A process for preparing synthetic hydrocarbons from a biomass feedstock is provided. The process involves electrolysis of steam and/or CO2, optionally along with a refinery gas in a high temperature co-electrolyzer (HTCE) to produce oxygen and hydrogen and/or enhanced hydrogen rich syngas. The oxygen generated via the electrolysis process is used for partial oxidation of a biomass feedstock in a gasifier to generate a hydrogen lean syngas. The hydrogen lean syngas is mixed with at least a portion of the hydrogen and/or enhanced hydrogen rich syngas generated via the high temperature electrolysis/co-electrolysis to formulate a hydrogen rich syngas. The hydrogen rich syngas is then reacted in a Fischer Tropsch (FT) reactor to produce synthetic hydrocarbons and refinery gas.
A process for preparing synthetic hydrocarbons from a biomass feedstock is provided. The process involves electrolysis of steam and/or CO2, optionally along with a refinery gas in a high temperature co-electrolyzer (HTCE) to produce oxygen and hydrogen and/or enhanced hydrogen rich syngas. The oxygen generated via the electrolysis process is used for partial oxidation of a biomass feedstock in a gasifier to generate a hydrogen lean syngas. The hydrogen lean syngas is mixed with at least a portion of the hydrogen and/or enhanced hydrogen rich syngas generated via the high temperature electrolysis/co-electrolysis to formulate a hydrogen rich syngas. The hydrogen rich syngas is then reacted in a Fischer Tropsch (FT) reactor to produce synthetic hydrocarbons and refinery gas.
The present invention relates to filters used to remove debris from water being sucked into a piping system. It has particular application use in nuclear power plants, which, after a loss of coolant accident, must pump cooling water back into the reactor core from a collection sump. This water may contain various types of debris that must be removed before the water is sent back into the reactor cooling system. There are restrictions on the allowable pressure drop across the strainer and the space available for installing this equipment. The finned strainer of the present invention addresses these issues while maximizing the quantity of debris filtered from the water.
B01D 29/33 - Eléments filtrants autoportants agencés pour la filtration à courant dirigé vers l'intérieur
B01D 29/39 - Filtres à éléments filtrants stationnaires pendant la filtration, p.ex. filtres à aspiration ou à pression, non couverts par les groupes ; Leurs éléments filtrants à disques creux disposés côte à côte autour de, ou sur, un ou plusieurs tubes, p.ex. du type à panneau filtrant
The invention relates to isotope separation methods, and methods for separating isotopes with low energy consumption, demonstrated using hydrogen isotopes. Also described are methods for enriching or depleting the isotope present in the hydrogen gas/vapour feed e.g. for tritium removal, tritium enrichment and deuterium enrichment, by arranging a series of cells in a cascaded configuration.
B01D 53/32 - SÉPARATION Épuration chimique ou biologique des gaz résiduaires, p.ex. gaz d'échappement des moteurs à combustion, fumées, vapeurs, gaz de combustion ou aérosols par effets électriques autres que ceux prévus au groupe
B01D 59/38 - Séparation par méthodes électrochimiques
B01D 59/40 - Séparation par méthodes électrochimiques par électrolyse
B01D 59/50 - Séparation impliquant plusieurs des procédés couverts par les différents groupes suivants: , , , , , , , ,
B01D 59/42 - Séparation par méthodes électrochimiques par électrophorèse
B01D 59/30 - Séparation par échange chimique par échange d'ions
C25B 9/23 - Cellules comprenant des électrodes fixes de dimensions stables; Assemblages de leurs éléments de structure avec des diaphragmes comprenant des membranes échangeuses d'ions dans ou sur lesquelles est incrusté du matériau pour électrode
C25B 9/70 - Assemblages comprenant plusieurs cellules
C25B 15/08 - Alimentation ou vidange des réactifs ou des électrolytes; Régénération des électrolytes
It is common to store decayed radioactive waste in waste packages, lowered into vertical concrete cylindrical storage containers called tile holes. These containers of these packages decay over time and may become fragile, making it difficult to remove them using conventional methods. A retrieval tool has been developed, comprising a cylinder that fits between the tile hole internal diameter and the outside diameter of the waste package inside the tile hole. Inflatable air wedges are equally spaced inside the cylinder. The air wedges are inflated to a low pressure (2.1 psig) to provide uniform grip to the outside of the packages, minimizing the risk of damage to the decayed containers. A back-up system uses horizontal safety bars at the bottom of the cylinder, which may be rotated to form a partial platform under the waste package, preventing the package from falling in the event of a failure.
G21F 5/14 - Dispositifs spécialement adaptés à la manipulation de récipients ou de barils, p.ex. dispositifs de transport
B66C 1/46 - Organes de saisie engageant uniquement les faces externes ou internes des objets et leur appliquant des forces de friction par gonflement de certains de leurs éléments
6.
Nuclear fuel containing recycled and depleted uranium, and nuclear fuel bundle and nuclear reactor comprising same
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 3/328 - Disposition relative des éléments dans le réseau
A cross-over fluid coupling includes a first coupling end and a second coupling end. A plurality of first conduits have inner ends disposed toward the first coupling end and outer ends spaced apart from the inner end toward the second coupling end and being outboard of the inner end. A plurality of second conduits have outer ends that are disposed toward the first coupling end and positioned laterally outboard of the inner end of at least one of the first conduits, and inner ends that are spaced apart from the outer end toward the second coupling end in the axial direction and is laterally inboard of the outer end of the at least one of the first conduits.
F16L 39/00 - Raccords ou accessoires de raccordement pour tuyaux à double paroi ou à canaux multiples ou pour assemblages de tuyaux
F16L 9/19 - Tuyaux à canaux multiples ou assemblages de tuyaux
F28F 9/26 - Dispositions pour raccorder des sections différentes des éléments d'échangeurs de chaleur, p.ex. de radiateur
F28D 7/10 - Appareils échangeurs de chaleur comportant des ensembles de canalisations tubulaires fixes pour les deux sources de potentiel calorifique, ces sources étant en contact chacune avec un côté de la paroi d'une canalisation les canalisations étant disposées l'une dans l'autre, p.ex. concentriquement
F28F 13/06 - Dispositions pour modifier le transfert de chaleur, p.ex. accroissement, diminution en affectant le mode d'écoulement des sources de potentiel calorifique
G21C 3/322 - Moyens pour influencer l'écoulement du réfrigérant à travers ou autour des faisceaux
G21C 15/02 - Aménagement ou disposition de passages dans lesquels la chaleur est transférée au réfrigérant, p.ex. pour la circulation du réfrigérant à travers les supports des éléments combustibles
G21C 3/328 - Disposition relative des éléments dans le réseau
G21C 1/20 - 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 le réfrigérant étant pressurisé le modérateur étant liquide, p.ex. réacteur à tubes de force
G21C 21/00 - Appareillage ou procédés spécialement adaptés pour la fabrication des réacteurs ou de pièces de ceux-ci
A portable detection apparatus includes a fluid inlet to acquire a stream of fluid, a fluid outlet and a fluid flowpath therebetween. A pump circulates the fluid through the fluid flowpath. A gamma spectrometer and a mercury analyzer engage the fluid flowpath to analyze and detect radiation emitted by the fluid. A filter trap is in the fluid flowpath downstream from the gamma spectrometer and the mercury analyzer. The filter trap includes a valve assembly and at least a first and second filter for collecting gaseous constituents from the fluid. Each filter is removably connected to the first valve assembly. The valve assembly has a first configuration, in which the first filter is fluidly connected to the fluid flowpath and the second filter is fluidly isolated from the fluid flowpath, and a second configuration, in which the second filter is fluidly connected to the fluid flowpath and the first filter is fluidly isolated from the fluid flowpath.
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
G01N 23/207 - Diffractométrie, p.ex. en utilisant une sonde en position centrale et un ou plusieurs détecteurs déplaçables en positions circonférentielles
9.
Test apparatus and instrumented conduit for use with same
A conduit can include a sidewall and at least a first cavity can be disposed in the sidewall. The first cavity may include a first base surface portion and an opposing first cover surface portion disposed radially between the first base surface portion and the first inner surface so that a first portion of the sidewall is provided radially between the first cover surface portion and the inner surface. A first aperture may be in communication with the first cavity and may be axially spaced apart from the first cover surface portion. A first sensor may have a transducer portion insertable through the first aperture and positioned within the first cavity. The transducer portion may be disposed radially between the first base surface portion and the first cover surface portion and being axially spaced apart from the first aperture.
