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
2.
DEVICES, SYSTEMS, AND METHODS FOR THE ENHANCED OPERATION OF HYDRAULIC CONTROL UNITS OF A CONTROL ROD DRIVE MECHANISM TO REGULATE NUCLEAR FLUX IN A REACTOR CORE
A hydraulic control unit ("HCU") configured to control a control rod drive mechanism ("CRDM") configured to control the nuclear flux produced by a nuclear reactor is disclosed herein. The HCU can include a plurality of valves configured to attenuate a fluid pressure within the CRDM, wherein the attenuation of the fluid pressure is configured to cause a control rod of the CRDM to be inserted or withdrawn from a reactor vessel of the nuclear reactor, and a control circuit including a plurality of relay interfaces, wherein each relay of the plurality of relay interfaces is electrically coupled to a valve of the plurality of valves, a controller electrically coupled to the plurality of relay interfaces, and a communications circuit communicably coupled to a header controller, wherein the communications circuit is configured to transmit and receive signals between the controller and the header controller.
A 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.
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.
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
8.
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
9.
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
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
11.
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.
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.
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
14.
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.
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
17.
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
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.
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.
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
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
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
24.
PRODUCTION OF HIGH ENERGY GAMMA RADIATION USING AN ELECTRONIC NEUTRON GENERATOR FOR FOOD AND MEDICAL DEVICE STERILIZATION
Devices, systems, and methods for producing gamma radiation using a neutron generator are disclosed herein. In some aspects, a device for producing gamma radiation includes a neutron generator configured to generate a neutron flux field and a neutron capture reservoir including a neutron capture material. The neutron capture material can be configured to emit gamma radiation in response to exposure to the neutron flux field. In one aspect, the emitted gamma radiation can be used to sterilize a food product. In another aspect, the emitted gamma radiation can be used to sterilize a medical device.
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.
A system configured to monitor the structural health of reactor vessel internals of a nuclear reactor is disclosed herein. The system includes a memory configured to store historical information associated with past performance of the nuclear reactor, and an anomaly detection subsystem including a control circuit configured to receive a signal from a sensor. The anomaly detection subsystem is configured to determine, via the control circuit, a characteristic of a vibrational response of the reactor vessel internals based, at least in part, on the signal; access, via the control circuit, the historical information stored in the memory; compare, via the control circuit, the determined characteristic to the historical information stored in the memory; and determine, via the control circuit, a condition of the reactor vessel internals based, at least in part, on the comparison of the determined characteristic and the historical information.
Devices, systems, and methods for power generation using irradiators (102) and other gamma ray sources are disclosed herein. In various aspects, an irradiator-based power generation device (100) is disclosed. The power generation device can include a radiator layer (104) configured to at least partially surround an irradiator (102), wherein the radiator layer (104) comprises a radiator material configured to emit delta radiation in response to exposure to gamma radiation; an electrical insulation layer (108) configured to surround the radiator layer (104), wherein the electrical insulation layer (108) comprises an electrical insulation material configured to allow delta radiation to penetrate therethrough; and a collector layer (110) configured to surround the electrical insulation layer (108), wherein the collector layer (110) comprises a collector material configured to collect delta radiation.
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 method of processing a nuclear material for use as a nuclear fuel in a 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 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 (110) into a first stream (112) and a second stream (114); enriching, via the emitted beam of electromagnetic radiation, a concentration of the targeted isotope to a predetermined concentration; dispositioning, via a sensitivity to the determined wavelength, the enriched concentration of the targeted isotope to the first stream; and dispositioning, via a lack of sensitivity to the determined wavelength, the non-targeted isotope to the second stream.
G21C 19/42 - Retraitement des combustibles irradiés
B01D 59/34 - Séparation par méthodes photochimiques
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
A nuclear reactor core mechanical support bracket is disclosed. The support bracket includes a housing, a spring disposed internally within the housing, a shaft slidingly disposed within the housing and to engage the spring to compress and decompress the spring as the shaft travels in and out of the housing, a shaft travel pin to control the travel of the shaft, and a flange to mount the support bracket to a canister of a nuclear reactor. The shaft includes an inset configured to interface with a nuclear reactor core component.
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
G21D 3/00 - Commande des installations à énergie nucléaire
32.
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.
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.
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 (114), wherein the nuclear fuel assembly is configured such that a hydrogen to uranium ratio for the fuel assembly, when coolant and the fissile material (114) 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.
In one aspect, a reactor unit cell (202) is disclosed. The reactor unit cell includes a graphite moderator structure (204), a heat pipe (208) positioned in the graphite moderator structure, and a fuel assembly (210) positioned in the graphite moderator structure. The fuel assembly comprises a beryllium-oxide sleeve (212) and nuclear fuel (214) positioned in the beryllium-oxide sleeve.
G21C 3/07 - Enveloppes; Chemises caractérisées par le matériau, p.ex. alliages
G21C 15/08 - Aménagement ou disposition de passages dans lesquels la chaleur est transférée au réfrigérant, p.ex. pour la circulation du réfrigérant à travers les supports des éléments combustibles provenant du matériau modérateur
G21C 15/257 - Cyclage du fluide réfrigérant utilisant des tubes caloporteurs
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 5/00 - Structure du modérateur ou du cœur; Emploi de matériaux spécifiés comme modérateur
36.
