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.
MANUFACTURE OF HEAT PIPE WICKS UTILIZING IN-SITU ROLLING AND HYDROFORMING DEVICE
An in-situ wick rolling and forming assembly configured to roll and form a wick for a heat pipe from a wick mesh. The in-situ wick rolling and forming assembly includes a first forming shell, a slotted mandrel, and an expandable member. The first forming shell is configured to form the wick in-situ after the rolling of the wick mesh. The first forming shell includes a first recess and a first parting surface. A first central axis of the first recess is positioned below the first parting surface. The slotted mandrel is removably positionable in the first recess.
B21F 33/00 - Outils ou dispositifs spécialement conçus pour la manipulation ou le traitement des tissus métalliques ou produits similaires
B22F 3/00 - Fabrication de pièces ou d'objets à partir de poudres métalliques, caractérisée par le mode de compactage ou de frittage; Appareils spécialement adaptés à cet effet
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
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
5.
DEVICES, SYSTEMS, AND METHODS FOR THE ENHANCED OPERATION OF HYDRAULIC CONTROL UNITS OF A CONTROL ROD DRIVE MECHANISM TO REGULATE NUCLEAR FLUX IN A REACTOR CORE
A hydraulic control unit ("HCU") configured to control a control rod drive mechanism ("CRDM") configured to control the nuclear flux produced by a nuclear reactor is disclosed herein. The HCU can include a plurality of valves configured to attenuate a fluid pressure within the CRDM, wherein the attenuation of the fluid pressure is configured to cause a control rod of the CRDM to be inserted or withdrawn from a reactor vessel of the nuclear reactor, and a control circuit including a plurality of relay interfaces, wherein each relay of the plurality of relay interfaces is electrically coupled to a valve of the plurality of valves, a controller electrically coupled to the plurality of relay interfaces, and a communications circuit communicably coupled to a header controller, wherein the communications circuit is configured to transmit and receive signals between the controller and the header controller.
An in-core detector configured to measure a power distribution in a nuclear reactor is disclosed herein. The in-core detector includes a housing configured to be placed within a predetermined location of the nuclear reactor and a plurality of a gamma detectors. Each gamma detector of the plurality of gamma detectors includes a Schottky diode including an active semiconductor region and a Schottky contact, an Ohmic contact, a photoelectron source material configured to transfer electrons to the active region upon contact with gamma radiation, and a first and second lead. The plurality of gamma detectors are positioned within the housing such that each gamma detector of the plurality of gamma detectors is radially offset relative to an adjacent gamma detector of the plurality of gamma detectors, such that the first and second leads of each gamma detector are offset relative to the first and second leads of the adjacent gamma detector.
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
9.
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
11.
FIBER REINFORCED MULTI-LAYERED WEAR AND CORROSION COATINGS OF ZIRCONIUM ALLOY NUCLEAR FUEL CLADDING
A covering for reinforcing a base layer of a nuclear fuel cladding is provided. The covering comprises a first layer configured to cover a first portion of the outer surface of the base layer of the nuclear fuel cladding, a second layer surrounding the first layer and the base layer and a third layer surrounding the second layer. The first layer comprises a fiber based material, the second layer comprises an interfacing material and the third layer comprises Chromium. A reinforced cladding for nuclear fuel and a method for producing a reinforced nuclear fuel cladding are also provided.
A covering for reinforcing a base layer (10) of a nuclear fuel cladding (100) is provided. The covering comprises a first layer (110) configured to cover a first portion of the outer surface of the base layer of the nuclear fuel cladding, a second layer (120) surrounding the first layer and the base layer and a third layer (130) surrounding the second layer. The first layer (110) comprises a fiber based material, the second layer (120) comprises an interfacing material and the third layer (130) comprises Chromium. A reinforced cladding (100) for nuclear fuel and a method for producing a reinforced nuclear fuel cladding (100) 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 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.
The present disclosure provides a nuclear power source, a nuclear battery assembly, and a method of manufacture thereof. The nuclear power source comprising a radiation source layer, a first electrical insulator layer disposed over the radiation source layer, a first casing layer disposed over the first electrical insulator layer, a first electrode in contact with the radiation source layer, and a second electrode in contact with the first casing layer. The radiation source layer comprises a composition configurable to emit beta radiation. A voltage potential is present between the first electrode and the second electrode when the radiation source layer emits beta radiation. The first electrical insulator layer has a thickness that reduces an average energy of the beta-radiation from the radiation source layer that contacts the first casing layer such that Bremsstrahlung radiation emitted when the beta-radiation reaches the first casing layer is reduced.
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
20.
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
22.
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
23.
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.
