 will primarily destroy the more radiation sensitive cancer cells within the range of the beta particles. The resulting zirconium isotope is not radioactive such that no further radiation is released. A low probability gamma is also created that will assist in cancer cell destruction.
A61N 5/10 - Radiothérapie; Traitement aux rayons gamma; Traitement par irradiation de particules
A61K 41/00 - Préparations médicinales obtenues par traitement de substances par énergie ondulatoire ou par rayonnement corpusculaire
A61K 51/12 - Préparations contenant des substances radioactives utilisées pour la thérapie ou pour l'examen in vivo caractérisées par un aspect physique particulier, p.ex. émulsion, microcapsules, liposomes
The invention relates to UF6 transport and process containers to store UF6 enriched up to 20 percent by weight 235U in amounts up to 1,500 kg U. The containers include a shell, which has an integral heat exchanger positioned between the exterior and interior surfaces/substrates of the shell. The integral heat exchanger is composed of metal passage voids to pass heat transport fluid. The shell forms an inner chamber, and a partition configuration is positioned within the inner chamber, extending longitudinally along the length of the container, to form a plurality of individual compartments within the inner chamber to store the UF6. The containers may be produced by additive manufacturing methods.
G21F 5/10 - Dispositifs d'évacuation de chaleur spécialement adaptés à ces récipients, p.ex. utilisant une circulation de fluide ou des ailettes de refroidissement
47.
THERAPEUTIC ELECTRON RADIATOR FOR CANCER TREATMENT
A method that produces high energy charged particles that may be used to destroy cancer cells contained in cancerous tissues. The device uses electronic neutron generators to produce neutrons with energies that have a high probability to interact with a therapeutic source comprised of a reactive material with an outer layer of a material having a high atomic number such as Platinum or Gold. The reaction produces high energy electrons, and in some cases other charged particles with relatively short half-lives, which can destroy the cancerous cells, without seriously damaging the surrounding healthy tissue.
A printed circuit heat exchanger for use in a reactor includes a core formed from a stack of plates diffusion bonded together. The core has: a top face, a bottom face disposed opposite the top face, a first side face extending between the top face and the bottom face, and a second side face disposed opposite the first side face. The printed circuit heat exchanger includes: a plurality of primary channels defined in the core, each of the primary channels extending from a primary inlet defined in the first side face to a primary outlet defined in the second side face; and a plurality of secondary channels defined in the core, each of the secondary channels extending among at least some of the primary channels from a secondary inlet defined in the top face to a secondary outlet defined in the top face.
G21C 15/02 - Aménagement ou disposition de passages dans lesquels la chaleur est transférée au réfrigérant, p.ex. pour la circulation du réfrigérant à travers les supports des éléments combustibles
G21C 1/03 - Réacteurs de fission rapides, c. à d. réacteurs n'utilisant pas de modérateur refroidis par un réfrigérant non nécessairement pressurisé, p.ex. réacteurs du type piscine
49.
A REMOVABLE MANDREL FOR AUTOMATING PROCESS TO MANUFACTURE CERAMIC COMPOSITE NUCLEAR FUEL CLADDING TUBES
The method described herein uses a ceramic precursors and controlled temperature rises for forming a stiffened ceramic composite fiber matrix to form a ceramic composite fuel cladding tube of the desired geometry and for removing a mandrel about which the composite fiber matrix was formed. The method described herein allows the manufacture of elongated ceramic composite claddings where the mandrel used to define the geometry of the cladding is easily removed without damaging the ceramic composite cladding. The method includes covering ceramic fibers with a mixture comprising at least one precursor of a ceramic material, wrapping the precursor covered fibers around a mandrel, heating the precursor covered fibers to the decomposition temperature of the precursor to convert the precursor to the ceramic material, and heating the mandrel to at least the melting point thereof to remove the mandrel.
A method of employing an eddy current sensor to perform an inspection of a tube of a steam generator involves accelerating and decelerating the eddy current sensor in a predetermined fashion that substantially reduces the likelihood of damage to the eddy current sensor. The reduction of probe stresses reduces radiological waste and reduces radiation exposure to workers involved in changing damaged probes The recording of an eddy current signal at each of a plurality of equally spaced apart locations along the tube permits the velocity of the eddy current sensor to be varied without compromising the validity of the data that has been recorded. The inspection system employs an encoder that outputs a series of signals as the probe is advanced incremental distances within the tube of the steam generator, and eddy current sensor signals are recorded responsive to at least some to be signals from the encoder.