SYSTEMS AND METHODS FOR WIRELESS REMOTE CONTROL OF AUTOMATED EQUIPMENT
Systems and methods for the remote control of automated equipment are disclosed herein. The systems and methods include automated equipment configured to execute a process in a restricted location by performing operations based on predetermined programming. In some embodiments, the process is a welding process and the restricted location is a nuclear containment building. The system and methods also include cellular routers configured to enable communication of operating parameters between the automated equipment and a human machine interface (HMI). An operator is able to remotely modify operations of the automated equipment, without being inside of or at the site of the restricted location, by changing the operating parameters using the HMI.
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 (Hf), 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 14/16 - Matériau métallique, bore ou silicium sur des substrats métalliques, en bore ou en silicium
C23C 14/35 - Pulvérisation cathodique par application d'un champ magnétique, p.ex. pulvérisation au moyen d'un magnétron
C23C 28/02 - Revêtements uniquement de matériaux métalliques
G21C 3/07 - Enveloppes; Chemises caractérisées par le matériau, p.ex. alliages
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
38.
RADIOISOTOPE ACTIVITY SURVEILLANCE APPARATUS, SYSTEM, AND METHOD
Disclosed are a radioisotope activity surveillance system and methods. The system includes a fuel rod assembly having a plurality of nuclear fuel rods and a target assembly having a top nozzle including an orifice plate and at least one target material rod fixedly coupled to the orifice plate. The least one target material rod is slidably disposed within the fuel rod assembly. A sensing assembly defines an opening sized and configured to receive the target assembly therethrough. The sensing assembly includes a self-powered detector assembly to detect radioisotope activity of the target rod material. Also disclosed is a method for measuring a self-powered detector signal to calculate radioisotope activity of a target assembly and a method for analyzing total activity of a desired radioisotope.
G21C 17/06 - Dispositifs ou dispositions pour la surveillance ou le test du combustible ou des éléments combustibles en dehors du cœur du réacteur, p.ex. pour la consommation ou pour la contamination
G21C 23/00 - Dispositions dans les réacteurs pour faciliter les expériences ou l'irradiation
G21G 1/02 - Dispositions pour la conversion des éléments chimiques par rayonnement électromagnétique, radiations corpusculaires ou bombardement par des particules, p.ex. production d'isotopes radioactifs dans les réacteurs nucléaires
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.
An adjustable core assembly for a nuclear reactor is disclosed herein. The adjustable core can include a plurality of reactivity control cells configured to accommodate a reactivity control rod, and a plurality of unit cells. The plurality of unit cells defines a radial dimension corresponding to an initial power output of the core. Each unit cell of the plurality of unit cells is configured to accommodate fuel configured to generate energy and a heat pipe configured to transfer thermal energy away from the core. Each unit cell of the plurality unit cells can be coupled to an adjacent unit cell in a radial direction, thereby altering the radial dimension, wherein the altered radial dimension corresponds to an adjusted power output of the core, and wherein the adjusted power output of the core is different than the initial power output of the core.
G21C 15/257 - Cyclage du fluide réfrigérant utilisant des tubes caloporteurs
G21C 1/32 - Réacteurs du type intégré, c. à d. réacteurs dans lesquels des parties associées de façon fonctionnelle avec le réacteur, mais non essentielles à la réaction, p.ex. des échangeurs de chaleur, sont disposées à l'intérieur de l'enveloppe avec le cœur
41.
ENHANCED GRAPHITE NEUTRON REFLECTOR WITH BERYLLIUM OXIDE INCLUSIONS
A nuclear reactor (100) is disclosed that includes a reactor core (102) and a reflector assembly (150) that surrounds the reactor core. The reflector assembly includes a stationary reflector component (152) that includes a graphite support structure (156) including a plurality of channels (158) defined therein and a plurality of beryllium-oxide pins (160) positioned in the channels.
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 15/02 - 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
43.
DEVICES, SYSTEMS, AND METHODS FOR CONFIGURING THE LAYOUT OF UNIT CELL OF A REACTOR CORE
A configurable unit cell of a core of a nuclear reactor is disclosed herein. The configurable unit cell includes a core block material and a plurality of interchangeable components configured to affect a performance parameter of the core of the nuclear reactor. The configurable unit cell further includes a plurality of channels defined within the core block material. Each channel of the plurality of channels is configured to engage an interchangeable component of the plurality of interchangeable components in an operating configuration. Each channel of the plurality of channels is separated from an adjacent channel of the plurality of channels by a predetermined pitch.
G21C 3/322 - Moyens pour influencer l'écoulement du réfrigérant à travers ou autour des faisceaux
G21C 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 5/02 - Structure du modérateur ou du cœur; Emploi de matériaux spécifiés comme modérateur - Détails
G21C 5/12 - Structure du modérateur ou du cœur; Emploi de matériaux spécifiés comme modérateur caractérisée par la composition, p.ex. le modérateur contenant des substances additionnelles qui assurent une meilleure résistance du modérateur
G21C 11/06 - Ecrans réflecteurs, c. à d. pour minimiser la perte de neutrons
G21C 15/08 - Aménagement ou disposition de passages dans lesquels la chaleur est transférée au réfrigérant, p.ex. pour la circulation du réfrigérant à travers les supports des éléments combustibles provenant du matériau modérateur
G21C 15/257 - Cyclage du fluide réfrigérant utilisant des tubes caloporteurs
44.
