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 - Dispositions pour la conversion des éléments chimiques par rayonnement électromagnétique, radiations corpusculaires ou bombardement par des particules, p.ex. production d'isotopes radioactifs à l'extérieur des réacteurs nucléaires ou des accélérateurs de particules par irradiation par des neutrons
G21G 1/00 - Dispositions pour la conversion des éléments chimiques par rayonnement électromagnétique, radiations corpusculaires ou bombardement par des particules, p.ex. production d'isotopes radioactifs
2.
DEVICES, SYSTEMS, AND METHODS FOR DELIVERING DELTA RADIATION USING PROMPT NEUTRON CAPTURE GAMMA RADIATION
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.
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 - Dispositions pour la conversion des éléments chimiques par rayonnement électromagnétique, radiations corpusculaires ou bombardement par des particules, p.ex. production d'isotopes radioactifs
B22F 10/28 - Fusion sur lit de poudre, p.ex. fusion sélective par laser [FSL] ou fusion par faisceau d’électrons [EBM]
B33Y 80/00 - Produits obtenus par fabrication additive
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
4.
Devices, Systems, and Methods for Detecting Radiation with Schottky Diodes for Enhanced In-Core Measurements n-Core Measurements
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.
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.
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 FORCES
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
G21C 7/04 - Commande de la réaction nucléaire par utilisation des propriétés autorégulatrices des matériaux du réacteur de poisons combustibles
G21C 19/19 - Parties de réacteurs spécifiquement adaptées pour faciliter la manipulation, p.ex. pour faciliter le chargement ou le déchargement des éléments combustibles
7.
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.
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
G21G 1/00 - Dispositions pour la conversion des éléments chimiques par rayonnement électromagnétique, radiations corpusculaires ou bombardement par des particules, p.ex. production d'isotopes radioactifs
9.
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.
An improved retention system for retaining fuel rods in a fuel assembly is disclosed. The retention system includes a plurality of first engagement surfaces on the bottom nozzle of a fuel assembly. There is at least one engagement surface for each fuel rod. A second engagement surface is formed on the bottom end plug of each fuel rod. The first and second engagement surfaces are configured for engagement with each other for axially and laterally retaining each fuel rod within the fuel assembly. Debris deflectors may also be provided to deflect debris from coolant channels surrounding the fuel rods.
G21C 3/33 - Moyens pour supporter ou suspendre des éléments dans le faisceau; Moyens faisant partie du faisceau pour l'insérer dans le cœur ou l'en extraire; Moyens de couplage de faisceaux adjacents
Nuclear fuel rods are disclosed. The nuclear fuel rods include a substrate and a chromium alloy coating layer applied to the substrate. The chromium alloy coating layer comprises chromium (Cr); a element or compound selected from the group consisting of yttrium (Y), lanthanum (La), thorium (Th), zirconium (Zr), titanium (Ti), hafnium (I-lf), molybdenum (Mo), tungsten (W), vanadium (V), rhenium (Re), ruthenium (Ru), cobalt (Co), aluminum (Al), carbides, borides, intermetallics, and combinations thereof; and interstitial elements up to 1500 ppm, wherein carbon (C), oxygen (O), and nitrogen (N) are each 500 ppm or less.
C23C 14/14 - Matériau métallique, bore ou silicium
C22C 28/00 - Alliages à base d'un métal non mentionné dans les groupes
C23C 16/06 - Revêtement chimique par décomposition de composés gazeux, ne laissant pas de produits de réaction du matériau de la surface dans le revêtement, c. à d. procédés de dépôt chimique en phase vapeur (CVD) caractérisé par le dépôt d'un matériau métallique
C23C 28/02 - Revêtements uniquement de matériaux métalliques
A method for transitioning a nuclear reactor during initial cycle startup to a power generating state is disclosed. The method includes setting the nuclear reactor to a zero power state, eliminating lower power physics tests (LPPTs) for a current cycle of the nuclear reactor based on a predetermined set of criteria, and setting the nuclear reactor to the power generating mode without performing the LPPTs, based on the reconciliation. The eliminating includes predicting, using a first design code, a first set of values for factors of the LPPTs, developing, using data from past cycles of the nuclear reactor, empirical formulas for the factors of the LPPTs, predicting, using the empirical formulas, a second set of values for the factors of the LPPTs, and reconciling the first values with the second values.
A coupler for connecting an irradiation target assembly to a transfer system is provided. The coupler comprises a housing and an inner assembly. The housing comprises a distal end, a proximal end and a side section defining a cavity therein. The side section comprises a plurality of side bores extending into the cavity. The inner assembly comprises an actuator body, a return member for exerting a default axial force on the actuator body, and a plurality of friction members configured to be transversely driven by the actuator body through the plurality of side bores. The actuator body is positioned within the cavity and comprises a first section, a second section and a middle section. A coupling system comprising a coupling insert for a transfer system and a coupler for an irradiation target assembly are also provided.
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
14.
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 - 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
G21C 3/16 - Eléments combustibles - Détails de structure - Détails de structure à l'intérieur de l'enveloppe
Provided herein is a nuclear fuel assembly for a pressurized water reactor. The nuclear fuel assembly comprises: a plurality of nuclear fuel rods configured to contain a fissile material, wherein the nuclear fuel assembly is configured such that a hydrogen to uranium ratio for the fuel assembly, when coolant and the fissile material are present under operating conditions, is at least 4.0. Also provided herein is a method for refueling a pressurized water nuclear reactor comprising a nuclear fuel assembly of the present disclosure.
G21C 3/04 - Eléments combustibles - Détails de structure
G21C 3/17 - Moyens de stockage ou de fixation de gaz dans des éléments combustibles
G21C 19/00 - Dispositions pour le traitement, pour la manipulation, ou pour faciliter la manipulation, du combustible ou d'autres matériaux utilisés à l'intérieur du réacteur, p.ex. à l'intérieur de l'enceinte sous pression
16.
METHOD TO REDUCE NUCLEAR RADIATION INDUCED SPECKLING IN VIDEO IMAGES
Disclosed is a video processor for removing interference due to nuclear radiation. The video processor includes a control circuit configured to receive video data from a camera placed in a nuclear radioactive environment, determine a first image from the video data, calculate a first brightness value at a first pixel in a first pixel location in the first image, determine a second image from the video data, calculate a second brightness value at a second pixel in a second pixel location in the second image, compare the first brightness value to the second brightness value, and update the second image by replacing the second pixel in the second image with the first pixel when the second brightness value is greater than the first brightness value. The first image corresponds to a time before the second image, and the first pixel location and the second pixel location are the same location.
G06T 5/50 - Amélioration ou restauration d'image en utilisant plusieurs images, p.ex. moyenne, soustraction
H04N 25/683 - Traitement du bruit, p.ex. détection, correction, réduction ou élimination du bruit appliqué aux défauts par l'estimation des défauts effectuée sur le signal de la scène, p. ex. détection en temps réel ou à la volée
17.