A means for installing material, through a fuel assembly instrument thimble insert, into the existing instrument thimbles in nuclear fuel assemblies for the purpose of allowing the material to be converted to commercially valuable quantities of desired radioisotopes during reactor power operations during a remainder of a fuel cycle and removing the radioisotopes from the core through the reactor flange opening once the fuel assemblies have been removed for refueling. The invention also describes methods that can be used to harvest the irradiated material so it can be packaged for transportation from the reactor to a location where the desired radioisotope(s) can be extracted from the fuel assembly instrument thimble insert.
G21C 19/20 - Dispositions pour introduire des objets à l'intérieur de l'enceinte sous pression; Dispositions pour manipuler des objets à l'intérieur de l'enceinte sous pression; Dispositions pour extraire des objets de l'enceinte sous pression
The invention relates to systems, apparatus and methods for the removal of cesium and other radionuclides from liquid waste contained in a high level waste tank. The invention includes transporting a stream of the liquid waste from the high level waste tank to one or more ion-exchange column assemblies to remove the cesium therefrom using a sorbent, such as, crystalline silico-titanate. The ion-exchange column assemblies include an ion-exchange column and an integrated shield. The column is concentrically positioned within the shield and an air gap is present between the column and the shield to provide passive cooling.
G21F 5/10 - Dispositifs d'évacuation de chaleur spécialement adaptés à ces récipients, p.ex. utilisant une circulation de fluide ou des ailettes de refroidissement
53.
CHEMICAL PROCESS FOR PRIMARY SYSTEM MATERIAL PASSIVATION DURING HOT FUNCTIONAL TESTING OF NUCLEAR POWER PLANTS
The present invention relates to a pre-core hot functional testing (HFT) preconditioning process, which includes the introduction of chemical additives, e.g., zinc, into coolant water that circulates through the primary system of a new nuclear power plant, at various temperatures. The chemical additives contact the primary system surfaces, which results in the formation of a protective zinc-containing oxide film on the fresh surfaces to control corrosion release and deposition during subsequent normal operation of the nuclear power plant. The method includes a series of three chemistry phases to optimize the passivation process: 1) an alkaline-reducing phase, 2) an acid-reducing phase and 3) an acid-oxidizing phase.
This invention relates to compositions and methods for the at least partial dissolution, disruption and/or removal of deposit, such as scale and other deposit, from heat exchanger components. The heat exchanger components can include pressurized water reactor steam generators. In accordance with the invention, elemental metal is added locally to the surface of the deposit and/or anodic or cathodic current is applied locally to the deposit surface to destabilize or weaken the deposit. Subsequently, mechanical stress is applied to the weakened deposit to disrupt and remove the deposit from the surface of the heat exchanger component.
This invention generally concerns radioactive decontamination of deposits on components in a nuclear power plant and is specifically concerned with improved systems and methods for disrupting, dissolving, removing and reducing at ambient temperature radionuclides formed on the primary side surfaces of components in a pressurized water reactor and the internal components of a boiling water reactor. The methods include identifying the structure, taking the structure out of operational service, contacting the structure with an aqueous solution (e.g., a recirculating flow or static immersion), and adding an effective amount of elemental metal in solid form to the aqueous solution.
A fuel assembly handling tool that can be lowered onto the top nozzle of a fuel assembly, positively latch the top nozzle, unlatch from the top nozzle, and be raised off the top nozzle of the fuel assembly. The tool head, that interfaces with the top nozzle has load bearing grippers that latch onto the fuel assembly, that are located in a storage position up within the tool while the tool is lowered onto the fuel assembly. The gripper fingers are then lowered into position during the latching process, and are raised back to the storage position during the unlatching process. In the storage position, the gripping fingers are spaced above the fuel assembly top nozzle when the tool head is resting on the nozzle.