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.
G01N 35/00 - Analyse automatique non limitée à des procédés ou à des matériaux spécifiés dans un seul des groupes ; Manipulation de matériaux à cet effet
G01T 7/02 - Moyens de collection pour recevoir ou conserver des échantillons à examiner
45.
COATED FUEL PELLETS WITH ENHANCED WATER AND STEAM OXIDATION RESISTANCE
Disclosed herein is a method comprising coating a fissile, uranium-containing ceramic material (72) with a water-resistant layer (74), the layer being non-reactive with the fissile, uranium-containing ceramic material. The coating is applied to a surface of the fissile, uranium-containing ceramic material. Also disclosed is a fuel for use in a nuclear reactor.
G21C 3/20 - Eléments combustibles - Détails de structure - Détails de structure à l'intérieur de l'enveloppe avec une intercouche non active entre l'enveloppe et le matériau actif
A system for determining coolant flow rate in a nuclear reactor primary cooling loop (100, 200) includes a processor (310) and a memory (320). 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 (154, 212a, b) in the cooling loop; calculate a model (250) 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.
METHOD AND SYSTEM FOR PERIODICALLY MEASURING THE TOTAL GAMMA RADIATION ACTIVITY OF A TARGET RADIOISOTOPE BEING PRODUCED INSIDE THE CORE OF A NUCLEAR REACTOR
A system for measuring radiation activity of a target radioisotope being produced in a reactor core is disclosed. The system includes a cable assembly and a radiation detector. The cable assembly includes a housing, a target cable configured to position the housing, and a drive cable couplable and decouplable with the target cable. The target radioisotope is positioned within the housing. The drive cable is configured to drive the target cable. The radiation detector configured to periodically measure the radiation activity of the target radioisotope being produced.
G21C 19/22 - Dispositions pour avoir accès à l'intérieur de l'enceinte sous pression pendant le fonctionnement du réacteur
G21G 1/02 - Dispositions pour la conversion des éléments chimiques par rayonnement électromagnétique, radiations corpusculaires ou bombardement par des particules, p.ex. production d'isotopes radioactifs dans les réacteurs nucléaires
G21C 23/00 - Dispositions dans les réacteurs pour faciliter les expériences ou l'irradiation
48.
SELF-POWERED NUCLEAR RADIATION DETECTOR AND METHOD OF CORRECTING A TEMPERATURE-RELATED CHANGE OF AN OUTPUT SIGNAL OF SAME
A self-powered nuclear radiation detector. The self-powered nuclear radiation detector includes a cable assembly, a temperature compensation assembly, and a metallic outer sheath. The cable assembly includes a metallic signal lead, an insulative material surrounding the metallic signal lead, and a metallic sheath surrounding the insulative material. The temperature compensation assembly includes a second metallic signal lead, a second insulative material surrounding the second metallic signal lead, and a second metallic sheath surrounding the second insulative material. The metallic outer sheath surrounds the cable assembly and the temperature compensation assembly.
A manipulator configured to navigate a heat exchanger including a plurality of tubes extending through a tubesheet is disclosed herein, the manipulator including a first end effector, a second end effector, and an articulation assembly. The first end effector is configured to accommodate an instrument configured to service the heat exchanger and includes a first actuator configured to extend a first gripper into a tube of the plurality of tubes. The second end effector includes a second actuator configured to extend a second gripper into a tube of the plurality of tubes. The first and second gripper are configured to secure the manipulator to the tubesheet, and, when the second gripper is securing the manipulator to the tubesheet, the articulation assembly is configured to enable the first end effector to move relative to the second end effector in a plane that is parallel to the tubesheet.
B25J 9/04 - Manipulateurs à commande programmée caractérisés par le mouvement des bras, p.ex. du type à coordonnées cartésiennes par rotation d'au moins un bras en excluant le mouvement de la tête elle-même, p.ex. du type à coordonnées cylindriques ou polaires
B25J 9/06 - Manipulateurs à commande programmée caractérisés par des bras à articulations multiples
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 !east 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 17/017 - Inspection ou maintenance de tuyaux ou de tubes dans des installations nucléaires
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 7/12 - Moyens pour amener les éléments de commande dans la position désirée
G21C 13/067 - Bouchons scellés pour des tubulures, p.ex. puits de chargement; Dispositifs de verrouillage pour bouchons
51.
METHODS AND SYSTEMS FOR SEPARATION OF THORIUM FROM URANIUM AND THEIR DECAY PRODUCTS
Methods and systems (300) for separation of thorium from uranium and their decay products are provided. The method comprises combining a nuclear fuel feedstock (102) comprising thorium and uranium with a first acid (104, 204) to form a first solution. The first solution is contacted an ion exchange resin (308) that is selective for thorium or uranium. The thorium or uranium is at least partially removed from the first solution by binding the thorium or uranium to the ion exchange resin (308) thereby forming a second solution (106 206). The second solution (106, 206) is combined with oxalic acid to precipitate uranium or thorium from the second solution to form a precipitate (110, 210). The precipitate (110, 210) is separated from the second solution (106, 206).