INTERNAL HYDROFORMING METHOD FOR MANUFACTURING HEAT PIPE WICKS
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 the second recess. The 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.
B29C 43/10 - Pressage isostatique, c. à d. en utilisant des organes presseurs non rigides coopérant avec des organes rigides ou des matrices
B29C 43/36 - Moules pour la fabrication d'objets de longueur définie, c. à d. d'objets séparés
18.
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 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.
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.
B23P 15/26 - Fabrication d'objets déterminés par des opérations non couvertes par une seule autre sous-classe ou un groupe de la présente sous-classe d'échangeurs de chaleur
21.
USE OF SUB-CRITICAL NEUTRON MULTIPLICATION DRIVEN BY ELECTRONIC NEUTRON GENERATORS TO PRODUCE RADIOISOTOPES
A target irradiation apparatus for producing radioisotope sources is provided. The target irradiation apparatus comprises a containment vessel, a plurality of electronic neutron generator inserts and a removable neutron enhancement cartridge. The containment vessel comprises an inner surface, an outer surface, a first end, a second end, a body section, and a support member. Each of the plurality of electronic neutron generator insert devices is inserted into one of a plurality of openings of the body section while the removable neutron enhancement cartridge is adapted to be positioned inside of the containment vessel. A radioisotope production system comprising a target irradiation apparatus and a method for producing radioisotope sources are also provided.
G21G 1/06 - Dispositions pour la conversion des éléments chimiques par rayonnement électromagnétique, radiations corpusculaires ou bombardement par des particules, p.ex. production d'isotopes radioactifs à l'extérieur des réacteurs nucléaires ou des accélérateurs de particules par irradiation par des neutrons
In various aspects, a nuclear fuel rod cladding is disclosed. The cladding can include a base tube and a mesh structure including gaps therein. The base tube can include an elongated tubular wall and can be configured to house nuclear fuel therein. The mesh structure can be positioned along at least a portion of the elongated tubular wall and can be configured to provide structural support to the base tube. In one aspect, the gaps of the mesh structure are designed to permit neutrons emitted by the nuclear fuel to pass therethrough to escape the fuel rod cladding.
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 3/07 - Enveloppes; Chemises caractérisées par le matériau, p.ex. alliages
23.
COATINGS AND SURFACE MODIFICATIONS TO MITIGATE SiC CLADDING DURING OPERATION IN LIGHT WATER REACTORS
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.
G21C 21/02 - Fabrication des éléments combustibles ou surrégénérateurs à l'intérieur de gaines non-actives
G21C 1/08 - Réacteurs hétérogènes, c. à d. dans lesquels le combustible et le modérateur sont séparés le modérateur étant hautement pressurisé, p.ex. réacteur à eau bouillante, réacteur à surchauffe intégrale, réacteur à eau pressurisée
G21C 3/07 - Enveloppes; Chemises caractérisées par le matériau, p.ex. alliages
C23C 28/00 - Revêtement pour obtenir au moins deux couches superposées, soit par des procédés non prévus dans un seul des groupes principaux , soit par des combinaisons de procédés prévus dans les sous-classes et
C23C 14/06 - Revêtement par évaporation sous vide, pulvérisation cathodique ou implantation d'ions du matériau composant le revêtement caractérisé par le matériau de revêtement
Channel boxes for a boiling water reactor and methods of manufacture thereof are provided. The channel box comprises a substrate and a first layer. The substrate comprises a tubular shape. The substrate comprises silicon carbide fibers. The first layer is deposited on a first surface of the substrate and the first layer comprises a corrosion resistant metallic composition.
C22C 47/06 - Prétraitement des fibres ou des filaments par façonnage des fibres ou des filaments en une structure préformée, p.ex. en utilisant un liant temporaire afin de former un élément analogue à un mat
C22C 47/04 - Prétraitement des fibres ou des filaments par revêtement, p.ex. avec un recouvrement protecteur ou activé
C22C 47/10 - Imprégnation en présence d'une atmosphère réactive; Imprégnation réactive
G21C 1/08 - Réacteurs hétérogènes, c. à d. dans lesquels le combustible et le modérateur sont séparés le modérateur étant hautement pressurisé, p.ex. réacteur à eau bouillante, réacteur à surchauffe intégrale, réacteur à eau pressurisée
25.
UNIVERSAL REACTOR VESSEL HEAD INSPECTION PLATFORM ASSEMBLY
A mobile robotic assembly for guiding an end effector in inspecting reactor vessel heads is disclosed. The mobile robotic assembly includes a mobile platform; a support assembly extending vertically from the mobile platform, wherein the support assembly comprises an adjustable height; and a robotic arm attached to and extending laterally from the support assembly.
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
B25J 5/00 - Manipulateurs montés sur roues ou sur support mobile
Device and method for rapidly measuring the activity of nuclear isotopes contained within a cylindrical enclosure using the current output from a lead self-powered detector element
A radioactivity measurement device for measuring an activity level of a radioisotope source is provided. The radioactivity measurement device comprises a housing and a self-powered detector. The housing comprises an outer shell and an inner shell, wherein the inner shell is adapted to house an insertable radioisotope source, and wherein the outer shell and the inner shell are configured to form a hollow annular region. The self-powered detector, positioned within the hollow annular region of the housing, comprises at least one tubular emitter configured to provide a source of electron emission proportional to a radioisotope activity level of the insertable radioisotope source and at least one tubular collector configured to sink the electron emission. A radioactivity level measurement system comprising at least one radioactivity measurement device, a shipping cask incorporating the radioactivity level measurement system and a method for shipping the shipping cask are also provided.
The present disclosure is generally related to methods, systems and devices for direct production of a radioisotope-based cancer treatment pharmaceutical directly from a corresponding non-radioactive drug molecule precursor by irradiating the non-radioactive drug molecule precursor using neutrons produced by an electronic neutron generator array or other neutron generator sources.
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
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 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 53/06 - Fabrication d'autres objets particuliers d'échangeurs de chaleur, p.ex. radiateurs, condenseurs à partir de tubes métalliques
B23P 15/26 - Fabrication d'objets déterminés par des opérations non couvertes par une seule autre sous-classe ou un groupe de la présente sous-classe d'échangeurs de chaleur
30.