A wet filter for a nuclear reactor primary containment vent that employs an inclined manifold having a plurality of outlets that communicate through a first set of metal fiber filters submerged in a pool of water enclosed within a pressure vessel. A demister suspended above the pool of water to remove any entrained moisture in the filtered effluent before being passed through a second stage of higher density, dry, metal fiber filters connected to a second manifold that communicates with an outlet on the pressure vessel that is connected to an exhaust passage to the atmosphere.
G21C 13/02 - Enceintes sous pression; Enceintes d'enveloppe; Enveloppes en général - Détails
B01D 53/00 - SÉPARATION Épuration chimique ou biologique des gaz résiduaires, p.ex. gaz d'échappement des moteurs à combustion, fumées, vapeurs, gaz de combustion ou aérosols
The present invention relates to a control rod drive mechanism assembly for a nuclear reactor having a nuclear reactor vessel, a nuclear reactor core, a reactor vessel head, a latch housing nozzle, a latch housing, a rod travel housing, a latch assembly, a drive rod assembly and a rod control cluster assembly. The latch housing is integrated with the latch housing nozzle, the rod travel housing is welded to the latch housing, and the latch assembly is connected to the rod travel housing. The latch assembly includes the drive rod assembly and the rod control cluster assembly which is attached to the drive rod assembly.
This invention relates to compositions and methods for the at least partial dissolution, disruption and/or removal of deposits, such as scale and other deposits, from heat exchanger components. The heat exchanger components can include pressurized water reactor steam generators. The pressurized water reactor steam generators can be in a wet layup condition. The compositions include elemental metal and complexing agent selected from the group consisting of sequestering agent, chelating agent, dispersant, and mixtures thereof. The methods include introducing the compositions into the heat exchanger components.
C23G 5/00 - Nettoyage ou dégraissage des matériaux métalliques par d'autres méthodes; Appareils pour le nettoyage ou le dégraissage de matériaux métalliques au moyen de solvants organiques
C02F 5/08 - Traitement de l'eau avec des produits chimiques complexants ou des agents solubilisants pour l'adoucissement, la prévention ou l'élimination de l'entartrage, p.ex. par addition d'agents séquestrants
A modular plate and shell heat exchanger in which welded pairs of heat transfer plates are tandemly spaced and coupled in parallel between an inlet and outlet conduit to form a heat transfer assembly. The heat transfer assembly is placed in the shell in order to transfer heat from a secondary to a primary fluid. Modules of one or more of the heat transfer plates are removably connected using gaskets at the inlet and outlet conduits which are connected to a primary fluid inlet and a primary fluid outlet nozzle. The heat transfer assembly is supported by a structure which rests on an internal track which is attached to the shell and facilitates removal of the heat transfer plates. The modular plate and shell heat exchanger has a removable head integral to the shell for removal of the heat transfer assembly for inspection, maintenance and replacement.
The invention relates to systems and methods for conducting an ultrasonic, nondestructive evaluation and inspection of a pipe using Lamb-type wave transducers to detect the presence of defects, flaws, discontinuities and the like. The transducers are positioned within the interior space of the pipe. Two transducers are positioned facing each other such that the ultrasonic beam emitted from each of the transducers is directed toward the other transducer and the portion of pipe to be inspected. The coverage of the transducers is verified and the results are processed using a combination of a cross correlation filter and a signal processing tool.
An improved control circuit that is structured to energize another device such as a squib. A first portion of the circuit includes a first transistor and is structured to discharge at a first rate a first portion of a charge stored by a capacitor. Another portion of the circuit includes a second transistor and is structured to discharge a second portion of the charge subsequent to the discharge of the first portion of the charge and at a second rate greater than the first rate.
H02J 7/00 - Circuits pour la charge ou la dépolarisation des batteries ou pour alimenter des charges par des batteries
F42C 15/40 - Dispositifs d'armement des fusées; Dispositifs de sécurité pour empêcher l'explosion prématurée des fusées ou des charges dans lesquels l'action de sécurité ou d'armement s'effectue électriquement
F42C 15/44 - Dispositions pour désarmer des fusées ou pour les rendre inoffensives après l'armement, p.ex. après le lancement
A blocking device for preventing the actuation of an automatic depressurization system in a pressurized nuclear reactor system due to spurious signals resulting from a software failure. The blocking signal is removed when the coolant level within the core makeup tanks drop below a predetermined level.