G21G 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
G21G 4/08 - Sources radioactives autres que les sources de neutrons caractérisées par des aspects de leur structure spécialement adaptées aux applications médicales
B01J 39/04 - Procédés utilisant des échangeurs organiques
METHODS FOR MANUFACTURING NANOSTRUCTURED AND COMPOSITIONALLY-TAILORED TUBES AND COMPONENTS BY LOW TEMPERATURE, SOLID-STATE COLD SPRAY POWDER DEPOSITION
Disclosed is a method for manufacturing free-standing cladding tubes with multi-layer structures. According to the method, a cylindrical mandrel substrate defining a hollow cylindrical inner space is provided. A first cold spray powder metal is selected. The cylindrical mandrel substrate is rotated and the first cold spray powder metal is applied to an outer surface of the cylindrical mandrel substrate to form a first layer. The cylindrical mandrel substrate is removed.
C23C 28/02 - Revêtements uniquement de matériaux métalliques
C23C 30/00 - Revêtement avec des matériaux métalliques, caractérisé uniquement par la composition du matériau métallique, c. à d. non caractérisé par le procédé de revêtement
C23C 24/00 - Revêtement à partir de poudres inorganiques
C23C 24/08 - Revêtement à partir de poudres inorganiques en utilisant la chaleur ou une pression et la chaleur
53.
METHOD FOR REDUCING RADIOLOGICALLY-CONTAMINATED WASTE
Provided herein is a method for reducing radiologically-contaminated waste. The method comprises treating radiologically-contaminated surfaces, wherein the radiologically- contaminated surfaces are treated with a surface treatment agent; treating radiologically- contaminated subsurfaces, wherein the radiologically-contaminated subsurfaces are treated with a surface/subsurface treatment agent; consolidating soil waste; employing real-time scanning technology to classify waste, wherein the classifying is based at least in part on a threshold of radiological contamination, and wherein the classified waste is sorted based on the classification; and disposing of the waste via at least one of different disposal routes, based at least in part on the classification.
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 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.
Channel boxes (100) for a boiling water reactor and methods of manufacture thereof are provided. The channel box comprises a substrate (102) and a first layer (104). The substrate comprises atubular shape. The substrate comprises silicon carbide fibers. The first layer is deposited on a firstsurface (102a) of the substrate and the first layer comprises a corrosion resistant metallic composition.
G21C 3/324 - Chemisages ou enveloppes pour les faisceaux
C04B 35/565 - Produits céramiques mis en forme, caractérisés par leur composition; Compositions céramiques; Traitement de poudres de composés inorganiques préalablement à la fabrication de produits céramiques à base de non oxydes à base de carbures à base de carbure de silicium
B32B 18/00 - Produits stratifiés composés essentiellement de céramiques, p.ex. de produits réfractaires
57.
INTERNAL HYDROFORMING METHOD FOR MANUFACTURING HEAT PIPE WICKS UTILIZING A HOLLOW MANDREL AND SHEATH
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.
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
B21D 39/04 - Utilisation de procédés permettant d'assembler des objets ou des parties d'objets, p.ex. revêtement par des tôles, autrement que par placage; Dispositifs de mandrinage des tubes des tubes avec des barres
58.
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 tire second recess, lire expandable tube and the forming shell assembly are configured to deform the wick mesh and form the wick based on the expandable tube hydraulically expanding towards the expanded configuration.
B21D 39/04 - Utilisation de procédés permettant d'assembler des objets ou des parties d'objets, p.ex. revêtement par des tôles, autrement que par placage; Dispositifs de mandrinage des tubes des tubes avec des barres
F28D 15/04 - Appareils échangeurs de chaleur dans lesquels l'agent intermédiaire de transfert de chaleur en tubes fermés passe dans ou à travers les parois des canalisations dans lesquels l'agent se condense et s'évapore, p.ex. tubes caloporteurs avec des tubes ayant une structure capillaire
59.
METHOD OF INSTALLING A HEAT PIPE WICK INTO A CONTAINER OF DIFFERING THERMAL EXPANSION COEFFICIENT
A heat pipe is disclosed to include a container, a container lid which includes a groove defined therein, a wick, and an end plug operably coupled to the wick. The end plug includes a pin extending therefrom, and the groove of the container lid is configured to receive the pin.
F28D 15/04 - Appareils échangeurs de chaleur dans lesquels l'agent intermédiaire de transfert de chaleur en tubes fermés passe dans ou à travers les parois des canalisations dans lesquels l'agent se condense et s'évapore, p.ex. tubes caloporteurs avec des tubes ayant une structure capillaire
60.