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
G01K 1/143 - Supports; Dispositifs de fixation; Dispositions pour le montage de thermomètres en des endroits particuliers pour la mesure de la température de surfaces
G01K 13/02 - Thermomètres spécialement adaptés à des fins spécifiques pour mesurer la température de fluides en mouvement ou de matériaux granulaires capables de s'écouler
G01K 7/04 - Mesure de la température basée sur l'utilisation d'éléments électriques ou magnétiques directement sensibles à la chaleur utilisant des éléments thermo-électriques, p.ex. des thermocouples l'objet à mesurer ne formant pas l'un des matériaux thermo-électriques
10.
Nuclear fuel bundle containing thorium and nuclear reactor comprising same
Fuel bundles for a nuclear reactor are disclosed, and in some embodiments include a first fuel element including thorium dioxide; a second fuel element including uranium having a first fissile content; and a third fuel element including uranium having a second fissile content different from the first fissile content. Nuclear reactors using such fuel bundles are also disclosed, including pressurized heavy water nuclear reactors. The uranium having the different fissile contents can include combinations of natural uranium, depleted uranium, recycled uranium, slightly enriched uranium, and low enriched uranium.
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 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 3/328 - Disposition relative des éléments dans le réseau
A channel type heterogeneous reactor core for a heavy water reactor for burnup of thorium based fuel is provided. The heterogeneous reactor core comprises at least one seed fuel channel region comprising seed fuel channels for receiving seed fuel bundles of thorium based fuel; and at least one blanket fuel channel region comprising blanket fuel channels for receiving blanket fuel bundles of thorium based fuel; wherein the seed fuel bundles have a higher percentage content of fissile fuel than the blanket fuel bundles. The seed fuel channel region and the blanket fuel channel region may be set out in a checkerboard pattern or an annular pattern within the heterogeneous reactor core. Fuel bundles for the core are also provided.
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 7/26 - Commande de la réaction nucléaire par déplacement du modérateur ou de parties de celui-ci
G21C 5/20 - Structure du modérateur ou du cœur; Emploi de matériaux spécifiés comme modérateur caractérisée par l'installation de plus d'une zone active dans laquelle une zone contient le matériau fissile et l'autre zone contient le matériau surrégénérateur
The present invention relates to filters used to remove debris from water being sucked into a piping system. It has particular application use in nuclear power plants, which, after a loss of coolant accident, must pump cooling water back into the reactor core from a collection sump. This water may contain various types of debris that must be removed before the water is sent back into the reactor cooling system. There are restrictions on the allowable pressure drop across the strainer and the space available for installing this equipment. The finned strainer of the present invention addresses these issues while maximizing the quantity of debris filtered from the water.
B01D 29/39 - Filtres à éléments filtrants stationnaires pendant la filtration, p.ex. filtres à aspiration ou à pression, non couverts par les groupes ; Leurs éléments filtrants à disques creux disposés côte à côte autour de, ou sur, un ou plusieurs tubes, p.ex. du type à panneau filtrant
B01D 29/33 - Eléments filtrants autoportants agencés pour la filtration à courant dirigé vers l'intérieur
13.
Chemical digestion methods of quantification for water and debris mixtures
With a water, particulate and fibre mixture, a method of quantifying fibre content may include providing a sample of the mixture, filtering the sample to produce a particulate and fibre mixture, burning the particulate and fibre mixture to produce a fibre sample, and dissolving the fibre sample to produce a fibre solution. The fibre solution may be analyzed to determine an elemental content of the fibre solution. The elemental content may be compared to a known elemental content to estimate the fibre content.
G01N 31/00 - Recherche ou analyse des matériaux non biologiques par l'emploi des procédés chimiques spécifiés dans les sous-groupes; Appareils spécialement adaptés à de tels procédés
G01N 5/04 - Analyse des matériaux par pesage, p.ex. pesage des fines particules séparées d'un gaz ou d'un liquide en éliminant un constituant, p.ex. par évaporation, et en pesant le reste
A system and method for non-destructive analysis of a structure. A probe acquires a transient time based reference signal and at least one test signal. The reference signal and test signals are transformed to the frequency domain. The frequency domain test signal can be normalized using the frequency domain reference signal. Parameters of interest are evaluated at each test location by iteratively determining estimated parameter values, generating an estimated frequency domain test signal using the estimated parameter values and determining the convergence between the estimated frequency domain test signal and the normalized frequency domain test signal. The parameters values are determined as the estimated parameter values resulting in a maximized convergence between the estimated signal and the normalized test signal. The parameter values can be used to visualize and model various features of the structure.
G01N 27/90 - Recherche ou analyse des matériaux par l'emploi de moyens électriques, électrochimiques ou magnétiques en recherchant des variables magnétiques pour rechercher la présence des criques en utilisant les courants de Foucault
15.
Method for annulus spacer detection in nuclear reactors
The present invention provides an apparatus for detecting and/or repositioning annulus spacers used to maintain the position of a pressure tube within a calandria tube of a nuclear reactor. The method comprises the steps of: vibrationally isolating a section of the pressure tube; vibrating the wall of said pressure tube within said isolated section; detecting vibration of the wall at a minimum of two axial positions within said isolated sections; and detecting the reduction in vibration level of the wall at one or more of said axial positions in comparison to the remaining axial positions. The apparatus comprises a tool head to be inserted into the pressure tube, the tool head comprising a first end and a second and a clamping block m each of said ends. The clamping blocks are used to vibrationally isolate a section of the pressure tube located between said ends. The apparatus also comprises piezo-actuators operable to vibrate said pressure tube; and accelerometers used for measuring vibration of said pressure tube.
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 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
F16L 7/00 - Support de tuyaux ou de câbles à l'intérieur d'autres tuyaux ou manchons, p.ex. pour permettre la pose ou le retrait de tuyaux ou de câbles sous des routes ou des voies ferrées sans devoir interrompre la circulation
A portable detection apparatus includes a fluid inlet to acquire a stream of fluid, a fluid outlet and a fluid flowpath therebetween. A pump circulates the fluid through the fluid flowpath. A gamma spectrometer and a mercury analyzer engage the fluid flowpath to analyze and detect radiation emitted by the fluid. A filter trap is in the fluid flowpath downstream from the gamma spectrometer and the mercury analyzer. The filter trap includes a valve assembly and at least a first and second filter for collecting gaseous constituents from the fluid. Each filter is removably connected to the first valve assembly. The valve assembly has a first configuration, in which the first filter is fluidly connected to the fluid flowpath and the second filter is fluidly isolated from the fluid flowpath, and a second configuration, in which the second filter is fluidly connected to the fluid flowpath and the first filter is fluidly isolated from the fluid flowpath.
G01N 35/08 - Analyse automatique non limitée à des procédés ou à des matériaux spécifiés dans un seul des groupes ; Manipulation de matériaux à cet effet en utilisant un courant d'échantillons discrets circulant dans une canalisation, p.ex. analyse à injection dans un écoulement
G01N 23/00 - Recherche ou analyse des matériaux par l'utilisation de rayonnement [ondes ou particules], p.ex. rayons X ou neutrons, non couvertes par les groupes , ou
An annulus spacer for a fuel channel assembly of a nuclear reactor, and method of manufacturing an annulus spacer. The fuel channel assembly includes a calandria tube and a pressure tube positioned at least partially within the calandria tube. The annulus spacer includes a garter spring configured to surround a portion of the pressure tube to maintain a gap between the calandria tube and the pressure tube. A girdle wire is positioned substantially within the garter spring and configured to form a loop around the pressure tube. The girdle wire includes a first segment and a second segment that overlaps the first segment to form an overlap, the overlap extending between approximately 45 degrees and approximately 135 degrees to reduce the possibility of girdle wire twisting.
G21C 3/04 - Eléments combustibles - Détails de structure
G21C 15/02 - Aménagement ou disposition de passages dans lesquels la chaleur est transférée au réfrigérant, p.ex. pour la circulation du réfrigérant à travers les supports des éléments combustibles
G21C 13/024 - Structures supportant les cuves de pression ou les enceintes de confinement
G21C 1/20 - 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 le réfrigérant étant pressurisé le modérateur étant liquide, p.ex. réacteur à tubes de force
18.