THREE DIMENSIONAL PRINTED PRECISION MAGNETS FOR FUEL ASSEMBLY
An improved retention and alignment system for nuclear fuel rods includes an upper nozzle plate and a lower nozzle plate, nuclear fuel rods, each having an upper end and a lower end and extending axially between the upper and lower nozzle plates, a first precision magnet incorporated onto the lower end of the fuel rod, and a plurality of second precision magnets incorporated onto the lower nozzle plate in positions confronting the first precision magnets on the fuel rods. Each first precision magnet has at least one of a magnetic north or south polarity and the second precision magnet has at least one of a magnetic south or north polarity opposite the polarity of the confronting first precision magnet to effect magnetic attraction between the confronting first and second precision magnets. Grids between the upper and lower nozzle plates form cells through which the fuel rods pass. Precision magnets of the same polarity may be positioned laterally along the fuel rods and grid walls in positions confronting each other to repel the fuel rods from the grid walls to maintain fuel rod alignment and prevent contact between the fuel rods and the grids.
G21C 3/33 - Moyens pour supporter ou suspendre des éléments dans le faisceau; Moyens faisant partie du faisceau pour l'insérer dans le cœur ou l'en extraire; Moyens de couplage de faisceaux adjacents
Nuclear fuel cladding for fast reactors, assemblies thereof, and methods of manufacture thereof are provided. The nuclear fuel cladding comprises a substrate, a first layer, and a second layer. The substrate a tubular shape. The first layer is deposited over an external surface of the substrate. The first layer comprises a corrosion resistant composition. The second layer is disposed over the first layer. The second layer comprises silicon carbide fibers infiltrated with silicon carbide. The second layer is configured to inhibit outward creep of the substrate.
Plated metallic substrates and methods of manufacture are provided. The method comprises depositing a first layer onto at least a portion of the metallic substrate to create a coated substrate utilizing physical vapor deposition. The method comprises electroplating a second layer comprising chromium, a chromium alloy, or a combination thereof onto at least a portion of the first layer to create a plated substrate.
A method of sampling a multi-layered material and a micro-sampling tool are described. The sampling method includes penetrating a top surface of a material in a component of interest with a micro-cutting tool to a predetermined depth sufficient to include each layer of the multi-layered material and a portion of the base, without cutting through the full depth of the base, undercutting from the depth of penetration through the base to define a micro-sample of the multi-layered material, and removing the micro-sample with each layer of the multi-layered material intact. The micro-sampler includes a cutting tool calibrated to cut to a depth no greater than 2 mm, and in some aspects, no greater than 200 microns into a multi-layered material, the material having a top surface and a metallic or ceramic base and a container for removing and storing a micro-sample cut from the material with each layer of the multi-layered material and a portion of the base intact.
G01N 1/06 - Dispositifs pour prélever des échantillons à l'état solide, p.ex. par coupe à l'outil procurant une tranche mince, p.ex. "microtome"
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
G01N 1/08 - Dispositifs pour prélever des échantillons à l'état solide, p.ex. par coupe à l'outil impliquant un outil d'extraction, p.ex. mèche cylindrique creuse ou trépan
G01N 1/10 - Dispositifs pour prélever des échantillons à l'état liquide ou fluide
34.
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 Schottky 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 Schottky 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 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.
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 13/024 - Structures supportant les cuves de pression ou les enceintes de confinement
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, a shaft travel pin, and a flange. The shaft is configured to engage the spring to compress and decompress the spring as the shaft travels in and out of the housing. The shaft travel pin controls the travel of the shaft. The flange is configured to mount the nuclear reactor core mechanical support bracket to a canister of a nuclear reactor. The shaft includes an inset configured to interface with a nuclear reactor core component.
A non-invasive eddy current flow meter embedded into a coolant channel for measuring the coolant flow velocity of liquid metal coolant in a nuclear reactor. The eddy current flow meter measures the coolant flow velocity in pool-type nuclear reactors and narrow coolant channels without creating bottlenecks that impede the coolant flow within the nuclear reactors.
G21C 17/032 - Mesure ou surveillance du débit de réfrigérant
H05K 9/00 - Blindage d'appareils ou de composants contre les champs électriques ou magnétiques
G01F 1/58 - Mesure du débit volumétrique ou du débit massique d'un fluide ou d'un matériau solide fluent, dans laquelle le fluide passe à travers un compteur par un écoulement continu en utilisant des effets électriques ou magnétiques par débitmètres électromagnétiques
38.
DEVICE FOR MEASURING THE ACTIVITY OF NUCLEAR ISOTOPES USING A SELF-POWER DETECTOR
A measuring device for measuring the activity of a specimen of a radioactive isotope is disclosed. The specimen of the radioactive isotope is contained within a capsule. The measuring device comprises an inner enclosure, a gamma-radiation sensitive self-power detector (SPD) positioned around the inner enclosure, and an outer enclosure positioned around the SPD and the inner enclosure. The inner enclosure comprises an internal cavity configured to receive the capsule containing the specimen. The inner enclosure defines a longitudinal axis. The outer enclosure secures the SPD to the inner enclosure such that the SPD does not move during operation and storage of the measuring device.
An ultrasonic phased array transducer assembly having a single housing in which a plurality of phased array transducer subassemblies are mounted at a skewed angle relative to a leading face of the housing and to each other, with each transducer mounted on composite wedge(s) at different orientations within the housing.
G01N 29/22 - 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
G01N 29/26 - Dispositions pour l'orientation ou le balayage
G21C 17/017 - Inspection ou maintenance de tuyaux ou de tubes dans des installations nucléaires
G21C 15/25 - Cyclage du fluide réfrigérant pour des liquides utilisant des pompes à jet
An insertable flux thimble interface for use in a bottom nozzle of a fuel assembly in a nuclear reactor (i.e., a bottom nozzle insert) is disclosed herein. In various aspects, the bottom nozzle insert has properties that are different from traditional bottom nozzle flux thimble interfaces. The properties of the bottom nozzle insert may mitigate wear phenomena observed on the flux thimble. For example, the bottom nozzle insert may be constructed from material that is different from the material of the bottom nozzle. In some aspects, the bottom nozzle insert is constructed from material that has a hardness that is less than the hardness the bottom nozzle material. In other aspects, the bottom nozzle insert is constructed from a material that has a hardness that is less than the hardness of the flux thimble material.
G21C 3/33 - Moyens pour supporter ou suspendre des éléments dans le faisceau; Moyens faisant partie du faisceau pour l'insérer dans le cœur ou l'en extraire; Moyens de couplage de faisceaux adjacents
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
A nuclear component handling arrangement is disclosed including a storage overpack including an inner envelope, an inner canister including an outer envelope, and a vent and duct system. The inner canister is positionable within the storage overpack. The vent and duct system includes an inlet vent, an outlet vent, and a passageway defined between the inner envelope of the storage overpack and the outer envelope of the inner canister. The passageway extends between the inlet vent and the outlet vent. The inlet vent includes an inlet entrance, an inlet exit, and a curved transition surface extending between the inlet entrance and the inlet exit.
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
G21F 5/008 - Récipients pour éléments combustibles
42.