A FIXED IN-CORE DETECTOR DESIGN USING SIC SCHOTTKY DIODES CONFIGURED WITH A HIGH AXIAL AND RADIAL SENSOR DENSITY AND ENHANCED FISSION GAMMA MEASUREMENT SENSITIVITY
A system for measuring gamma spectroscopy of a neutron irradiated material includes a plurality of semiconductor sensors. Each of the semiconductor sensors includes a gamma ray receiving surface disposed above a Shottky layer in contact with an n-doped active layer. The receiving surface is configured to emit electrons upon irradiation by gamma rays. The receiving surface contacts an adjustable telescoping mount configured to adjust the distance between the receiving surface and the Shottky layer. The n-doped layer is fabricated to have a thickness designed to pass through electrons having greater than a defined energy. The combination of adjustable receiving surface and active layer thickness define a minimum and maximum energy response of each of the sensors. Multiple sensors may be integrated in an array in which each sensor has its own energy response. An array of such sensors can measure the gamma spectrum of a material irradiated with neutrons.
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.
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.
A reactor core block (200) is disclosed including a fuel channel (202), a heat pipe (204), a primary moderator matrix (206) configured to encompass the fuel channel (202) and the heat pipe (204), and a secondary moderator channel (208) configured to at least partially surround the fuel channel (202), the heat pipe (204), and the primary moderator matrix (206). The secondary moderator channel (208) is comprised of metal hydride.
G21C 15/257 - Cyclage du fluide réfrigérant utilisant des tubes caloporteurs
G21C 5/12 - Structure du modérateur ou du cœur; Emploi de matériaux spécifiés comme modérateur caractérisée par la composition, p.ex. le modérateur contenant des substances additionnelles qui assurent une meilleure résistance du modérateur
G21C 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
64.
METAL WICK CRIMPING METHOD FOR HEAT PIPE INTERNALS
A wick assembly for use with a heat pipe is disclosed. The wick assembly includes an end plug including a wick receiving area, a wick, and a crimp. A portion of the wick is positioned about the wick receiving area. The crimp is positioned about the portion of the wick and the wick receiving area. The end plug, the portion of the wick, and the crimp are diffusion bonded.
F28D 15/04 - Appareils échangeurs de chaleur dans lesquels l'agent intermédiaire de transfert de chaleur en tubes fermés passe dans ou à travers les parois des canalisations dans lesquels l'agent se condense et s'évapore, p.ex. tubes caloporteurs avec des tubes ayant une structure capillaire
G21C 15/257 - Cyclage du fluide réfrigérant utilisant des tubes caloporteurs
A 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 5/06 - Récipients blindés portatifs ou transportables - Détails ou accessoires des récipients
66.
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
67.
UNIVERSAL REACTOR VESSEL HEAD INSPECTION PLATFORM ASSEMBLY
A mobile robotic assembly for guiding an end effector (700) in inspecting reactor vessel heads (402, 502, 602) is disclosed. The mobile robotic assembly includes a mobile platform (10); a support assembly (3) extending vertically from the mobile platform (10), wherein the support assembly (3) comprises an adjustable height; and a robotic arm (11) attached to and extending laterally from the support assembly (3).
A nuclear fuel assembly (430, 530) and a method of manufacture thereof are provided. The method comprises depositing a thermally conductive layer (104) onto at least a portion of at least two nuclear fuel layers (102) to create at least two at least partially coated layers (120). The method comprises stacking the at least two coated layers (120) and bonding the at least two coated layers (120) to form a nuclear fuel assembly (430, 530).
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 7/04 - Commande de la réaction nucléaire par utilisation des propriétés autorégulatrices des matériaux du réacteur de poisons combustibles
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
A block style heat exchanger for a heat pipe reactor having a plurality of heat pipes extending from a reactor core. The heat exchanger includes a plurality of primary channels, each for receiving heat transferred from the core via one of the heat pipes. The primary channels extending within a block of one or more materials. The heat exchanger also includes a plurality of secondary channels defined within the block for transmitting a flow of the secondary heat transfer medium through the heat exchanger from an inlet to an outlet. The block is formed from one or both of: a plurality of plates bonded together, with each plate defining at least a portion of one or more of the plurality of primary channels and/or the plurality of secondary channels, and/or a unitary piece of material formed from an additive manufacturing process.
A portable real-time system monitoring device is advantageously capable of autonomously learning the normal behavior of any system and of alerting the user or taking other action when the system becomes unpredictable or otherwise undesirable. No prior knowledge about the system is needed by the device. This is because the device uses a combination of machine learning and statistical process control to autonomously develop its own model of the monitored system and then autonomously monitor the system for unexpected behavior. Therefore, without any prior analysis or model creation, it can be deployed on any system, and it can be reused on any other system after it has been reset. The advantageous device of the disclosed and claimed concept performs this function in either real time or near real-time.
A runner assembly for mounting to, and rotating with, a pump shaft of a pump includes a support member to be fixed to the pump shaft; a seal face ring positioned on, and mounted to the support member by a support shroud coupled to the support member; and an outer O-ring positioned in an upward and radially outward facing notch defined in a top portion of the support member. The outer O-ring forms a static sealed joint between the top of the support member and the bottom of the seal face ring.
F04D 29/12 - Joints d'étanchéité pour arbre utilisant des bagues
F16J 15/34 - Joints d'étanchéité entre deux surfaces mobiles l'une par rapport à l'autre par bague glissante pressée contre la face plus ou moins radiale d'une des deux parties
72.