A tube and shell steam generator in which a series of rods having a diameter substantially equal to that of the heat exchange tubing in the tube bundle are placed on either side of the tube lane to buffer the flow in the tube lane from the heat exchange tubes to attenuate turbulent forces on the first several rows of heat exchange tubes adjacent to the tube lane.
A method of designing/making an acoustic side branch resonator (36) structured to be coupled to a standpipe (32) of, for example, a nuclear power plant, wherein the acoustic side branch resonator includes a plurality of wire mesh elements (58) for damping purposes. The method includes determining a resonant frequency of the standpipe, determining an active length of the acoustic side branch resonator using the resonant frequency, and determining a particular number of the wire mesh elements to be used in the acoustic side branch resonator and a pitch of each of the wire mesh elements using momentum and continuity equations of a compressible fluid.
G10K 11/02 - Impédances acoustiques mécaniques; Adaptation d'impédance, p.ex. au moyen de pavillons; Résonateurs acoustiques
F16L 55/02 - Absorbeurs d'énergie; Absorbeurs de bruit
F16L 55/04 - Dispositifs amortisseurs de vibrations ou de pulsations dans les fluides
F17D 1/20 - Aménagements ou ensembles de dispositifs pour influencer ou modifier les caractéristiques dynamiques des systèmes, p.ex. pour amortir les pulsations dues à l'ouverture ou à la fermeture des vannes
G10K 11/16 - Procédés ou dispositifs de protection contre le bruit ou les autres ondes acoustiques ou pour amortir ceux-ci, en général
An in-core neutron monitor that employs vacuum microelectronic devices to configure an in-core instrument thimble assembly that monitors and wirelessly transmits a number of reactor parameters directly from the core of a nuclear reactor without the use of external cabling. The in-core instrument thimble assembly is substantially wholly contained within an instrument guide tube within a nuclear fuel assembly.
A method and apparatus for monitoring a parameter in an irradiated environment and communicating a signal representative of the monitored parameter to a less caustic environment that employs a wireless transmitter that is powered by the irradiated environment. The power for the wireless transmitter is derived from a self-powered radiation detector disposed within the radioactive environment.
This invention relates to an in-situ cleaning fixture for demister separator vane assemblies. The cleaning fixture includes an injection chamber with an inlet and a perforated plate which extends horizontally, substantially over the length of the demister separator vane assembly. A cleaning fluid source is connected to the injection chamber during a cleaning process. The injection chamber is designed to receive the cleaning fluid, pass the cleaning fluid through the holes formed in the plate, downwardly along a plurality of vanes in the demister separator vane assembly and into the drain trough. The in-situ cleaning fixture facilitates removal of scale build-up from the demister separator vane assembly and thereby restores the efficacy of the vanes.
A means of offsetting semi-circular tube support plates typically present in heat exchangers with cross flow baffles, such as axial flow economizers, utilizing the motive force of steam generator pressurization. The offset slightly flexes the tubes, thereby providing a preload which minimizes the potential for tube vibration and wear.
A fixture for performing visual inspections of the underside of the top guide of a boiling water reactor. The inspections are performed in the reactor vessel, under water, and includes a framed structure that rests on top of the top guide and supports a wheel track within a fuel assembly opening in the top guide, that follows the contour of the opening. A camera support, suspended from the frame, is then remotely, manually rotated to follow the contour of the wheel track as the fixture maintains the camera at a fixed angle and known constant distance from the underside of the top guide.
This invention relates to a computational system and method for performing a safety analysis of a postulated Loss of Coolant Accident in a nuclear reactor for a full spectrum of break sizes including various small, intermediate and large breaks. Further, modeling and analyzing the postulated small break, intermediate break and large break LOCAs are performed with a single computer code and a single input model properly validated against relevant experimental data. Input and physical model uncertainties are combined following a random sampling process, e.g., a direct Monte Carlo approach (ASTRUM-FS) and advanced statistical procedures are utilized to show compliance with Nuclear Regulatory Commission 10 CFR 50.46 criteria.