METHOD OF REPLACING A FUNCTIONALITY OF A THERMAL SHIELD FLEXURE, A THERMAL SHIELD FLEXURE MEMBER, AND A SYSTEM INCLUDING THE SAME
A thermal shield flexure member. The thermal shield flexure member includes a first face portion, a second face portion and a third portion. The first face portion defines openings configured to align with receptacles of a thermal shield. The second face portion defines openings configured to align with openings of a core barrel and openings of an arm portion of a modified thermal shield flexure connected to the core barrel. The third portion is connected to the first face portion and the second face portion, and comprises a radiused portion. The thermal shield flexure member is configured to provide flexibility in an axial direction to accommodate differential axial expansions of the core barrel and the thermal shield, and rigidity in a radial direction to inhibit undesirable shell mode vibrations of the core barrel and/or the thermal shield.
G21C 11/08 - Ecrans thermiques; Revêtements thermiques, c. à d. pour dissiper la chaleur provenant de radiations gamma qui sans cela chaufferaient un écran biologique externe
G21C 21/00 - Appareillage ou procédés spécialement adaptés pour la fabrication des réacteurs ou de pièces de ceux-ci
Annular nuclear fuel rods are disclosed. The annular nuclear fuel rods include an outer cladding tube made of ceramic composite or cermet composite, an inner cladding tube made of ceramic composite or cermet composite, a nuclear fuel region located between the outer cladding tube and inner cladding tube, and an open channel for liquid coolant to flow.
An improved retention and alignment system for nuclear fuel rods includes an upper nozzle plate and a lower nozzle plate, nuclear fuel rods, each having an upper end and a lower end and extending axially between the upper and lower nozzle plates, a first precision magnet incorporated onto the lower end of the fuel rod, and a plurality of second precision magnets incorporated onto the lower nozzle plate in positions confronting the first precision magnets on the fuel rods. Each first precision magnet has at least one of a magnetic north or south polarity and the second precision magnet has at least one of a magnetic south or north polarity opposite the polarity of the confronting first precision magnet to effect magnetic attraction between the confronting first and second precision magnets. Grids between the upper and lower nozzle plates form cells through which the fuel rods pass. Precision magnets of the same polarity may be positioned laterally along the fuel rods and grid walls in positions confronting each other to repel the fuel rods from the grid walls to maintain fuel rod alignment and prevent contact between the fuel rods and the grids.
G21C 3/33 - Moyens pour supporter ou suspendre des éléments dans le faisceau; Moyens faisant partie du faisceau pour l'insérer dans le cœur ou l'en extraire; Moyens de couplage de faisceaux adjacents
A reactor core block is disclosed including a fuel channel, a heat pipe, a primary moderator matrix configured to encompass the fuel channel and the heat pipe, and a secondary moderator channel configured to at least partially surround the fuel channel, the heat pipe, and the primary moderator matrix. The secondary moderator channel is comprised of metal hydride.
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
G21D 5/02 - Réacteur et moteur structurellement combinés, p.ex. portatifs
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
46.
SILICON CARBIDE REINFORCED ZIRCONIUM BASED CLADDING
A method for making an improved nuclear fuel cladding tube includes reinforcing a Zr alloy tube by first winding or braiding ceramic yarn directly around the tube to form a ceramic covering, then physically bonding the ceramic covering to the tube by applying a first coating selected from the group consisting of Nb, Nb alloy, Nb oxide, Cr, Cr oxide, Cr alloy, or combinations thereof, by one of a thermal deposition process or a physical deposition process to provide structural support member for the Zr tube, and optionally applying a second coating and optionally applying a third coating by one of a thermal deposition process or a physical deposition process. If the tube softens at 800° C.-1000° C., the structural support tube will reinforce the Zr alloy tube against ballooning and bursting, thereby preventing the release of fission products to the reactor coolant.
A replacement thermal sleeve with a flange for a reactor vessel closure head penetration adapter housing. By altering a diameter of the flange, a replacement thermal sleeve can be installed through the narrow diameter of the penetration adapter housing opening from under the reactor vessel head. The flange can be compressible or expandable or the tubular wall of the thermal sleeve can be inserted in longitudinal sections, one at a time, into an opening in the underside of the penetration head adapter and reformed within the opening when fully inserted.
G21C 13/036 - Raccords entre le tube et la paroi d'une enceinte, p.ex. tenant compte des contraintes thermiques le tube traversant la paroi, c. à d. s'étendant de chaque côté
G21C 13/067 - Bouchons scellés pour des tubulures, p.ex. puits de chargement; Dispositifs de verrouillage pour bouchons
G21C 13/032 - Raccords entre le tube et la paroi d'une enceinte, p.ex. tenant compte des contraintes thermiques
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
G21C 15/00 - Dispositions pour le refroidissement à l'intérieur de l'enceinte sous pression contenant le cœur; Emploi de réfrigérants spécifiques
G21C 19/00 - Dispositions pour le traitement, pour la manipulation, ou pour faciliter la manipulation, du combustible ou d'autres matériaux utilisés à l'intérieur du réacteur, p.ex. à l'intérieur de l'enceinte sous pression
G21C 7/12 - Moyens pour amener les éléments de commande dans la position désirée
G21C 15/12 - 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 de l'enceinte d'enveloppe
48.
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
49.
A NUCLEAR FUEL ASSEMBLY AND A METHOD OF MANUFACTURE THEREOF
A nuclear fuel assembly and a method of manufacture thereof are provided. The method comprises depositing a thermally conductive layer onto at least a portion of at least two nuclear fuel layers to create at least two at least partially coated layers. The method comprises stacking the at least two coated layers and bonding the at least two coated layers to form a nuclear fuel assembly.
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 3/18 - Entretoises intérieures ou autre matériau non actif à l'intérieur de l'enveloppe, p.ex. pour compenser l'expansion des barres combustibles ou pour compenser une réactivité excessive
G21C 3/36 - Assemblages d'éléments combustibles en forme de plaques ou de tubes coaxiaux
G21C 21/02 - Fabrication des éléments combustibles ou surrégénérateurs à l'intérieur de gaines non-actives
50.
METHOD AND APPARATUS EMPLOYING VANADIUM NEUTRON DETECTORS
Disclosed herein is a method pertaining to a power distribution of a reactor core of a nuclear installation, the method being executed on a general purpose computer. The method comprises: measuring current values from a plurality of vanadium neutron detector assemblies which are disposed in the reactor core of the nuclear installation; determining a measured relative core power distribution based upon the measured current values; producing a measured core power distribution based upon the measured relative core power distribution; and verifying that the reactor is operating within the licensed core operating limits based at least in part upon the measured core power distribution. Also disclosed herein is a vanadium neutron detector assembly.