Method for preparation of alpha sources of polonium using sulfide micro-precipitation
A method for preparing alpha sources of polonium. A sample of polonium is provided in a solution. A controlled amount of sulfide and a controlled amount of a metal capable of forming an insoluble sulfide salt in the solution are introduced into the solution, in order to co-precipitate polonium from the solution. The precipitates are filtered out.
C01G 99/00 - Matière non prévue dans les autres groupes de la présente sous-classe
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
19.
Method for annulus spacer detection and repositioning in nuclear reactors
The present invention provides an apparatus for detecting and/or repositioning annulus spacers used to maintain the position of a pressure tube within a calandria tube of a nuclear reactor. The method comprises the steps of: vibrationally isolating a section of the pressure tube; vibrating the wall of said pressure tube within said isolated section; detecting vibration of the wall at a minimum of two axial positions within said isolated sections; and detecting the reduction in vibration level of the wall at one or more of said axial positions in comparison to the remaining axial positions. The apparatus comprises a tool head to be inserted into the pressure tube, the tool head comprising a first end and a second and a clamping block m each of said ends. The clamping blocks are used to vibrationally isolate a section of the pressure tube located between said ends. The apparatus also comprises piezo-actuators operable to vibrate said pressure tube; and accelerometers used for measuring vibration of said pressure tube.
F16L 7/00 - Support de tuyaux ou de câbles à l'intérieur d'autres tuyaux ou manchons, p.ex. pour permettre la pose ou le retrait de tuyaux ou de câbles sous des routes ou des voies ferrées sans devoir interrompre la circulation
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 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
20.
Sealing apparatus for mitigating emissions of hazardous gases
A sealing apparatus for mitigating emissions of a hazardous gas flowing between first and second regions. A body of the apparatus includes at least one inlet, at least one outlet spaced apart from the at least one inlet, and a channel connecting the at least one inlet and the at least one outlet in fluid communication. Treatment material housed in at least a portion of the channel is adapted to treat the hazardous gas to form a conditioned gas. In use, the hazardous gas being emitted from the first region is received at the at least one inlet, and the conditioned gas is discharged to the second region at the at least one outlet. The apparatus may be used in combination with a storage container housing radioactive or other toxic waste.
An annulus spacer for a fuel channel assembly of a nuclear reactor. The fuel channel assembly includes a calandria tube and a pressure tube positioned at least partially within the calandria tube. The annulus spacer includes a garter spring configured to surround a portion of the pressure tube to maintain a gap between the calandria tube and the pressure tube. The garter spring includes a first end and a second end. The annulus spacer also includes a connector coupled to the first end and the second end of the garter spring. The connector allows movement of the annulus spacer when the pressure tube moves relative to the calandria tube during thermal cycles of the fuel channel assembly. The annulus spacer further includes a girdle wire positioned substantially within the garter spring and configured to form a loop around the pressure tube.
G21C 3/04 - Eléments combustibles - Détails de structure
G21C 15/02 - Aménagement ou disposition de passages dans lesquels la chaleur est transférée au réfrigérant, p.ex. pour la circulation du réfrigérant à travers les supports des éléments combustibles
22.
LOW PRESSURE GASEOUS HYDROGEN-CHARGE TECHNIQUE WITH REAL TIME CONTROL
A method for hydriding a material, such as a metallic or metal alloy, using coulometric titration. The method comprises placing the material to be hydrided inside a reaction furnace; introducing a flow of a gas mixture comprising hydrogen and optionally an inert gasto a first coulometric titration cell upstream of the furnace, through the reaction furnace, and into a second coulometric titration cell downstream of said furnace; heating the upstream and downstream coulometric titration cells; applying a current of oxygen ions to the gas mixture flow of the downstream coulometric titration cell under conditions effective to convert H2 in the downstream coulometric titration cell to H2O ; and monitoring the current of oxygen, allowing the material to absorb a desired amount of H2. The reduction in the current of oxygen can be monitored in real time to quantify the amount of hydrogen absorbed.
While typically-collected diameter data contains information for detecting some garter springs, many garter springs may not be detected without processing the diameter data. Responsively, a method for processing the diameter data to detect the garter springs has been developed. In particular, the processing involves fitting of the diameter data to a shape, determining residual errors and using the residual errors to locate garter springs.
G01B 21/14 - Dispositions pour la mesure ou leurs détails, où la technique de mesure n'est pas couverte par les autres groupes de la présente sous-classe, est non spécifiée ou est non significative pour mesurer des diamètres des diamètres intérieurs
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
G21D 3/00 - Commande des installations à énergie nucléaire
G21C 1/20 - 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 le réfrigérant étant pressurisé le modérateur étant liquide, p.ex. réacteur à tubes de force
The present invention provides a polymer indentation method and tester that includes measuring the time taken by a polymeric material to recover a set portion of an initial deformation and use this duration as a material degradation indicator. The recovery time was found to be more sensitive to cable degradation than the specific compressive stillness (or indenter modulus) measured during the indentation phase, and this high sensitivity was achieved for both thermally aged and irradiated polymer.
G01N 3/42 - Recherche de la dureté ou de la dureté au rebondissement en effectuant des empreintes sous une charge permanente par des dispositifs de pénétration, p.ex. sphère, pyramide
G01N 3/40 - Recherche de la dureté ou de la dureté au rebondissement
The present application pertains to a method of detecting and locating leaks in pipes having a secondary containment vessel. More particularly, the present application pertains to a method of leak detection whereby a tracer gas is introduced into a secondary containment vessel and detected in the primary pipe to determine the location of a leak in the primary pipe.
G01M 3/22 - Examen de l'étanchéité des structures ou ouvrages vis-à-vis d'un fluide par utilisation d'un fluide ou en faisant le vide par détection de la présence du fluide à l'emplacement de la fuite en utilisant des révélateurs particuliers, p.ex. teinture, produits fluorescents, produits radioactifs pour soupapes
F17D 5/04 - Prévention, interception ou localisation des pertes au moyen d'un fluide signalisateur contenu dans une double paroi
26.
Electrolysis cell with multiple membranes for CuCl/HCI electrolysis in hydrogen production
An electrochemical cell for producing hydrogen gas and cupric chloride. The cell comprises: an anode compartment comprising an anode for disposition in an anolyte, wherein the anolyte is cuprous chloride in hydrochloric acid; a cathode compartment comprising a cathode, wherein the cathode comprises an electrocatalyst; a plurality of ion exchange membranes disposed between the anode compartment and the cathode compartment; and at least one center compartment defined by a pair of said ion exchange membranes and comprising at least one element for removal or sequestering of copper ions that cross at least one of said membranes from the anode compartment. Also described is a method for CuCl/HCl electrolysis in the production of hydrogen using the electrochemical cell.
C25B 11/04 - PROCÉDÉS ÉLECTROLYTIQUES OU ÉLECTROPHORÉTIQUES POUR LA PRODUCTION DE COMPOSÉS ORGANIQUES OU MINÉRAUX, OU DE NON-MÉTAUX; APPAREILLAGES À CET EFFET Électrodes; Leur fabrication non prévue ailleurs caractérisées par le matériau
27.
Boron-loaded liquid scintillator compositions and methods of preparation thereof
Described herein is a boron-loaded liquid scintillator composition comprising a scintillation solvent including at least one linear alkylbenzene (LAB), diisopropyl naphthalene (DIN) or phenylxylyl ethane (PXE), or a combination of one or more thereof; at least one boron-containing material; one or more fluors, such as 2,5-diphenyloxazole (PPO), and optionally one or more wavelength shifters, such as 1,4-bis[2-methylstyryl]benzene (bis-MSB). The boron-containing material may comprise a carborane, such as o-carborane, especially those enriched in Boron-10. Methods of preparation of the liquid scintillator composition are also described, as well as concentrates thereof.
A method is proposed herein to detect high atomic number materials, such as Special Nuclear Materials, within a container based on muon tomography. The container is modeled as a plurality of volume elements. Information related to an initial trajectory and a final trajectory of each muon passing through the container is received. Additionally, a set of initial outer prong vectors and a set of final outer prong vectors are created. Then, a plurality of vector combinations are created from a selected initial vector and a selected final vector. A metric is determined and associated with each vector combination. A subset of the plurality of vector combinations is associated with each volume element and an estimated scattering density is determined and assigned to the volume element. Based on the estimated scattering density assigned to the volume elements, a three dimensional image of the container may be generated.