H04N 23/71 - Circuits d'évaluation de la variation de luminosité
H04N 23/81 - Chaînes de traitement de la caméra; Leurs composants pour supprimer ou minimiser les perturbations lors de la génération de signaux d'image
G06T 5/50 - Amélioration ou restauration d'image en utilisant plusieurs images, p.ex. moyenne, soustraction
H04N 25/618 - Traitement du bruit, p.ex. détection, correction, réduction ou élimination du bruit pour les bruits aléatoires ou de haute fréquence
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
24.
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.
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
G21C 19/40 - Dispositions pour prévenir l'apparition de conditions critiques, p.ex. pendant le stockage
G21C 19/07 - Râteliers de stockage; Piscines de stockage
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
27.
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
30.
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 1/08 - 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
31.
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
42 - Services scientifiques, technologiques et industriels, recherche et conception
Produits et services
Software as a service (SAAS) services featuring software for
database and digital management of personnel; software as a
service (SAAS) services featuring software for personnel
training.
42 - Services scientifiques, technologiques et industriels, recherche et conception
Produits et services
nuclear micro reactors; nuclear small modular reactors engineering services in the field of nuclear micro reactors; engineering services in the field of nuclear small modular reactors; designing nuclear components for nuclear micro reactors and equipment for nuclear micro reactors; scientific development of nuclear reactors; scientific research in the field of nuclear reactors
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
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 3/07 - Enveloppes; Chemises caractérisées par le matériau, p.ex. alliages
G21C 3/08 - Enveloppes; Chemises munis de moyens externes pour favoriser l'échange de chaleur, p.ex. ailettes, déflecteurs, cannelures
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 3/20 - 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 21/02 - Fabrication des éléments combustibles ou surrégénérateurs à l'intérieur de gaines non-actives
42 - Services scientifiques, technologiques et industriels, recherche et conception
Produits et services
(1) Software as a service (SAAS) services featuring software for database and digital management of personnel; software as a service (SAAS) services featuring software for personnel training.
37.
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
39.
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.
G01T 1/167 - Mesure du contenu radioactif des objets, p.ex. contamination
G01M 3/38 - Examen de l'étanchéité des structures ou ouvrages vis-à-vis d'un fluide par utilisation de la lumière
41.
A 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.
42 - Services scientifiques, technologiques et industriels, recherche et conception
Produits et services
Small modular reactor; micro nuclear reactor. Engineering services in the field of nuclear micro reactors;
engineering services in the field of nuclear small modular
reactors; designing nuclear components for nuclear micro
reactors and equipment for nuclear micro reactors;
scientific development of nuclear reactors; scientific
research in the field of nuclear reactors.
Disclosed is an apparatus and method for conditioning fluid flow in a nuclear power plant steam generator. A flow conditioning device includes an outer enclosure defining a plurality of entrance apertures arranged in an array and a plurality of exit apertures arranged in an array. A plurality of baffle plates are defined within the outer housing. The baffle plates define flow channels in fluid communication with the entrance and exit apertures to create a flow path of alternating directions. The flow channels receive fluid flow from the plurality of entrance apertures, direct the fluid flow from the entrance apertures in alternating directions through the flow channels to impart turning and frictional pressure loss to the fluid flow, and direct exiting fluid flow through the exit apertures into the tubelane region of the steam generator.
42 - Services scientifiques, technologiques et industriels, recherche et conception
Produits et services
Providing temporary use of non-downloadable computer
software framework for creating SaaS applications for
organizing, visualizing and integrating nuclear power plant
data across engineering disciplines; providing temporary use
of non-downloadable computer software framework for creating
SaaS applications for document management, and data and
process control and management.
42 - Services scientifiques, technologiques et industriels, recherche et conception
Produits et services
(1) Small modular reactor; micro nuclear reactor. (1) Engineering services in the field of nuclear micro reactors; engineering services in the field of nuclear small modular reactors; designing nuclear components for nuclear micro reactors and equipment for nuclear micro reactors; scientific development of nuclear reactors; scientific research in the field of nuclear reactors.
47.
METHOD AND DEVICE FOR DIRECT PRODUCTION OF RADIO-ISOTOPE BASED CANCER TREATMENT PHARMACEUTICALS
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
The present disclosure is generally related to methods, systems and devices for direct production of a radioisotope-based cancer treatment pharmaceutical 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. According to some aspects of the present disclosure, the radioisotope-based cancer treatment pharmaceutical includes lutetium-177 (Lu-177) and the corresponding non-radioactive drug molecule precursor includes lutetium-176 (Lu-176).