METHOD AND APPARATUS EMPLOYING VANADIUM NEUTRON DETECTORS
Disclosed herein is a method (300) pertaining to a power distribution of a reactor core of a nuclear installation, the method being executed on a general purpose computer. The method (300) comprises: measuring current values from a plurality of vanadium neutron detector assemblies (10) which are disposed in the reactor core of the nuclear installation (302); determining a measured relative core power distribution based upon the measured current values (304); producing a measured core power distribution based upon the measured relative core power distribution (306); and verifying that the reactor is operating within the licensed core operating limits based at least in part upon the measured core power distribution (308). Also disclosed herein is a vanadium neutron detector (1-5) assembly (10).
A system for use in shutting down a nuclear reactor includes a housing that defines a region therein sealed from an ambient environment and a gate member disposed within the region in a manner such that the gate member segregates the region into a first compartment and a second compartment isolated from the first compartment. The gate member is formed from a material having a predetermined melting point. The system further includes a neutron absorbing material disposed within the first compartment and a dispersion mechanism disposed within the region. The dispersion mechanism structured to encourage the neutron absorbing material from the first compartment into the second compartment.
G21C 9/02 - Moyens pour effectuer une réduction très rapide du facteur de réactivité dans des conditions défectueuses, p.ex. fusible pour réacteur
G21C 7/06 - 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
74.
PHYSICAL VAPOR DEPOSITION OF CERAMIC COATINGS ON ZIRCONIUM ALLOY NUCLEAR FUEL RODS
22N, 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.
A motor control center circuit breaker replacement kit includes a standoff having a first plurality of mounting holes corresponding to existing holes on a bucket of the motor control center and a second plurality of holes corresponding to existing holes on a circuit breaker, a door interface panel having a third plurality of holes corresponding to existing holes on a door of the motor control center, the door interface panel having an opening formed therein having a size and shape corresponding to a handle operator associated with the circuit breaker, and a safety latch having a slot structured to receive a tab of the handle operator.
An ultrasonic testing 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
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.
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.
C23C 24/00 - Revêtement à partir de poudres inorganiques
C23C 24/08 - Revêtement à partir de poudres inorganiques en utilisant la chaleur ou une pression et la chaleur
C23C 24/10 - Revêtement à partir de poudres inorganiques en utilisant la chaleur ou une pression et la chaleur avec formation d'une phase liquide intermédiaire dans la couche
B05B 7/08 - Pistolets pulvérisateurs; Appareillages pour l'évacuation avec des orifices de sortie séparés, p.ex. pour former des jets parallèles, pour former des jets croisés
B05B 7/14 - Appareillages de pulvérisation pour débiter des liquides ou d'autres matériaux fluides provenant de plusieurs sources, p.ex. un liquide et de l'air, une poudre et un gaz agencés pour projeter des matériaux en particules
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
79.
MODULAR RADIOISOTOPE PRODUCTION CAPSULES AND RELATED METHOD
A radioisotope production capsule is described. Each capsule includes generally an inner container for housing one of a target material and a neutron moderator, an outer container surrounding the inner container for housing the one of the target material and the neutron moderator not housed by the inner container, and cladding for isolating the target material from the neutron moderator. One or more modular capsules are placed in each of a plurality of plug fingers. Each single plug finger loaded with one or more capsules is inserted into a guide thimble of an array of guide thimbles in a fuel assembly.
G21G 1/02 - Dispositions pour la conversion des éléments chimiques par rayonnement électromagnétique, radiations corpusculaires ou bombardement par des particules, p.ex. production d'isotopes radioactifs dans les réacteurs nucléaires
G21C 23/00 - Dispositions dans les réacteurs pour faciliter les expériences ou l'irradiation
80.
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 dry cask storage system for spent nuclear fuel includes a detection apparatus having a resonant electrical circuit, with resonant electrical circuit being situated within an interior region of a metallic vessel wherein the SNF is situated. The detection apparatus includes a transmitter that generates an excitation pulse that causes the resonant circuit to resonate and to generate a response pulse. The resonant circuit includes an inductor that is formed with a core whose magnetic permeability varies with temperature such that the frequency of the resonant circuit varies as a function of temperature. The response pulse is then used to determine the temperature within the interior of the vessel where the SNF is situated. Pressure detection is also provided.
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 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
G21F 5/008 - Récipients pour éléments combustibles
G21F 5/06 - Récipients blindés portatifs ou transportables - Détails ou accessoires des récipients
H04Q 9/00 - Dispositions dans les systèmes de commande à distance ou de télémétrie pour appeler sélectivement une sous-station à partir d'une station principale, sous-station dans laquelle un appareil recherché est choisi pour appliquer un signal de commande ou
82.
APPARATUS FOR PERFORMING IN-SITU ADHESION TEST OF COLD SPRAY DEPOSITS AND METHOD OF EMPLOYING
A testing arrangement and method of using in performing an in-situ adhesion test of a cold spray deposit on a surface of a structure. The testing arrangement includes a specimen member having a number of apertures defined therein and a loading arrangement coupled to the specimen member. The loading arrangement is configured to provide a mechanical force of a known magnitude to the specimen member. In performing an in-situ test of a cold spray deposit on a structure, the method includes positioning the testing arrangement with respect to a surface of the structure, depositing the cold spray deposit on the surface of the structure, and testing the adhesion of the cold spray deposit to the surface.