G01T 1/00 - Mesure des rayons X, des rayons gamma, des radiations corpusculaires ou des radiations cosmiques
G01T 1/29 - Mesure effectuée sur des faisceaux de radiations, p.ex. sur la position ou la section du faisceau; Mesure de la distribution spatiale de radiations
G01N 23/083 - Recherche ou analyse des matériaux par l'utilisation de rayonnement [ondes ou particules], p.ex. rayons X ou neutrons, non couvertes par les groupes , ou en transmettant la radiation à travers le matériau et mesurant l'absorption le rayonnement consistant en rayons X
H01J 3/14 - Dispositifs pour la focalisation ou la réflexion du rayon ou du faisceau
G01V 5/00 - Prospection ou détection au moyen de radiations nucléaires, p.ex. de la radioactivité naturelle ou provoquée
G01N 23/04 - Recherche ou analyse des matériaux par l'utilisation de rayonnement [ondes ou particules], p.ex. rayons X ou neutrons, non couvertes par les groupes , ou en transmettant la radiation à travers le matériau et formant des images des matériaux
G01N 23/20 - Recherche ou analyse des matériaux par l'utilisation de rayonnement [ondes ou particules], p.ex. rayons X ou neutrons, non couvertes par les groupes , ou en utilisant la réflexion de la radiation par les matériaux
H01J 37/252 - Tubes analyseurs à spot par faisceaux électroniques ou ioniques; Micro-analyseurs
29.
METHOD FOR PREPARATION OF ALPHA SOURCES OF POLONIUM USING SULFIDE MICRO-PRECIPITATION
A method for preparing alpha sources of polonium. A sample of polonium is provided in a solution. A controlled amount of sulfide and a controlled amount of a metal capable of forming an insoluble sulfide salt in the solution are introduced into the solution, in order to co-precipitate polonium from the solution. The precipitates are filtered out.
G21G 4/04 - Sources radioactives autres que les sources de neutrons
C01G 99/00 - Matière non prévue dans les autres groupes de la présente sous-classe
G01G 1/00 - Appareils de pesée dans lesquels est utilisé un contrepoids ou toute autre masse d'équilibrage
G01G 3/12 - Appareils de pesée caractérisés par l'utilisation d'organes déformables par élasticité, p.ex. balances à ressort dans lesquels l'élément de pesée est constitué par un corps solide soumis à une pression ou une traction pendant la pesée
The invention relates to isotope separation methods, and methods for separating isotopes with low energy consumption, demonstrated using hydrogen isotopes. To this end, an isotope transfer electrochemical cell is provided, which comprises an anode plate and a cathode plate; current carrier plates with flow channels or mesh layers or porous material; a proton exchange membrane or solid polymer electrolyte membrane; and gas diffusion layers positioned on either side of the proton exchange membrane which together with the proton exchange membrane forms a membrane electrode assembly; and a housing containing the anode and cathode plates in operable arrangement with the membrane electrode assembly, and defining a hydrogen feed inlet on the anode, a product outlet on the cathode, an outlet for excess hydrogen on the anode, and internal flow paths for transfer of gases and fluids on either side of the membrane electrode assembly. Also described are methods for enriching or depleting the isotope present in the hydrogen gas/vapour feed e.g. for tritium removal, tritium enrichment and deuterium enrichment, by arranging a series of cells in a cascaded configuration.
To avoid the detrimental effects of bubbles in the carrying out of immersion ultrasonic testing, various surfaces may be coated with a coating that includes appropriately selected compounds. Such compounds may include those compounds that cause higher local surface tension and those compounds that are hydrophilic. Furthermore, various surfaces involved in the testing may be coated in a manner that minimizes cavities and crevices to which air bubbles can adhere.
The invention relates to isotope separation methods, and methods for separating isotopes with low energy consumption, demonstrated using hydrogen isotopes. To this end, an isotope transfer electrochemical cell is provided, which comprises an anode plate and a cathode plate; current carrier plates with flow channels or mesh layers or porous material; a proton exchange membrane or solid polymer electrolyte membrane; and gas diffusion layers positioned on either side of the proton exchange membrane which together with the proton exchange membrane forms a membrane electrode assembly; and a housing containing the anode and cathode plates in operable arrangement with the membrane electrode assembly, and defining a hydrogen feed inlet on the anode, a product outlet on the cathode, an outlet for excess hydrogen on the anode, and internal flow paths for transfer of gases and fluids on either side of the membrane electrode assembly. Also described are methods for enriching or depleting the isotope present in the hydrogen gas/vapour feed e.g. for tritium removal, tritium enrichment and deuterium enrichment, by arranging a series of cells in a cascaded configuration.
A portable detection apparatus can include a housing, a first detector for detecting ionizing radiation from a first subject and a second detector within the housing for the detecting the background radiation. A shield within the housing can surround the first and second detectors and define a shield aperture around the first and second detectors for radiation from the subject to enter the housing. A radiation blocking member can substantially block at least a portion of the ionizing radiation from reaching the second detector, whereby radiation detected by the second detector comprises substantially only the background radiation. A processor module can be connected to the first and second detectors for determining the amount of ionizing radiation detected by the first detector attributable to secondary radiation.
A method for preparing alpha sources of polonium. A sample of polonium is provided in a solution. A controlled amount of sulfide and a controlled amount of a metal capable of forming an insoluble sulfide salt in the solution are introduced into the solution, in order to co-precipitate polonium from the solution. The precipitates are filtered out.
G21G 4/04 - Sources radioactives autres que les sources de neutrons
G01G 1/00 - Appareils de pesée dans lesquels est utilisé un contrepoids ou toute autre masse d'équilibrage
G01G 3/12 - Appareils de pesée caractérisés par l'utilisation d'organes déformables par élasticité, p.ex. balances à ressort dans lesquels l'élément de pesée est constitué par un corps solide soumis à une pression ou une traction pendant la pesée
C01G 99/00 - Matière non prévue dans les autres groupes de la présente sous-classe
A tool may be inserted into the pressure tube inside a calandria tube of a fuel channel of a nuclear reactor. Once in position, the tool may act to generate information useful for determining a location for an annulus spacer. Once the annulus spacer has been located, the tool may act to generate information useful for determining a compressive load on the annulus spacer due to the annulus spacer being pinched between the two tubes. In both the locating and the load determining, the tool may act to isolate a section of the pressure tube, excite the isolated section of the pressure tube with vibrations and measure resultant tube vibrations. Tube vibration characteristics, determined from the vibrations, may then be analyzed to determine an axial location along the pressure tube for the annulus spacer and/or determine a load on the annulus spacer.
G01L 5/06 - Appareils ou procédés pour la mesure des forces, du travail, de la puissance mécanique ou du couple, spécialement adaptés à des fins spécifiques pour la mesure de la tension dans les éléments flexibles, p.ex. dans les cordages, les câbles, les fils métalliques, les filaments, les courroies ou les bandes en utilisant des moyens mécaniques
G01B 17/00 - Dispositions pour la mesure caractérisées par l'utilisation de vibrations infrasonores, sonores ou ultrasonores
A channel type heterogeneous reactor core for a heavy water reactor for burnup of thorium based fuel is provided. The heterogeneous reactor core comprises at least one seed fuel channel region comprising seed fuel channels for receiving seed fuel bundles of thorium based fuel; and at least one blanket fuel channel region comprising blanket fuel channels for receiving blanket fuel bundles of thorium based fuel; wherein the seed fuel bundles have a higher percentage content of fissile fuel than the blanket fuel bundles. The seed fuel channel region and the blanket fuel channel region may be set out in a checkerboard pattern or an annular pattern within the heterogeneous reactor core. Fuel bundles for the core are also provided.