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
A61K 51/00 - Préparations contenant des substances radioactives utilisées pour la thérapie ou pour l'examen in vivo
C07B 59/00 - Introduction d'isotopes d'éléments dans les composés organiques
49.
SELF-POWERED NUCLEAR RADIATION DETECTOR AND METHOD OF CORRECTING A TEMPERATURE-RELATED CHANGE OF AN OUTPUT SIGNAL OF SAME
A self-powered nuclear radiation detector. The self-powered nuclear radiation detector includes a cable assembly, a temperature compensation assembly, and a metallic outer sheath. The cable assembly includes a metallic signal lead, an insulative material surrounding the metallic signal lead, and a metallic sheath surrounding the insulative material. The temperature compensation assembly includes a second metallic signal lead, a second insulative material surrounding the second metallic signal lead, and a second metallic sheath surrounding the second insulative material. The metallic outer sheath surrounds the cable assembly and the temperature compensation assembly.
A 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
52.
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
56.
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. In various aspect, a powder collection and blockage device is disclosed. The device can be positioned between upper and lower absorber materials of a control rod of the RCCA and/or CEA. The device can be configured to prevent powder generated by the upper absorber material from passing to a lower portion of the control rod. In another aspect, a plenum volume of the control rod can be increased by incorporating an axial hole into a top end plug extension and/or a bottom end plug.
42 - Services scientifiques, technologiques et industriels, recherche et conception
Produits et services
Software as a service (SAAS) services featuring software for database and digital management of personnel; software as a service (SAAS) services featuring software for personnel training
58.
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.
UNIVERSITY OF PITTSBURGH - OF THE COMMONWEALTH SYSTEM OF HIGHER EDUCATION (USA)
Inventeur(s)
Heibel, Michael D.
Lopresti, Brian J.
Congedo, Thomas V.
Abrégé
Devices, systems, and methods to produce Ac-225 from Ra-226 using gamma-radiation generator are disclosed herein. The gamma radiation generator can utilize an electronic neutron generator or a nuclear reactor to produce high energy prompt-capture gamma-radiation. The Ra-226 is irradiated by the gamma radiation to produce Ra-225, which decays to produce Ac-225. The method of using electronic neutron generator and an irradiation target material such as Gd-157 to produce high energy gamma radiation without using a continuously decaying radioisotope such as Co-60 could significantly reduce the cost and increase the safety associated with the production of high energy gamma radiation and Ac-225.
G21G 1/12 - 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 électromagnétique, p.ex. de rayons gamma ou de rayons X
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
An insertable flux thimble interface (50) for use in a bottom nozzle (12) of a fuel assembly (10) in a nuclear reactor (i.e., a bottom nozzle insert (200)) 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 (70). 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
64.
NON-INVASIVE LIQUID METAL FLOW MEASUREMENT IN LIQUID METAL FUEL ASSEMBLIES, REACTOR COOLANT PUMPS, AND TEST CARTRIDGES
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.
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
G21C 17/032 - Mesure ou surveillance du débit de réfrigérant
65.
NON-INVASIVE LIQUID METAL FLOW MEASUREMENT IN LIQUID METAL FUEL ASSEMBLIES, REACTOR COOLANT PUMPS, AND TEST CARTRIDGES
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
66.
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
70.
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
42 - Services scientifiques, technologiques et industriels, recherche et conception
Produits et services
Providing information in the field of nuclear energy via an
interactive website; computer services, namely, hosting an
interactive web site that allows users to learn about
products and services in the field of nuclear and renewable
power generation.
Annular nuclear fuel rods (100) are disclosed. The annular nuclear fuel rods include an outer cladding tube (102) made of ceramic composite or cermet composite, an inner cladding tube (104) made of ceramic composite or cermet composite, a nuclear fuel region (106) located between the outer cladding tube and inner cladding tube, and an open channel (108) for liquid coolant to flow.
Annular nuclear fuel rods (100) are disclosed. The annular nuclear fuel rods include an outer cladding tube (102) made of ceramic composite or cermet composite, an inner cladding tube (104) made of ceramic composite or cermet composite, a nuclear fuel region (106) located between the outer cladding tube and inner cladding tube, and an open channel (108) for liquid coolant to flow.
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
77.
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
79.
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
42 - Services scientifiques, technologiques et industriels, recherche et conception
Produits et services
Small modular reactor; micro nuclear reactor Engineering services in the field of nuclear micro reactors; Engineering services in the field of nuclear small modular reactors; Designing nuclear components for nuclear micro reactors and equipment for nuclear micro reactors; Scientific development of nuclear reactors; Scientific research in the field of nuclear reactors
The present disclosure is generally related to methods, systems and devices for forming a randomized grain structure coating on a substrate of a component for use in a nuclear reactor to provide protection against corrosion and, more particularly, is directed to improved methods, systems and devices for forming a randomized grain structure coating on a zirconium alloy nuclear fuel cladding tube using a cathodic arc (CA) physical vapor deposition (PVD) process to provide protection against corrosion in both normal operation and in transient and accidents of the nuclear reactor.