A method of eddy current testing for flaws in a tube is provided that includes passing an eddy current probe through the tube and obtaining eddy current data for a number of positions along the tube, analyzing the eddy current data to generate background noise data for a number of positions along the tube, analyzing the eddy current data to generate extracted data for a number of positions along the tube, and determining whether a flaw of a particular category is present in the tube based on a set of one or more of rules applied to at least a portion of the extracted data, wherein at least one of the rules uses a particular part of the extracted data and employs a threshold that is a function a particular part of the background noise data that is associated with the particular part of the extracted data.
A telescoping rod control cluster assembly change tool for moving control rod assemblies among fuel assemblies in a nuclear facility. The operation of the tool is completely mechanical and the telescoping feature enables the tool to have a relatively low profile when it is being moved and stored without housing a control rod assembly. Rigidly supported alignment cards guide a gripper that attaches to the control rod assembly as the control rod assembly is withdrawn into the tool with the alignment cards preventing any lateral or rotational movement of the gripper.
G21C 19/115 - Dispositifs de relèvement ou d'enlèvement adaptés pour coopérer avec les éléments combustibles ou avec l'élément de commande à dispositifs de verrouillage et couplages à billes
An eddy current probe testing apparatus structured to operate concurrently in a driver pick-up mode and said impedance mode is provided. The eddy current probe has two coils. The eddy current probe testing apparatus also includes a signal producing device, an output device, and a switch assembly. The switch assembly is structured to switch how an input signal from the signal producing device is provided to the two coils.
A miniature sludge lance for a steam generator in a pressurized water nuclear reactor is provided. The sludge lance is structured to enter the steam generator via an inspection opening and has a body sufficiently thin to fit between adjacent tubes. The sludge lance rail has at least two types of nozzle assemblies that may be attached thereto. One nozzle assembly rotates and another nozzle assembly translates in a vertical direction. A drive assembly, a mounting assembly, an oscillation assembly, and flow straighteners are also provided.
An improved method of inspecting the tubes of a steam generator of a nuclear reactor involves modeling the steam generator and comparing signals of a tube from an eddy current sensor with aspects of the model to determine whether further analysis is required. The model can advantageously include exception data with regard to particular regions of interest (ROIs) of particular tubes that is based upon historic data collected from the steam generator.
A digital rod control system that employs separate power modules to energize the respective coils of a magnetic jack control rod drive rod drive system so that two, independently powered grippers can simultaneously support the control rod drive rod when it is not in motion to avoid dropped rods. The basic building block of the system is two or more selecting cabinets which receive multiplex power from at least one moving cabinet and are under the control of a single logic cabinet. Each of the cabinets include monitoring features to confirm the reliability of the system.
A pipe scanner for non-destructively scanning an extended length of the circumference of a pipe along an axial dimension. The pipe scanner includes a collar sized to fit around the outer circumference of the pipe. Wheels supported on the collar ride on the surface of the pipe while maintaining a space between the inner surface of the collar and the outer surface of the pipe. A track extends circumferentially around the collar for guiding a circumferential drive unit that rides on the track and carries a non-destructive sensor for monitoring the surface of the pipe as the circumferential drive unit moves around the track. An axial drive unit is connected to the collar, having a plurality of circumferentially spaced drive wheels in contact with the pipe for moving the collar along the extended length.
An improved scale conditioning composition and method is disclosed that results in improved dissolution and disruption of tube scale, hardened sludge and other deposits composed primarily of highly densified magnetite such as those found in heat exchange vessels, particularly steam generators. After treatment with the advanced scale conditioning composition, these magnetite rich deposits are more easily removed using known and commercially available high pressure hydro-mechanical cleaning techniques. The present invention further provides effective cleaning in a short period of time and at relatively low temperatures, while reducing the amount of waste produced and reducing the resulting corrosion of carbon and low alloy steel components within the steam generator during the cleaning process.
C02F 5/12 - Traitement de l'eau avec des produits chimiques complexants ou des agents solubilisants pour l'adoucissement, la prévention ou l'élimination de l'entartrage, p.ex. par addition d'agents séquestrants en utilisant des substances organiques contenant de l'azote
brevets