G21C 5/20 - Structure du modérateur ou du cœur; Emploi de matériaux spécifiés comme modérateur caractérisée par l'installation de plus d'une zone active dans laquelle une zone contient le matériau fissile et l'autre zone contient le matériau surrégénérateur
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
A channel type heterogeneous reactor core for a heavy water reactor for burnup of thorium based fuel is provided. The heterogeneous reactor core comprises at least one seed fuel channel region comprising seed fuel channels for receiving seed fuel bundles of thorium based fuel; and at least one blanket fuel channel region comprising blanket fuel channels for receiving blanket fuel bundles of thorium based fuel; wherein the seed fuel bundles have a higher percentage content of fissible fuel than the blanket fuel bundles. The seed fuel channel region and the blanket fuel channel region may be set out in a checkerboard pattern or an annular pattern within the heterogeneous reactor core. Fuel bundles for the core are also provided.
Processes and devices useful in the application of coatings (14) to the interior of tubes (10) are described. Such processes (40, 400) may include applying a layer (20) of coating fluid (18) to the internal surface (16) of the tube (10) and passing a smoothing member (22) through the tube (10) at a distance from the internal surface (16). The viscosity of the coating fluid (18) may be selected so that the layer (20) of coating fluid (18) has a thickness substantially equal to or in excess of a predetermined wet film thickness (Twf) correlated to a desired final thickness (Tf) of the coating (14). The distance between the smoothing member (22) and the internal surface (16) may substantially correspond to the predetermined wet film thickness (Twf). The smoothing member (22) may smooth the coating fluid (18) and remove coating fluid (18) in excess of the wet film thickness (Twf) from the internal surface (16).
B05D 7/22 - Procédés, autres que le flocage, spécialement adaptés pour appliquer des liquides ou d'autres matériaux fluides, à des surfaces particulières, ou pour appliquer des liquides ou d'autres matériaux fluides particuliers à des surfaces internes, p.ex. à l'intérieur de tubes
B05C 7/08 - Appareillages spécialement agencés pour appliquer un liquide ou autre matériau fluide à l'intérieur d'une pièce creuse par des dispositifs se déplaçant en restant en contact avec l'ouvrage pour appliquer des liquides ou d'autres matériaux fluides aux surfaces intérieures de tubes
F16L 58/14 - Revêtements caractérisés par les matériaux utilisés de matériaux céramiques ou vitreux
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
B05C 3/18 - Appareillages dans lesquels un ouvrage est mis en contact avec une grande quantité de liquide ou autre matériau fluide un côté uniquement de l'ouvrage venant en contact avec le liquide ou autre matériau fluide
B05C 11/02 - Appareils pour étaler ou répartir des liquides ou d'autres matériaux fluides déjà appliqués sur une surface; Réglage de l'épaisseur du revêtement
B05D 1/40 - Distribution des liquides ou d'autres matériaux fluides, appliqués par des éléments se déplaçant par rapport à la surface à couvrir
B05D 1/42 - Distribution des liquides ou d'autres matériaux fluides, appliqués par des éléments se déplaçant par rapport à la surface à couvrir par des éléments non rotatifs
39.
Profiling tool for determining material thickness for inspection sites having complex topography
A phased array ultrasonic probe may be mounted to a component to be inspected for wall thickness on an apparatus that includes a split ring adapted to be magnetically held in place on the component. In particular, the probe may be mounted to a carriage connected to the split ring in a manner that allows the carriage to rotate around the split ring while the probe is in operation. Between the probe and the component, a transducer shoe defining, by a flexible membrane, a cavity and an aperture. Conveniently, the construction of the flexible membrane allows wall thickness measurements to be acquired in portions of the component that have complex topography, such as welds. The apparatus is installed on an adaptor assembly for inspection of straight section of pipes. This adaptor assembly is not used in absence of straight section. By acquiring data from multiple output pulse transmitted at multiple incidence angles, processing software may conveniently produce an accurate wall thickness map of the area of interest on the component.
G01N 29/26 - Dispositions pour l'orientation ou le balayage
G01B 17/02 - Dispositions pour la mesure caractérisées par l'utilisation de vibrations infrasonores, sonores ou ultrasonores pour mesurer l'épaisseur
G21C 17/017 - Inspection ou maintenance de tuyaux ou de tubes dans des installations nucléaires
G01N 29/22 - Recherche ou analyse des matériaux par l'emploi d'ondes ultrasonores, sonores ou infrasonores; Visualisation de l'intérieur d'objets par transmission d'ondes ultrasonores ou sonores à travers l'objet - Détails
235U, and wherein at least one of the fuel elements is a poisoned low-enriched uranium fuel element including a neutron poison in a concentration greater than about 5.0 vol %.
G21C 19/00 - Dispositions pour le traitement, pour la manipulation, ou pour faciliter la manipulation, du combustible ou d'autres matériaux utilisés à l'intérieur du réacteur, p.ex. à l'intérieur de l'enceinte sous pression
G21C 3/326 - Faisceaux d'éléments combustibles en forme d'aiguilles, de barres ou de tubes parallèles comprenant, en plus des éléments combustibles, d'autres éléments en forme d'aiguille, de barre ou de tube, p.ex. barres de commande, barres de support de grilles, barres fertiles, barres à poison ou barres factices
G21C 19/20 - 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 controller for producing a nuclear reactor shutdown system trip signal in response to at least one detector signal. The controller includes a signal conditioning module receiving the at least one detector signal and outputting a measured flux signal. A rate module generates a rate signal from the measured flux signal. A comparator circuit compares the rate signal to a trip setpoint and generates a first trip signal.
A controller for producing a nuclear reactor shutdown system trip signal in response to at least one detector signal. The controller includes a signal conditioning module receiving the at least one detector signal and outputting a measured flux signal. A rate module generates a rate signal from the measured flux signal. A comparator circuit compares the rate signal to a trip setpoint and generates a first trip signal.
G21C 3/42 - Emploi de substances spécifiées comme combustibles pour réacteurs
G21C 1/20 - 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 le réfrigérant étant pressurisé le modérateur étant liquide, p.ex. réacteur à tubes de force
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
It is common to store decayed radioactive waste in waste packages, lowered into vertical concrete cylindrical storage containers called tile holes. These containers of these packages decay over time and may become fragile, making it difficult to remove them using conventional methods. A retrieval tool has been developed, comprising a cylinder that fits between the tile hole internal diameter and the outside diameter of the waste package inside the tile hole. Inflatable air wedges are equally spaced inside the cylinder. The air wedges are inflated to a low pressure (2.1 psig) to provide uniform grip to the outside of the packages, minimizing the risk of damage to the decayed containers. A back-up system uses horizontal safety bars at the bottom of the cylinder, which may be rotated to form a partial platform under the waste package, preventing the package from falling in the event of a failure.
B66C 1/22 - Organes rigides, p.ex. en forme d'équerre, dont une partie s'engage sous la charge; Crochets de grues
B66C 1/46 - Organes de saisie engageant uniquement les faces externes ou internes des objets et leur appliquant des forces de friction par gonflement de certains de leurs éléments
B66C 1/62 - Eléments ou dispositifs de prise de la charge adjoints aux mécanismes de levage, de descente ou de halage, ou adaptés pour être utilisés avec ces mécanismes et transmettant les efforts à des articles ou à des groupes d'articles par moyens mécaniques comportant des organes de saisie ayant une forme complémentaire de celle des objets à manipuler
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
G21F 5/14 - Dispositifs spécialement adaptés à la manipulation de récipients ou de barils, p.ex. dispositifs de transport
While the typically-collected diameter data contains information for detecting some garter springs, many garter springs may not be detected without processing the diameter data. Responsively, a method for processing the diameter data to detect the garter springs has been developed. In particular, the processing involves fitting of the diameter data to a shape, determining residual errors and using the residual errors to locate garter springs.
G21C 13/02 - Enceintes sous pression; Enceintes d'enveloppe; Enveloppes en général - Détails
G01B 21/20 - Dispositions pour la mesure ou leurs détails, où la technique de mesure n'est pas couverte par les autres groupes de la présente sous-classe, est non spécifiée ou est non significative pour mesurer des contours ou des courbes, p.ex. pour déterminer un profil
The present application pertains to a method of detecting and locating leaks in pipes having a secondary containment vessel. More particularly, the present application pertains to a method of leak detection whereby a tracer gas is introduced into the secondary containment vessel and detected in the primary pipe to determine the location of a leak in a primary pipe.