A process for treating highly localized carcinoma cells that provides precise positioning of a therapeutic source of highly ionizing but weakly penetrating radiation, which can be shaped so that it irradiates essentially only the volume of the tumor. The intensity and duration of the radiation produced by the source can be activated and deactivated by controlling the neutron flux generated by an array of electrically controlled neutron generators positioned outside the body being treated. The energy of the neutrons that interact with the source element can be adjusted to optimize the reaction rate of the ionized radiation production by utilizing neutron moderating material between the neutron generator array and the body. The source device may be left in place and reactivated as needed to ensure the tumor is eradicated without exposing the patient to any additional radiation between treatments. The source device may be removed once treatment is completed.
An apparatus for removing irradiated capsules containing produced Co-60 from a plurality of burnable absorber rodlets. The apparatus comprises a solenoid that induces an electromagnetic flux into a Co-60 capsule and magnetically 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 holding 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
G21C 7/04 - Commande de la réaction nucléaire par utilisation des propriétés autorégulatrices des matériaux du réacteur de poisons combustibles
G21C 19/19 - Parties de réacteurs spécifiquement adaptées pour faciliter la manipulation, p.ex. pour faciliter le chargement ou le déchargement des éléments combustibles
G21C 3/326 - Faisceaux d'éléments combustibles en forme d'aiguilles, de barres ou de tubes parallèles comprenant, en plus des éléments combustibles, d'autres éléments en forme d'aiguille, de barre ou de tube, p.ex. barres de commande, barres de support de grilles, barres fertiles, barres à poison ou barres factices
G21C 19/02 - Dispositions pour le traitement, pour la manipulation, ou pour faciliter la manipulation, du combustible ou d'autres matériaux utilisés à l'intérieur du réacteur, p.ex. à l'intérieur de l'enceinte sous pression - Détails des dispositions pour la manipulation
G21C 23/00 - Dispositions dans les réacteurs pour faciliter les expériences ou l'irradiation
53.
METHODS AND DEVICES TO IMPROVE PERFORMANCES OF RCCA AND CEA TO MITIGATE CLAD STRAIN IN THE HIGH FLUENCE REGION
The present disclosure is generally related to methods, devices and systems for improving the performances of a Rod Cluster Control Assembly (RCCA) and/or a Control Element Assembly (CEA) to mitigate clad strain, especially in the high fluence region, during normal operation conditions and accident conditions. One method may include incorporating a device such as a powder collection and blockage device between the ceramic upper and ceramic lower absorber materials of the RCCA and/or CEA. Another method may include increasing the plenum volume by incorporating an axial hole into the top end plug extension. Another method may include increasing the plenum volume by incorporating an axial hole into the bottom end plug and optionally incorporating radial grooves in the bottom of the lower absorber material to provide a flow channel for gas expansion or generation to ensure that the lower absorber does not block the opening in the bottom end plug.
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.
Disclosed herein is a cold spray system. The cold spray system comprises a nozzle unit comprising a coating nozzle member, configured to apply at least a portion of a metallic coating to a substrate. The cold spray system is configured to pre-heat the substrate before application of the at least a portion of the metallic coating to the substrate. Also disclosed herein is a method for applying a coating via a cold spray technique.
B05B 13/04 - Moyens pour supporter l'ouvrage; Disposition ou assemblage des têtes de pulvérisation; Adaptation ou disposition des moyens pour entraîner des pièces les têtes de pulvérisation étant déplacées au cours de l'opération
56.
PHYSICAL VAPOR DEPOSITION OF CERAMIC COATINGS ON ZIRCONIUM ALLOY NUCLEAR FUEL RODS
A nuclear fuel cladding tube is described herein that includes a zirconium alloy tube having an outer wear and oxidation resistant ceramic coating selected from the group consisting of CrN, Cr2N, CrWN, CrZrN, and combinations thereof. The cladding may have an intermediate layer formed between the tube and the outer ceramic coating. The intermediate layer may be selected from the group consisting of Ta, W, Mo, Nb, and combinations thereof. Both the intermediate layer and the outer ceramic coating may be deposited by physical vapor deposition.
G21C 3/07 - Enveloppes; Chemises caractérisées par le matériau, p.ex. alliages
C23C 14/06 - Revêtement par évaporation sous vide, pulvérisation cathodique ou implantation d'ions du matériau composant le revêtement caractérisé par le matériau de revêtement
An assembly configured to seal an end plug on a plugged end of a fuel tube is disclosed. The assembly includes a seal weld chamber assembly and a helium flow stop assembly (HFSA) removably coupled to the seal weld chamber assembly. The seal weld chamber assembly includes a welding chamber and a plunger fluidically coupled to the welding chamber. A helium source is configured to supply helium to the welding chamber. The end plug of the fuel tube is positionable within the welding chamber via the plunger. The HFSA is configured to prevent helium from escaping the welding chamber through the plunger.
B23K 9/16 - Soudage ou découpage à l'arc utilisant des gaz de protection
G21C 21/02 - Fabrication des éléments combustibles ou surrégénérateurs à l'intérieur de gaines non-actives
B23K 31/02 - Procédés relevant de la présente sous-classe, spécialement adaptés à des objets ou des buts particuliers, mais non couverts par un seul des groupes principaux relatifs au brasage ou au soudage
A variable diameter fuel rod of a nuclear reactor assembly is disclosed. The variable diameter fuel rod includes an elongated cladding tube configured to house a plurality of fuel pellets including a fissile material arranged in a fuel stack orientation. The elongated cladding tube includes first and second axial reflector regions and a middle axial region therebetween. The middle axial region comprises an outer diameter defined as d1. The first and second axial reflector regions include an outer cladding diameter defined as d2 and d3, respectively. The variable diameter fuel rod further includes a transitional region between the diameter d1 of the middle axial region and the diameter d2 of the axial reflector region. The diameter d2 of the axial reflector region is greater than the diameter d1 of the middle axial region.
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.
G01N 29/265 - Dispositions pour l'orientation ou le balayage en déplaçant le capteur par rapport à un matériau fixe
G01N 29/22 - 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
G01N 29/26 - Dispositions pour l'orientation ou le balayage
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
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.
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
G21C 13/00 - Enceintes sous pression; Enceintes d'enveloppe; Enveloppes en général
61.
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.
G01N 3/08 - Recherche des propriétés mécaniques des matériaux solides par application d'une contrainte mécanique par application d'efforts permanents de traction ou de compression
G01N 3/24 - Recherche des propriétés mécaniques des matériaux solides par application d'une contrainte mécanique en appliquant des efforts permanents de cisaillement
62.
Devices, systems, and methods for detecting radiation with Schottky diodes for enhanced in-core measurements
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.
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 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 as the first step or after removal to a separate unit for further processing.