A method of controlling a nuclear power plant (10, 400) includes obtaining sensor data from one or more sensors (12, 404) of the nuclear power plant, providing the sensor data and a desired plant response to a neural network (200), wherein the neural network has been previously trained using a simulated nuclear power plant and is structured to determine at least one control system setting to achieve the desired plant response, determining at least one control system setting to achieve the desired plant response with the neural network, and setting or changing at least one control system setting of a control system (402) of the nuclear power plant to the at least one control system setting determined by the neural network.
G21D 3/08 - Régulation de différents paramètres dans l'installation
G05B 13/04 - Systèmes de commande adaptatifs, c. à d. systèmes se réglant eux-mêmes automatiquement pour obtenir un rendement optimal suivant un critère prédéterminé électriques impliquant l'usage de modèles ou de simulateurs
A sensor system for a fuel rod including a fuel pellet (150) stack, the sensor system including a wireless interrogator (50) disposed outside the fuel rod (2) and a passive sensor component (60) disposed within the fuel rod. The passive sensor component includes a receiver (62) structured to receive an interrogation signal and output an excitation signal in response to receiving the interrogation signal, a reference transmitter (64) structured to output a reference signal to the reference receiver (54) in response to the excitation signal, a sensing transmitter (66) structured to output a sensing signal to the sensing receiver (56) in response to the excitation signal, and a core (130) at least partially disposed within the sensing transmitter and coupled to move in conjunction with expansion or contraction of the fuel pellet stack, to move based on changes in pressure within the fuel rod, or to change temperature based on temperature changes within the fuel rod.
G21C 17/10 - Combinaison structurelle de l'élément combustible, de la barre de commande, du cœur du réacteur, ou de la structure du modérateur avec des instruments sensibles, p.ex. pour la mesure de la radioactivité, des contraintes
H04Q 9/00 - Dispositions dans les systèmes de commande à distance ou de télémétrie pour appeler sélectivement une sous-station à partir d'une station principale, sous-station dans laquelle un appareil recherché est choisi pour appliquer un signal de commande ou
A detection apparatus is a flow and temperature measuring device in the form of a tube (56) having a channel (60) positioned parallel to a coolant flow stream and contains a drogue (62) that is firmly attached to a mount (78) within the channel. The mount has a load detection (92) apparatus firmly imbedded near the flow inlet to the tube. The drogue has at least neutral buoyancy in the fluid at the minimum fluid temperature of interest. A change in the buoyancy of the drogue as a function of temperature and a corresponding change in the strain detection apparatus output in the fluid is determined by a combination of simple physics and calibration measurements. The relationship between changes in strain detection apparatus signal output and flow-rate-induced forces applied to the drogue surface are also determined using a combination of simple physics and calibration measurements. A system and method are also described.
G21C 17/022 - Dispositifs ou dispositions pour la surveillance du réfrigérant ou du modérateur pour la surveillance de réfrigérants ou de modérateurs liquides
G21C 17/10 - 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
An energy storage device includes a plurality of plates, each having a first and second surface, with at least one of the surfaces having a plurality of grooves formed therein. The device further includes inlet and outlet plenums for providing or receiving a heat transfer medium to or from the grooves. At least one of the first surface and the second surface having the plurality of grooves formed therein of a first plate is disposed in direct contact with the other one of the at least first surface and second surface of an adjacent second plate. Heat from the transfer medium is transferred to the plates in a charging mode of operation or transferred from the plates to the transfer medium in a discharging mode of operation when the heat transfer medium is passed along the grooves.
F28D 20/00 - Appareils ou ensembles fonctionnels d'accumulation de chaleur en général; Appareils échangeurs de chaleur de régénération non couverts par les groupes ou
F28F 21/04 - Structure des appareils échangeurs de chaleur caractérisée par l'emploi de matériaux spécifiés de pierre naturelle
88.
SYSTEM AND METHOD ENABLING SIGNALS FROM REPLACEMENT SELF-POWERED NEUTRON DETECTORS TO BE USED TO GENERATE INPUTS TO LEGACY SOFTWARE
A method whereby signals that are output by replacement SPNDs (40A-E) are converted into equivalent signals that would have been detected by legacy SPNDs (48A-D) for input to the legacy software. The replacement SPNDs have a different geometry than the legacy SPNDs and also have a different neutron sensitivity than the legacy SPNDs. The replacement SPNDs are subjected to a neutron flux in a core of a reactor and responsively output a set of signals. The set of signals and the geometry of the replacement SPNDs are employed to create a characterization of the neutron flux in the form of a curve (88) that represents flux as a function of location along the core of the reactor. The legacy geometry of the legacy SPNDs is then employed to find the values on the curve that correspond with the positions where the legacy SPNDs (64A-D) had been located to create inputs for the legacy software.
G01T 7/00 - MESURE DES RADIATIONS NUCLÉAIRES OU DES RAYONS X - Détails des instruments de mesure des radiations
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
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
90.