G01M 3/22 - Examen de l'étanchéité des structures ou ouvrages vis-à-vis d'un fluide par utilisation d'un fluide ou en faisant le vide par détection de la présence du fluide à l'emplacement de la fuite en utilisant des révélateurs particuliers, p.ex. teinture, produits fluorescents, produits radioactifs pour soupapes
F17D 5/04 - Prévention, interception ou localisation des pertes au moyen d'un fluide signalisateur contenu dans une double paroi
47.
ELECTROLYSIS CELL WITH MULTIPLE MEMBRANES FOR CUCL/HCL ELECTROLYSIS IN HYDROGEN PRODUCTION
An electrochemical cell for producing hydrogen gas and cupric chloride. The cell comprises: an anode compartment comprising an anode for disposition in an anolyte, wherein the anolyte is cuprous chloride in hydrochloric acid; a cathode compartment comprising a cathode, wherein the cathode comprises an electrocatalyst; a plurality of ion exchange membranes disposed between the anode compartment and the cathode compartment; and at least one center compartment defined by a pair of said ion exchange membranes and comprising at least one element for removal or sequestering of copper ions that cross at least one of said membranes from the anode compartment. Also described is a method for CuC1/HC1 electrolysis in the production of hydrogen using the electrochemical cell.
C25B 9/21 - Cellules comprenant des électrodes fixes de dimensions stables; Assemblages de leurs éléments de structure avec des diaphragmes avec plusieurs diaphragmes
C25B 1/04 - Hydrogène ou oxygène par électrolyse de l'eau
The present application pertains to a method of detecting and locating leaks in pipes having a secondary containment vessel. More particularly, the present application pertains to a method of leak detection whereby a tracer gas is introduced into the secondary containment vessel and detected in the primary pipe to determine the location of a leak in a primary pipe.
G01M 3/22 - Examen de l'étanchéité des structures ou ouvrages vis-à-vis d'un fluide par utilisation d'un fluide ou en faisant le vide par détection de la présence du fluide à l'emplacement de la fuite en utilisant des révélateurs particuliers, p.ex. teinture, produits fluorescents, produits radioactifs pour soupapes
F17D 5/04 - Prévention, interception ou localisation des pertes au moyen d'un fluide signalisateur contenu dans une double paroi
While the typically-collected diameter data contains information for detecting some garter springs, many garter springs may not be detected without processing the diameter data. Responsively, a method for processing the diameter data to detect the garter springs has been developed. In particular, the processing involves fitting of the diameter data to a shape, determining residual errors and using the residual errors to locate garter springs.
G01B 21/20 - Dispositions pour la mesure ou leurs détails, où la technique de mesure n'est pas couverte par les autres groupes de la présente sous-classe, est non spécifiée ou est non significative pour mesurer des contours ou des courbes, p.ex. pour déterminer un profil
G21C 13/02 - Enceintes sous pression; Enceintes d'enveloppe; Enveloppes en général - Détails
It is common to store decayed radioactive waste in waste packages, lowered into vertical concrete cylindrical storage containers called tile holes. These containers of these packages decay over time and may become fragile, making it difficult to remove them using conventional methods. A retrieval tool has been developed, comprising a cylinder that fits between the tile hole internal diameter and the outside diameter of the waste package inside the tile hole. Inflatable air wedges are equally spaced inside the cylinder. The air wedges are inflated to a low pressure (2.1 psig) to provide uniform grip to the outside of the packages, minimizing the risk of damage to the decayed containers. A back-up system uses horizontal safety bars at the bottom of the cylinder, which may be rotated to form a partial platform under the waste package, preventing the package from falling in the event of a failure.
B66C 1/22 - Organes rigides, p.ex. en forme d'équerre, dont une partie s'engage sous la charge; Crochets de grues
B66C 1/46 - Organes de saisie engageant uniquement les faces externes ou internes des objets et leur appliquant des forces de friction par gonflement de certains de leurs éléments
B66C 1/62 - Eléments ou dispositifs de prise de la charge adjoints aux mécanismes de levage, de descente ou de halage, ou adaptés pour être utilisés avec ces mécanismes et transmettant les efforts à des articles ou à des groupes d'articles par moyens mécaniques comportant des organes de saisie ayant une forme complémentaire de celle des objets à manipuler
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
G21F 5/14 - Dispositifs spécialement adaptés à la manipulation de récipients ou de barils, p.ex. dispositifs de transport
51.
ELECTROLYSIS CELL WITH MULTIPLE MEMBRANES FOR CUCI/HCI ELECTROLYSIS IN HYDROGEN PRODUCTION
An electrochemical cell for producing hydrogen gas and cupric chloride. The cell comprises: an anode compartment comprising an anode for disposition in an anolyte, wherein the anolyte is cuprous chloride in hydrochloric acid; a cathode compartment comprising a cathode, wherein the cathode comprises an electrocatalyst; a plurality of ion exchange membranes disposed between the anode compartment and the cathode compartment; and at least one center compartment defined by a pair of said ion exchange membranes and comprising at least one element for removal or sequestering of copper ions that cross at least one of said membranes from the anode compartment. Also described is a method for CuC1/HC1 electrolysis in the production of hydrogen using the electrochemical cell.
It is common to store decayed radioactive waste in waste packages, lowered into vertical concrete cylindrical storage containers called tile holes. These containers of these packages have decayed over time and are fragile, making it difficult to remove them using conventional methods. A retrieval tool has been developed, comprising a cylinder that fits between the tile hole internal diameter and the outside diameter of the waste package inside the tile hole. Six inflatable air wedges are equally spaced inside the cylinder. The air wedges are inflated to a low pressure (2.1 psig) to provide uniform grip to the outside of the packages, minimizing the risk of damage to the decayed containers. A back-up system uses six horizontal safety bars at the bottom of the cylinder, which may be rotated to form a partial platform under the waste package, preventing the package from falling in the event of a failure. Other aspects of the retrieval system are also described.
B66C 1/22 - Organes rigides, p.ex. en forme d'équerre, dont une partie s'engage sous la charge; Crochets de grues
B66C 1/46 - Organes de saisie engageant uniquement les faces externes ou internes des objets et leur appliquant des forces de friction par gonflement de certains de leurs éléments
B66C 1/62 - Eléments ou dispositifs de prise de la charge adjoints aux mécanismes de levage, de descente ou de halage, ou adaptés pour être utilisés avec ces mécanismes et transmettant les efforts à des articles ou à des groupes d'articles par moyens mécaniques comportant des organes de saisie ayant une forme complémentaire de celle des objets à manipuler
G21F 5/14 - Dispositifs spécialement adaptés à la manipulation de récipients ou de barils, p.ex. dispositifs de transport
53.
BORON-LOADED LIQUID SCINTILLATOR COMPOSITIONS AND METHODS OF PREPARATION THEREOF
Described herein is a boron-loaded liquid scintillator composition comprising a scintillation solvent including at least one linear alkylbenzene (LAB), diisopropyl naphthalene (DIN) or phenylxylyl ethane (PXE), or a combination of one or more thereof; at least one boron-containing material; one or more fluors, such as 2,5- diphenyloxazole (PPO), and optionally one or more wavelength shifters, such as 1,4-bis[2-methylstyryl]benzene (bis-MSB). The boron-containing material may comprise a carborane, such as o-carborane, especially those enriched in Boron- 10. Methods of preparation of the liquid scintillator composition are also described, as well as concentrates thereof.
Described herein is a boron-loaded liquid scintillator composition comprising a scintillation solvent including at least one linear alkylbenzene (LAB), diisopropyl naphthalene (DIN) or phenylxylyl ethane (PXE), or a combination of one or more thereof; at least one boron-containing material; one or more fluors, such as 2.5-diphenyloxazole (PPO), and optionally one or more wavelength shifters, such as 1,4-bis[2-methylstyryl]benzene (bis-MSB). The boron-containing material may comprise a carborane, such as o-carborane, especially those enriched in Boron-10. Methods of preparation of the liquid scintillator composition are also described, as well as concentrates thereof.
The present invention provides a radiation detector for detecting both the intensity and direction of one or more sources of radiation comprising a radiation sensor, an inverse collimator that shields the sensor from at least a portion of the incident radiation originating from the direction in which the inverse collimator is pointed and a means for pointing the inverse collimator in different directions. In accordance with another aspect of the invention, there is provided a method for detecting both the intensity and direction of one or more sources of radiation comprising the steps of providing a radiation sensor, providing an inverse collimator that shields the sensor from at least a portion of the incident radiation originating from the direction in which the inverse collimator is pointed, providing a means for pointing the inverse collimator in different directions, pointing the inverse collimator in a direction, recording the direction in which the inverse collimator is pointed and recording the signal from the sensor, repeating the preceding two steps one or more times for one or more different directions.