A neutron detector is disclosed herein. The neutron detector can include a housing defining a cavity, wherein the housing is configured to permit an amount of neutrons emitted from a core of a nuclear reactor to enter the cavity. The neutron detector can also include an amount of a neutron sensitive material dispositioned within the cavity, wherein the neutron sensitive material is configured to generate and emit gamma rays upon interacting with the amount of neutrons. The neutron detector can further include an amount of electron emissive material configured to generate and emit a current of electrons upon interacting with the emitted gamma rays, wherein the current of electrons is indicative of the amount of neutrons emitted from the core of the nuclear reactor.
G21G 1/08 - Dispositions pour la conversion des éléments chimiques par rayonnement électromagnétique, radiations corpusculaires ou bombardement par des particules, p.ex. production d'isotopes radioactifs à l'extérieur des réacteurs nucléaires ou des accélérateurs de particules par irradiation par des neutrons accompagnée de fission nucléaire
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
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.
G21D 3/00 - Commande des installations à énergie nucléaire
G21C 9/02 - Moyens pour effectuer une réduction très rapide du facteur de réactivité dans des conditions défectueuses, p.ex. fusible pour réacteur
G21C 17/08 - Combinaison structurelle du cœur du réacteur ou de la structure du modérateur avec des moyens de vision, p.ex. avec des caméras de télévision, périscopes, fenêtres
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
G21D 3/06 - Dispositions de sécurité réagissant à des défaillances à l'intérieur de l'installation
67.
Nuclear reactor system, transmitter device therefor, and associated method of measuring a number of environmental conditions
Disclosed is a method of measuring a number of environmental conditions with a transmitter device, said transmitter device comprising a neutron detector structured to generate electrical current from neutron flux, an oscillator circuit comprising an electrostatic switch electrically connected to said neutron detector, and an antenna electrically connected with said electrostatic switch, wherein said electrostatic switch is moveable based on said neutron detector, wherein said oscillator circuit is structured to pulse said antenna based on said neutron detector, wherein a period between pulses is related to the neutron flux, the method comprising the steps of: generating the electrical current with said neutron detector, storing energy in said oscillator circuit until a trigger voltage of said electrostatic switch is reached, and emitting a signal with said antenna corresponding to a number of characteristic values of said oscillator circuit.
Apparatuses, systems, and methods of filtering debris from the bottom nozzle of a nuclear reactor while minimizing loss coefficients are disclosed herein, including a debris filter bottom nozzle with a plate-like body, a plurality of flow passages, and a filter positioned within at least one flow passage, wherein the at least one flow passage has a dimension based at least in part on a predetermined loss coefficient of the at least one flow passage and a predetermined filtration capability of the filter.
G21C 3/32 - Faisceaux d'éléments combustibles en forme d'aiguilles, de barres ou de tubes parallèles
G21C 3/33 - Moyens pour supporter ou suspendre des éléments dans le faisceau; Moyens faisant partie du faisceau pour l'insérer dans le cœur ou l'en extraire; Moyens de couplage de faisceaux adjacents
G21C 19/30 - Dispositions pour introduire un matériau fluent à l'intérieur du cœur du réacteur; Dispositions pour enlever un matériau fluent du cœur du réacteur avec purification continue du matériau fluent en circulation, p.ex. par extraction des produits de fission
69.
USE OF ENDOTHERMIC MATERIALS IN ICE CONDENSER CONTAINMENTS
An energy absorber apparatus is described that includes a plurality of assemblies, each of which contains a plurality of preferably cylindrical tubes, with each tube containing an endothermic material, such as ammonium carbamate. The assemblies are supported in a plurality of elongate baskets positioned in vaults that may surround the periphery of a nuclear reactor containment structure. The energy absorber apparatus absorbs excess energy released in the event of a design basis accident.
A method of processing a nuclear material for use as a nuclear fuel in a nuclear reactor is disclosed herein. The nuclear material includes a complex isotope vector including a plurality of isotopes including a targeted isotope and a non-targeted isotope. The method can include: determining a wavelength of electromagnetic radiation based, at least in part, on the targeted isotope; emitting a beam of electromagnetic radiation including the determined wavelength towards the nuclear material; separating, via the emitted beam of electromagnetic radiation, the nuclear material into a first stream and a second stream; enriching, via the emitted beam of electromagnetic radiation, a concentration of the targeted isotope to a predetermined concentration; and dispositioning, via a sensitivity to the determined wavelength, the enriched concentration of the targeted isotope to the first stream of the nuclear material; and dispositioning, via a lack of sensitivity to the determined wavelength, the non-targeted isotope to the second stream of the nuclear material.
G01N 23/22 - Recherche ou analyse des matériaux par l'utilisation de rayonnement [ondes ou particules], p.ex. rayons X ou neutrons, non couvertes par les groupes , ou en mesurant l'émission secondaire de matériaux
G01N 23/221 - Recherche ou analyse des matériaux par l'utilisation de rayonnement [ondes ou particules], p.ex. rayons X ou neutrons, non couvertes par les groupes , ou en mesurant l'émission secondaire de matériaux utilisant l'analyse par activation
71.
Nuclear reactor core support system providing radial and axial support
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, a shaft travel pin, and a flange. The shaft is configured to engage the spring to compress and decompress the spring as the shaft travels in and out of the housing. The shaft travel pin controls the travel of the shaft. The flange is configured to mount the nuclear reactor core mechanical support bracket to a canister of a nuclear reactor. The shaft includes an inset configured to interface with a nuclear reactor core component.
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
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
G21D 3/00 - Commande des installations à énergie nucléaire
G21C 7/12 - Moyens pour amener les éléments de commande dans la position désirée
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.
A method of determining reactivity of a nuclear reactor by a reactivity computer may include receiving a neutron detector response for a discrete period of time, performing a statistical check on the neutron detector response, determining if the neutron detector response is acceptable based on the statistical check, and calculating reactivity using a prior delayed neutron concentration if the neutron detector response is not acceptable and using a newly calculated delayed neutron concentration if the neutron detector response is acceptable.
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.
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
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
76.
PASSIVE VENTING ARRANGEMENT OF STOICHIOMETRIC HYDROGEN PLUS OXYGEN GASES GENERATED IN A SHIELDED CONTAINER
A passive venting arrangement for use in venting of gases produced by radioactive materials includes a source gas region for receiving the gases produced by the radioactive materials; a filter ullage region disposed above the source gas region and segregated therefrom except for a plurality of bore holes which each extend between, and fluidly couple, the source gas region and the filter ullage region; and a plurality of filters disposed in contact with the filter ullage region, wherein each filter is structured to provide for the exchange of gases from the filter ullage region through the filter to an ambient environment.