DEBRIS FILTERING SKIRT ARRANGEMENT FOR NUCLEAR FUEL ASSEMBLY BOTTOM NOZZLE AND BOTTOM NOZZLE INCLUDING SAME
A debris filtering skirt (52) configured for use with a flow plate (46) of a bottom nozzle (50) of a nuclear fuel assembly is disclosed herein. The debris filtering skirt (52) includes a base portion defining an opening between a bottom edge and a reactor vessel lower core plate (14), and the opening includes a dimension configured to position the bottom nozzle (50) a predetermined distance away from the reactor vessel lower core plate (14). The debris filtering skirt (52) also includes a plurality of holes (54), and at least one hole of the plurality of holes (54) 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 (50).
G21C 3/12 - Moyens formant partie de l'élément pour le positionner dans le cœur du réacteur; Entretoises extérieures à cet effet
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
B01D 29/00 - Filtres à éléments filtrants stationnaires pendant la filtration, p.ex. filtres à aspiration ou à pression, non couverts par les groupes ; Leurs éléments filtrants
91.
ENERGY CONTAINMENT STRUCTURES FOR NUCLEAR REACTORS
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.
22, wherein the fuel is dimensioned relative to the cladding to define gaps at each lateral end of the enclosure sufficiently large such that upon swelling in use, the fuel does not increase the strain on the cladding beyond the limits of the claddings strain tolerance. The lateral gaps at the ends of the fuel allow lateral expansion during swelling that reduces the strain on the cladding.
The method is well-suited for use in a reactor having a plurality of cladding tubes housed in a plurality of linearly arranged channels for flowing coolant past the cl adding tubes. The method includes monitoring channels for the occurrence of an increase in radiation above selected base lines indicative of the presence of at least one fission product in the coolant in at least one of the plurality7 of channels, monitoring the channels for the occurrence of time dependent changes in the strength of radiation in the coolant above the base line along the length of at least one of the plurality of channels. The leak location is calculated by triangulating the radiation readings from a fixed linear array of detectors positioned adjacent to the channel s to determine the location of the strongest radiation reading and the location along the length of the channel where the increase in radiation occurred.
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
G01T 1/24 - Mesure de l'intensité de radiation avec des détecteurs à semi-conducteurs
H01L 31/108 - Dispositifs sensibles au rayonnement infrarouge, visible ou ultraviolet caractérisés par une seule barrière de potentiel ou de surface la barrière de potentiel étant du type Schottky
H01L 31/118 - Dispositifs sensibles au rayonnement d'ondes très courtes, p.ex. rayons X, rayons gamma ou rayonnement corpusculaire du type détecteurs à barrière de surface ou à jonction PN superficielle, p.ex. détecteurs de particules alpha à barrière de surface
A 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 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 filtering arrangement for use in a bottom nozzle of a fuel assembly in a nuclear reactor includes a top surface, a bottom surface, a plurality of vertical wall portions arranged in a generally squared grid-like pattern which extend between the bottom surface and the top surface and define a plurality of non-circular passages extending between the bottom surface and the top surface through the arrangement, and a plurality of first debris filters which are each positioned between the top surface and the bottom surface to generally span across a respective one of the plurality of passages.
G21C 3/322 - Moyens pour influencer l'écoulement du réfrigérant à travers ou autour des faisceaux
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
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 3/33 - 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 21/00 - Appareillage ou procédés spécialement adaptés pour la fabrication des réacteurs ou de pièces de ceux-ci
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.
G01R 35/00 - Test ou étalonnage des appareils couverts par les autres groupes de la présente sous-classe
G01R 35/02 - Test ou étalonnage des appareils couverts par les autres groupes de la présente sous-classe des dispositifs auxiliaires, p.ex. des transformateurs pour appareils en fonction du rapport de transformation, de l'angle de phase ou de la puissance à l'utilisation
99.
IMPROVED CORROSION RESISTANCE OF ADDITIVELY-MANUFACTURED ZIRCONIUM ALLOYS
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.
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
B22F 3/105 - Frittage seul en utilisant un courant électrique, un rayonnement laser ou un plasma
B22F 3/24 - Traitement ultérieur des pièces ou objets
B23K 15/00 - Soudage ou découpage par faisceau d'électrons
A fuel assembly (200) for use in a nuclear reactor comprising a fuel bundle (200), a plenum header connection (100) positioned on the fuel bundle (200), a mast (300) extending from the fuel bundle (200), and a common fission gas plenum (400) extending from the mast (300) is disclosed. The reactor includes a vessel and coolant situated within the vessel. The fuel bundle (200) comprises a plurality of fuel elements (210) including nuclear fuel material positioned therein. The plenum header connection (100) comprises a plurality of passageways (130, 135) defined therein that are in fluid communication with the nuclear fuel material. The elongate mast (300) comprises an internal passage (320) connecting the common fission gas plenum (400) to the plurality of passageways (130, 135) of the plenum header connection (100) such that the common fission gas plenum (400) is configured to receive an amount of fission gas generated by the nuclear fuel material during operation. The common fission gas plenum (400) 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 1/03 - 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
brevets