G21K 1/02 - Dispositions pour manipuler des particules ou des rayonnements ionisants, p.ex. pour focaliser ou pour modérer utilisant des diaphragmes, des collimateurs
Fuel bundles for a nuclear reactor are disclosed, and in some embodiments include a first fuel element including thorium dioxide; a second fuel element including uranium having a first fissile content; and a third fuel element including uranium having a second fissile content different from the first fissile content. Nuclear reactors using such fuel bundles are also disclosed, including pressurized heavy water nuclear reactors. The uranium having the different fissile contents can include combinations of natural uranium, depleted uranium, recycled uranium, slightly enriched uranium, and low enriched uranium.
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 3/328 - Disposition relative des éléments dans le réseau
The present invention relates to a spacer for maintaining a distance between a pressure tube and a calandria tube in a nuclear reactor, and more specifically, to a spacer which is secured in position between the pressure tube and calandria tube. The axial position of the spacer is maintained by having a spacer with an outer profile that is in close fit or a slight interference fit with a locally expanded profile of the calandria tube. A spacer, a corresponding calandria tube, and a method for installing such a spacer are described.
G21C 13/02 - Enceintes sous pression; Enceintes d'enveloppe; Enveloppes en général - Détails
G21C 13/00 - Enceintes sous pression; Enceintes d'enveloppe; Enveloppes en général
G21C 19/20 - Dispositions pour introduire des objets à l'intérieur de l'enceinte sous pression; Dispositions pour manipuler des objets à l'intérieur de l'enceinte sous pression; Dispositions pour extraire des objets de l'enceinte sous pression
The present invention relates to a spacer for maintaining a distance between a pressure tube and a calandria tube in a nuclear reactor, and more specifically, to a spacer which is secured in position between the pressure tube and calandria tube. The axial position of the spacer is maintained by having a spacer with an outer profile that is in close fit or a slight interference fit with a locally expanded profile of the calandria tube. A spacer, a corresponding calandria tube, and a method for installing such a spacer are described.
G21C 13/02 - Enceintes sous pression; Enceintes d'enveloppe; Enveloppes en général - Détails
G21C 13/00 - Enceintes sous pression; Enceintes d'enveloppe; Enveloppes en général
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 controller for producing a nuclear reactor shutdown system trip signal in response to at least one detector signal. The controller includes a signal conditioning module receiving the at least one detector signal and outputting a measured flux signal. A rate module generates a rate signal from the measured flux signal. A comparator circuit compares the rate signal to a trip setpoint and generates a first trip signal.
A nuclear reactor can include a pressure vessel for containing a pressurized moderator at a first pressure. The nuclear reactor can also include a plurality of fuel channels for a coolant fluid at a second pressure. The plurality of fuel channels are fluidly connected at inlet ends thereof to a coolant supply conduit and are adapted to receive nuclear fuel bundles and to be mounted within the pressure vessel and surrounded by the moderator. The outlet ends of the fuel channels are fluidly connected to a coolant outlet conduit to enable the coolant fluid to circulate from the coolant supply conduit through the fuel channels to the coolant outlet conduit. The plurality of fuel channels maintain separation between the coolant fluid circulating within the fuel channels and the moderator.
G21C 1/08 - Réacteurs hétérogènes, c. à d. dans lesquels le combustible et le modérateur sont séparés le modérateur étant hautement pressurisé, p.ex. réacteur à eau bouillante, réacteur à surchauffe intégrale, réacteur à eau pressurisée
G21C 5/02 - Structure du modérateur ou du cœur; Emploi de matériaux spécifiés comme modérateur - Détails
G21C 19/19 - Parties de réacteurs spécifiquement adaptées pour faciliter la manipulation, p.ex. pour faciliter le chargement ou le déchargement des éléments combustibles
G21C 1/10 - Réacteurs hétérogènes, c. à d. dans lesquels le combustible et le modérateur sont séparés le modérateur étant hautement pressurisé, p.ex. réacteur à eau bouillante, réacteur à surchauffe intégrale, réacteur à eau pressurisée le modérateur et le réfrigérant étant différents ou séparés
G21C 15/02 - Aménagement ou disposition de passages dans lesquels la chaleur est transférée au réfrigérant, p.ex. pour la circulation du réfrigérant à travers les supports des éléments combustibles
61.
Apparatus and method for detecting position of annulus spacer between concentric tubes
An apparatus for detecting the location of at least one annulus spacer between concentric interior and exterior tubes when a temperature gradient is present therebetween. A probe head assembly is movable within the interior tube. At least one temperature sensor is coupled to the probe head assembly and configured to detect a temperature of an interior surface of the interior tube. A drive assembly is operable to move the probe head assembly relative to the interior tube. A data acquisition system is coupled to the at least one temperature sensor and configured to receive a plurality of temperature measurements in order to identify at least one position along the interior surface having a temperature abnormality corresponding to a reduced temperature gradient.
G01N 25/00 - Recherche ou analyse des matériaux par l'utilisation de moyens thermiques
G01J 5/00 - Pyrométrie des radiations, p.ex. thermométrie infrarouge ou optique
G01K 1/00 - MÉTROLOGIE; TESTS ÉLÉMENTS THERMOSENSIBLES NON PRÉVUS AILLEURS - Détails des thermomètres non spécialement adaptés à des types particuliers de thermomètres
G01K 3/00 - Thermomètres donnant une indication autre que la valeur instantanée de la température
G01K 13/00 - Thermomètres spécialement adaptés à des fins spécifiques
G21C 17/017 - Inspection ou maintenance de tuyaux ou de tubes dans des installations nucléaires
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
62.
APPARATUS AND METHOD FOR DETECTING POSITION OF ANNULUS SPACER BETWEEN CONCENTRIC TUBES
An apparatus for detecting the location of at least one annulus spacer between concentric interior and exterior tubes when a temperature gradient is present therebetween. A probe head assembly is movable within the interior tube. At least one temperature sensor is coupled to the probe head assembly and configured to detect a temperature of an interior surface of the interior tube. A drive assembly is operable to move the probe head assembly relative to the interior tube. A data acquisition system is coupled to the at least one temperature sensor and configured to receive a plurality of temperature measurements in order to identify at least one position along the interior surface having a temperature abnormality corresponding to a reduced temperature gradient.
G01B 21/00 - Dispositions pour la mesure ou leurs détails, où la technique de mesure n'est pas couverte par les autres groupes de la présente sous-classe, est non spécifiée ou est non significative
A pressure-tube nuclear reactor can include an outer shell having an interior to contain a moderator at a first pressure and a coolant plenum to receive the coolant fluid at a second pressure, the second pressure being greater than the first pressure. The reactor also includes a plurality of pressure tubes. Each pressure tube is received within and extends through a corresponding shell tube and is configured to releasably retain at least one fuel bundle. A first end of each pressure tube being coupled to the plenum tubesheet in fluid communication with the plenum chamber and a second end of each pressure tube fluidly connected to a coolant conduit to enable the coolant fluid to flow between the coolant plenum and each pressure tube and to flow from the nuclear reactor for further processing.
G21C 15/00 - Dispositions pour le refroidissement à l'intérieur de l'enceinte sous pression contenant le cœur; Emploi de réfrigérants spécifiques
G21C 1/10 - Réacteurs hétérogènes, c. à d. dans lesquels le combustible et le modérateur sont séparés le modérateur étant hautement pressurisé, p.ex. réacteur à eau bouillante, réacteur à surchauffe intégrale, réacteur à eau pressurisée le modérateur et le réfrigérant étant différents ou séparés
G21C 1/20 - 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 le réfrigérant étant pressurisé le modérateur étant liquide, p.ex. réacteur à tubes de force
G21C 13/04 - Dispositions pour l'expansion et la contraction
G21C 15/02 - Aménagement ou disposition de passages dans lesquels la chaleur est transférée au réfrigérant, p.ex. pour la circulation du réfrigérant à travers les supports des éléments combustibles
G21C 15/20 - Compartiments ou isolement thermique entre le canal d'enfournement et le modérateur, p.ex. dans des réacteurs à tubes de force
64.