A fuel assembly for use in a nuclear reactor comprising a fuel bundle, a plenum header connection positioned on the fuel bundle, a mast extending from the fuel bundle, and a common fission gas plenum extending from the mast is disclosed. The reactor includes a vessel and coolant situated within the vessel. The fuel bundle comprises a plurality of fuel elements including nuclear fuel material positioned therein. The plenum header connection comprises a plurality of passageways defined therein that are in fluid communication with the nuclear fuel material. The elongate mast comprises an internal passage connecting the common fission gas plenum to the plurality of passageways of the plenum header connection such that the common fission gas plenum is configured to receive an amount of fission gas generated by the nuclear fuel material during operation. The common fission gas plenum is positioned in an otherwise unused portion of the vessel.
G21C 3/32 - Faisceaux d'éléments combustibles en forme d'aiguilles, de barres ou de tubes parallèles
G21C 1/02 - Réacteurs de fission rapides, c. à d. réacteurs n'utilisant pas de modérateur
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
78.
Injecting reactant into a spent fuel pool to react with radioactive effluent released into the pool from a nuclear reactor containment
A method of releasing an atmospheric effluent within a nuclear containment to an atmosphere surrounding the nuclear containment is disclosed. The nuclear containment is adjacent to an associated spent fuel pool that is located outside the nuclear containment, the method comprises sensing a pressure buildup within the nuclear containment, routing a portion of the atmospheric effluent through the spent fuel pool when a pressure buildup within the nuclear containment reaches a preselected value, and releasing a chemical into the spent fuel pool, based on the routing, to facilitate a reaction with the atmospheric effluent to substantially neuter any deleterious environmental impact of the atmospheric effluent.
G21C 13/02 - Enceintes sous pression; Enceintes d'enveloppe; Enveloppes en général - Détails
G21C 19/00 - Dispositions pour le traitement, pour la manipulation, ou pour faciliter la manipulation, du combustible ou d'autres matériaux utilisés à l'intérieur du réacteur, p.ex. à l'intérieur de l'enceinte sous pression
G21C 13/10 - Moyens pour prévenir la contamination dans le cas d'une fuite
G21C 19/307 - Dispositions pour introduire un matériau fluent à l'intérieur du cœur du réacteur; Dispositions pour enlever un matériau fluent du cœur du réacteur avec purification continue du matériau fluent en circulation, p.ex. par extraction des produits de fission spécialement adaptés pour des liquides
G21C 19/303 - Dispositions pour introduire un matériau fluent à l'intérieur du cœur du réacteur; Dispositions pour enlever un matériau fluent du cœur du réacteur avec purification continue du matériau fluent en circulation, p.ex. par extraction des produits de fission spécialement adaptés pour des gaz
79.
DEBRIS FILTERING SKIRT ARRANGEMENT FOR NUCLEAR FUEL ASSEMBLY BOTTOM NOZZLE AND BOTTOM NOZZLE INCLUDING SAME
A debris filtering skirt configured for use with a flow plate of a bottom nozzle of a nuclear reactor is disclosed herein. The debris filtering skirt includes a base portion defining an opening between a bottom edge and a reactor vessel lower core plate, and the opening includes a dimension configured to position the bottom nozzle a predetermined distance away from the reactor vessel lower core plate. The debris filtering skirt also includes a plurality of holes, and at least one hole of the plurality of holes includes a dimension determined based, at least in part, on a predetermined size of debris capable of traversing through the inlet and the outlet. The dimension of the opening and the dimension of the at least one hole are determined based, at least in part, on a predetermined loss coefficient of the bottom nozzle.
G21C 3/12 - Moyens formant partie de l'élément pour le positionner dans le cœur du réacteur; Entretoises extérieures à cet effet
B01D 29/33 - Eléments filtrants autoportants agencés pour la filtration à courant dirigé vers l'intérieur
G21C 3/32 - Faisceaux d'éléments combustibles en forme d'aiguilles, de barres ou de tubes parallèles
G21C 3/33 - Moyens pour supporter ou suspendre des éléments dans le faisceau; Moyens faisant partie du faisceau pour l'insérer dans le cœur ou l'en extraire; Moyens de couplage de faisceaux adjacents
80.
Autonomous path planning and path execution for decontamination of nuclear power plant objects
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.
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
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.
A process is described that includes forming a metal alloy component having a pre-specified three dimensional geometry for use in a nuclear reactor by an additive manufacturing process followed by annealing the formed component at a first annealing temperature within the alpha temperature range of the phase diagram for the metal alloy. A second annealing step at a second annealing temperature lower than the first annealing temperature may be added. Alternatively, annealing may be at an annealing temperature in the alpha+beta temperature range of a phase diagram for the metal alloy, followed by a second anneal in the alpha temperature range of the phase diagram for the metal alloy.
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.
G05B 15/02 - Systèmes commandés par un calculateur électriques
H04L 69/329 - Protocoles de communication intra-couche entre entités paires ou définitions d'unité de données de protocole [PDU] dans la couche application [couche OSI 7]
H04L 67/125 - Protocoles spécialement adaptés aux environnements propriétaires ou de mise en réseau pour un usage spécial, p.ex. les réseaux médicaux, les réseaux de capteurs, les réseaux dans les véhicules ou les réseaux de mesure à distance en impliquant la commande des applications des terminaux par un réseau
84.
CONTROL ROD DRIVE MECHANISM DIAGNOSTIC TOOL USING VOLTAGE AND CURRENT RECORDINGS
Disclosed is a diagnostic apparatus structured to be electrically connected with a coil stack of a drive mechanism of a control device of a nuclear reactor. The coil stack has a plurality of coils. The diagnostic apparatus includes a power supply and a controller including a processor and a memory that stores a number of routines including a number of instructions. When executed on the processor the instructions cause the diagnostic apparatus to apply to a coil a voltage that varies as a function of time, detect a current in the coil as a function of time, identify in the current a first inflection point and a second inflection point, and determine, based upon an electronic evaluation that includes the first inflection point and the second inflection point, that the coil is one of functioning properly and in a state of at least partial failure.
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 at least one fuel rod. Each fuel rod comprises a beryllium-oxide sleeve and nuclear fuel positioned in the beryllium-oxide sleeve.
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.
Disclosed are a voltage drop measurement system and methods for measuring resistivity of a nuclear reactor cladding. The system includes a short cladding sample of a nuclear reactor cladding. Two electrically conductive plugs are attached to the short cladding. A power supply is electrically coupled to the each of the two electrically conductive plugs and is configured to apply an electrical current to the short cladding through the two electrically conductive plugs. Two needle like probes are electrically coupled to a surface of the short cladding between the two electrically conductive plugs. The needle like probes are spaced apart by a distance L. Resistivity and heat flux are determined in accordance with Equations (1)-(4).