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
83.
HELIUM FLOW STOP ASSEMBLY (HFSA) FOR TIG WELDING PROCESS OF NUCLEAR FUEL RODS
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 37/00 - Dispositifs ou procédés auxiliaires non spécialement adaptés à un procédé couvert par un seul des autres groupes principaux de la présente sous-classe
B23K 9/167 - Soudage ou découpage à l'arc utilisant des gaz de protection et une électrode non consommable
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.
A61N 5/10 - Radiothérapie; Traitement aux rayons gamma; Traitement par irradiation de particules
A61K 41/00 - Préparations médicinales obtenues par traitement de substances par énergie ondulatoire ou par rayonnement corpusculaire
86.
A METHOD AND DEVICE TO CONTROL THE MOVEMENT OF CAPSULES CONTAINING COBALT MATERIAL LOCATED INSIDE CONTAINERS MADE OF NON-FERROMAGNETIC MATERIALS USING THE APPLICATION OF ELECTROMAGNETIC 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 19/02 - 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 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 19/34 - Procédés ou appareils de démantèlement du combustible nucléaire, p.ex. avant retraitement
G21C 23/00 - Dispositions dans les réacteurs pour faciliter les expériences ou l'irradiation
G21G 1/02 - Dispositions pour la conversion des éléments chimiques par rayonnement électromagnétique, radiations corpusculaires ou bombardement par des particules, p.ex. production d'isotopes radioactifs dans les réacteurs nucléaires
87.
A METHOD AND DEVICE TO CONTROL THE MOVEMENT OF CAPSULES CONTAINING COBALT MATERIAL LOCATED INSIDE CONTAINERS MADE OF NON-FERROMAGNETIC MATERIALS USING THE APPLICATION OF ELECTROMAGNETIC FORCE
An apparatus for removing irradiated Co-60 capsules from a plurality of burnable absorber rodlets. The apparatus comprises a solenoid that induces an electromagnetic flux into a Co-60 capsule and locks the Co-60 capsule in parallel with the apparatus. The apparatus is slideable along a longitudinal axis of the burnable absorber rodlet and causes the Co-60 capsule to overcome a plurality of forces exerted on it.
G21C 19/32 - Appareils pour enlever des objets ou matériaux radioactifs de l'aire de décharge du réacteur, p.ex. pour les porter à un emplacement de stockage; Appareils pour manipuler des objets ou matériaux radioactifs à l'intérieur d'un emplacement de stockage ou les extraire de celui-ci
G21G 1/02 - Dispositions pour la conversion des éléments chimiques par rayonnement électromagnétique, radiations corpusculaires ou bombardement par des particules, p.ex. production d'isotopes radioactifs dans les réacteurs nucléaires
88.
Device for magnetically removing a capsule containing Co-60 from a burnable absorber rodlet
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
89.
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.
42 - Services scientifiques, technologiques et industriels, recherche et conception
Produits et services
(1) Providing information in the field of nuclear energy via an interactive website; computer services, namely, hosting an interactive web site that allows users to learn about products and services in the field of nuclear and renewable power generation.
91.
MOTOR CONTROL CENTER CIRCUIT BREAKER REPLACEMENT KIT AND METHOD
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
42 - Services scientifiques, technologiques et industriels, recherche et conception
Produits et services
Providing temporary use of non-downloadable computer software framework for creating SaaS applications for organizing, visualizing and integrating nuclear power plant data across engineering disciplines; Providing temporary use of non-downloadable computer software framework for creating SaaS applications for document management, and data and process control and management
94.
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
100.
MODULAR THERMAL AND RADIATION SHIELDING WITH PASSIVE HEAT REMOVAL
A housing assembly (200) configured to house a reactor is disclosed. The housing assembly (200) includes a plurality of modular walls (202, 204) configured to surround the reactor and a passive temperature control system (230). The plurality of modular walls includes (202, 204) a first modular wall (202). The passive temperature control system (230) is coupled to the first modular wall (202). The passive temperature control system (230) is configured to transfer heat between the reactor and an area around the housing assembly (200).
G21C 15/257 - Cyclage du fluide réfrigérant utilisant des tubes caloporteurs
G21F 5/10 - Dispositifs d'évacuation de chaleur spécialement adaptés à ces récipients, p.ex. utilisant une circulation de fluide ou des ailettes de refroidissement