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
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 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
G21D 3/00 - Commande des installations à énergie nucléaire
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 - Cyclage du fluide réfrigérant utilisant des tubes caloporteurs
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
F28D 21/00 - Appareils échangeurs de chaleur non couverts par l'un des groupes
A nuclear battery is provided. The nuclear battery comprises a radiation source layer, a first electrical insulator layer, a casing layer, a first electrode, and a second electrode. The radiation source layer comprises a composition configurable to emit beta radiation. The first electrical insulator layer is disposed over the radiation source layer. The casing layer is disposed over the first electrical insulator layer. The casing layer comprises a composition configured to inhibit traversal of beta radiation. The first electrode is in electrical communication with the radiation source layer. The second electrode is in electrical communication with the casing layer. A voltage potential is present between the first electrode and the second electrode when the radiation source layer emits beta radiation.
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 - Raccords entre le tube et la paroi d'une enceinte, p.ex. tenant compte des contraintes thermiques le tube traversant la paroi, c. à d. s'étendant de chaque côté
G21C 13/04 - Dispositions pour l'expansion et la contraction
92.
Devices, systems, and methods for measuring radioactive isotope production in bulk
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.
H05G 1/00 - Appareils à rayons X utilisant des tubes à rayons X; Circuits pour ces appareils
G01N 23/223 - Recherche ou analyse des matériaux par l'utilisation de rayonnement [ondes ou particules], p.ex. rayons X ou neutrons, non couvertes par les groupes , ou en mesurant l'émission secondaire de matériaux en irradiant l'échantillon avec des rayons X ou des rayons gamma et en mesurant la fluorescence X
G01N 23/095 - Absorption des rayons gamma par résonance, p.ex. en utilisant l’effet Mössbauer
93.
DEVICES, SYSTEMS, AND METHODS FOR ADJUSTING THE OUTPUT OF A REACTOR CORE
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.
A nuclear reactor is disclosed including a reactor core and a reflector assembly surrounding the reactor core. The reflector assembly includes a stationary reflector component including a graphite support structure comprising a plurality of channels defined therein and a plurality of beryllium-oxide pins positioned in the channels.
G21C 11/06 - Ecrans réflecteurs, c. à d. pour minimiser la perte de neutrons
G21C 3/18 - Entretoises intérieures ou autre matériau non actif à l'intérieur de l'enveloppe, p.ex. pour compenser l'expansion des barres combustibles ou pour compenser une réactivité excessive
G21C 7/28 - Commande de la réaction nucléaire par déplacement du réflecteur ou de parties de celui-ci
A control rod for a nuclear fuel assembly is described herein that includes a neutron absorbing material having a melting point greater than 1500° C. that does not form a eutectic with a melting point less than 1500° C., and may further include a cladding material having a melting point greater than 1500° C. The cladding material is selected from the group consisting of silicon carbide, zirconium, a zirconium alloy, tungsten, and molybdenum. The absorbing material is selected from the group consisting of Gd2O3, Ir, B4C, Re, and Hf. The metal cladding or the absorbing material may be coated with an anti-oxidation coating of Cr with or without a Nb intermediate layer.
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 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
F28D 9/00 - Appareils échangeurs de chaleur comportant des ensembles de canalisations fixes en forme de plaques ou de laminés pour les deux sources de potentiel calorifique, ces sources étant en contact chacune avec un côté de la paroi d'une canalisation
F28F 9/00 - Carters; Boîtes de distribution; Supports auxiliaires pour les éléments; Eléments auxiliaires dans les carters
F28F 9/26 - Dispositions pour raccorder des sections différentes des éléments d'échangeurs de chaleur, p.ex. de radiateur
G21C 15/14 - 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 des conduits comprenant des appareils auxiliaires, p.ex. pompes, caméras
F28F 9/16 - Dispositions pour obturer des éléments dans les boîtes de distribution ou plaques d'extrémité par joints permanents, p.ex. par dudgeonnage
97.
TWO AND THREE-DIMENSIONAL MODEL BASED CORRECTION OF ELBOW TAP FLOW MEASUREMENT
A system for determining coolant flow rate in a nuclear reactor primary cooling loop includes a processor and a memory. The memory stores physical measurements of the mechanical components comprising the primary cooling loop. The memory also stores instructions that cause the processor to: receive pressure data from a plurality of pressure sensors in the cooling loop; calculate a model of fluid flow through the primary cooling loop based on the mechanical component measurements; compare the data from the pressure sensors with estimated data from the fluid flow model; and calculate a statistical weighting of the pressure data from the pressure sensors based on the estimated pressure data from the fluid flow model. In another system, the flow rate is determined from a combination of the estimate from the modeled fluid flow with an estimate based on a calorimetric thermal exchange calculation.
G01F 1/50 - Moyens de correction ou de compensation
G01K 13/02 - Thermomètres spécialement adaptés à des fins spécifiques pour mesurer la température de fluides en mouvement ou de matériaux granulaires capables de s'écouler
G21C 17/022 - Dispositifs ou dispositions pour la surveillance du réfrigérant ou du modérateur pour la surveillance de réfrigérants ou de modérateurs liquides
G06F 30/20 - Optimisation, vérification ou simulation de l’objet conçu
A system that provides a direct indication of peak fuel rod centerline temperature and peak fuel rod clad temperature than conventionally inferred from the power distribution by directly and continuously measuring the fuel temperatures of the fuel pellets in one or more of the hottest fuel elements in the core. The peak fuel rod clad temperature is then obtained from the maximum measured peak fuel rod centerline temperature in combination with the maximum coolant core exit temperature and the minimum coolant flow rate.
G21C 17/022 - Dispositifs ou dispositions pour la surveillance du réfrigérant ou du modérateur pour la surveillance de réfrigérants ou de modérateurs liquides
G21C 17/032 - Mesure ou surveillance du débit de réfrigérant
99.
METHOD AND SYSTEM TO DETECT AND LOCATE THE IN-CORE POSITION OF FUEL BUNDLES WITH CLADDING PERFORATIONS IN CANDU-STYLE NUCLEAR REACTORS
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 - 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
100.
SELF-HEALING LIQUID PELLET-CLADDING GAP HEAT TRANSFER FILLER
An improvement in a nuclear fuel rod is disclosed. The improved fuel rod includes a cladding tube, a plurality of fuel pellets stacked within the cladding tube, and a liquid material filling the gap between the fuel pellets and the cladding tube. The liquid material is selected from those having a thermal conductivity higher than that of helium, a melting point lower than about 400° C., a boiling point higher than 1600° C., and which are capable of wetting both the fuel pellets and the cladding sufficient to form a protective layer over the pellets and to wick into openings that may form in the cladding.
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 3/07 - Enveloppes; Chemises caractérisées par le matériau, p.ex. alliages
G21C 3/18 - Entretoises intérieures ou autre matériau non actif à l'intérieur de l'enveloppe, p.ex. pour compenser l'expansion des barres combustibles ou pour compenser une réactivité excessive
brevets