DETECTING HIGH ATOMIC NUMBER MATERIALS WITH COSMIC RAY MUON TOMOGRAPHY
A method is proposed herein to detect high atomic number materials, such as Special Nuclear Materials, within a container based on muon tomography. The container is modeled as a plurality of volume elements. Information related to an initial trajectory and a final trajectory of each muon passing through the container is received. Additionally, a set of initial outer prong vectors and a set of final outer prong vectors are created. Then, a plurality of vector combinations are created from a selected initial vector and a selected final vector. A metric is determined and associated with each vector combination. A subset of the plurality of vector combinations is associated with each volume element and an estimated scattering density is determined and assigned to the volume element. Based on the estimated scattering density assigned to the volume elements, a three dimensional image of the container may be generated.
G01N 23/04 - Recherche ou analyse des matériaux par l'utilisation de rayonnement [ondes ou particules], p.ex. rayons X ou neutrons, non couvertes par les groupes , ou en transmettant la radiation à travers le matériau et formant des images des matériaux
G21H 7/00 - Utilisation des effets des rayonnements cosmiques
65.
DETECTING HIGH ATOMIC NUMBER MATERIALS WITH COSMIC RAY MUON TOMOGRAPHY
A method is proposed herein to detect high atomic number materials, such as Special Nuclear Materials, within a container based on muon tomography. The container is modeled as a plurality of volume elements. Information related to an initial trajectory and a final trajectory of each muon passing through the container is received. Additionally, a set of initial outer prong vectors and a set of final outer prong vectors are created. Then, a plurality of vector combinations are created from a selected initial vector and a selected final vector. A metric is determined and associated with each vector combination. A subset of the plurality of vector combinations is associated with each volume element and an estimated scattering density is determined and assigned to the volume element. Based on the estimated scattering density assigned to the volume elements, a three dimensional image of the container may be generated.
G01N 23/04 - Recherche ou analyse des matériaux par l'utilisation de rayonnement [ondes ou particules], p.ex. rayons X ou neutrons, non couvertes par les groupes , ou en transmettant la radiation à travers le matériau et formant des images des matériaux
G01N 23/20 - Recherche ou analyse des matériaux par l'utilisation de rayonnement [ondes ou particules], p.ex. rayons X ou neutrons, non couvertes par les groupes , ou en utilisant la réflexion de la radiation par les matériaux
The present invention relates to filters used to remove debris from water being sucked into a piping system. It has particular application for use in nuclear power plants, which, after a loss of coolant accident, must pump cooling water back into the reactor core from a collection sump. This water may contain various types of debris that must be removed before the water is sent back into the reactor cooling system. Filtering of the debris is realized with the component known as “strainers”. There are restrictions on the space available for installing strainers. The vaned filtering element, for example a vaned fin, of the present invention is designed to reduce the space required for strainer installation by increasing strainer surface area per unit volume, while maximizing the quantity of debris that can be filtered from the water.
B01D 29/07 - Filtres à éléments filtrants stationnaires pendant la filtration, p.ex. filtres à aspiration ou à pression, non couverts par les groupes ; Leurs éléments filtrants avec des éléments filtrants plats avec des supports à feuilles filtrantes ondulées, pliées ou enroulées
B01D 29/52 - Filtres à éléments filtrants stationnaires pendant la filtration, p.ex. filtres à aspiration ou à pression, non couverts par les groupes ; Leurs éléments filtrants à plusieurs éléments filtrants caractérisés par leur agencement relatif montés en parallèle
G21C 13/02 - Enceintes sous pression; Enceintes d'enveloppe; Enveloppes en général - Détails
G21C 19/307 - Dispositions pour introduire un matériau fluent à l'intérieur du cœur du réacteur; Dispositions pour enlever un matériau fluent du cœur du réacteur avec purification continue du matériau fluent en circulation, p.ex. par extraction des produits de fission spécialement adaptés pour des liquides
The present invention relates to a method of refurbishing calandria vessels in nuclear reactors, and more specifically, to a method of fastening calandria tubes to a tubesheet plate in a calandria when refurbishing a nuclear reactor. A method of refurbishing a calandria is described, comprising the steps of: forming circumferential cuts/serrations/grooves on the outside diameter of a calandria tube; and expanding/deforming the calandria tube into a bore of a tubesheet plate of the calandria, whereby the sharp edges of the serrations "bite" into the tubesheet plate to provide a leak- tight seal. Other aspects of the invention are also described.
The present invention relates to a method of refurbishing calandria vessels in nuclear reactors, and more specifically, to a method of fastening calandria tubes to a tubesheet plate in a calandria when refurbishing a nuclear reactor. A method of refurbishing a calandria is described, comprising the steps of: forming circumferential cuts/serrations/grooves on the outside diameter of a calandria tube; and expanding/deforming the calandria tube into a bore of a tubesheet plate of the calandria, whereby the sharp edges of the serrations "bite" into the tubesheet plate to provide a leak- tight seal. Other aspects of the invention are also described.
A phased array ultrasonic probe may be mounted to a component to be inspected for wall thickness on an apparatus that includes a split ring adapted to be magnetically held in place on the component. In particular, the probe may be mounted to a carriage connected to the split ring in a manner that allows the carriage to rotate around the split ring while the probe is in operation. Between the probe and the component, a transducer shoe defining, by a flexible membrane, a cavity and an aperture. Conveniently, the construction of the flexible membrane allows wall thickness measurements to be acquired in portions of the component that have complex topography, such as welds. The apparatus is installed on an adaptor assembly for inspection of straight section of pipes. This adaptor assembly is not used in absence of straight section. By acquiring data from multiple output pulse transmitted at multiple incidence angles, processing software may conveniently produce an accurate wall thickness map of the area of interest on the component.
A phased array ultrasonic probe may be mounted to a component to be inspected for wall thickness on an apparatus that includes a split ring adapted to be magnetically held in place on the component. In particular, the probe may be mounted to a carriage connected to the split ring in a manner that allows the carriage to rotate around the split ring while the probe is in operation. Between the probe and the component, a transducer shoe defining, by a flexible membrane, a cavity and an aperture. Conveniently, the construction of the flexible membrane allows wall thickness measurements to be acquired in portions of the component that have complex topography, such as welds. The apparatus is installed on an adaptor assembly for inspection of straight section of pipes. This adaptor assembly is not used in absence of straight section. By acquiring data from multiple output pulse transmitted at multiple incidence angles, processing software may conveniently produce an accurate wall thickness map of the area of interest on the component.
A phased array ultrasonic probe may be mounted to a component to be inspected for wall thickness on an apparatus that includes a split ring adapted to be magnetically held in place on the component. In particular, the probe may be mounted to a carriage connected to the split ring in a manner that allows the carriage to rotate around the split ring while the probe is in operation. Between the probe and the component, a transducer shoe defining, by a flexible membrane, a cavity and an aperture. Conveniently, the construction of the flexible membrane allows wall thickness measurements to be acquired in portions of the component that have complex topography, such as welds. The apparatus is installed on an adaptor assembly for inspection of straight section of pipes. This adaptor assembly is not used in absence of straight section. By acquiring data from multiple output pulse transmitted at multiple incidence angles, processing software may conveniently produce an accurate wall thickness map of the area of interest on the component.
Processes and devices useful in the application of coatings (14) to the interior of tubes (10) are described. Such processes (40, 400) may include applying a layer (20) of coating fluid (18) to the internal surface (16) of the tube (10) and passing a smoothing member (22) through the tube (10) at a distance from the internal surface (16). The viscosity of the coating fluid (18) may be selected so that the layer (20) of coating fluid (18) has a thickness substantially equal to or in excess of a predetermined wet film thickness (Twf) correlated to a desired final thickness (Tf) of the coating (14). The distance between the smoothing member (22) and the internal surface (16) may substantially correspond to the predetermined wet film thickness (Twf). The smoothing member (22) may smooth the coating fluid (18) and remove coating fluid (18) in excess of the wet film thickness (Twf) from the internal surface (16).
B05D 1/40 - Distribution des liquides ou d'autres matériaux fluides, appliqués par des éléments se déplaçant par rapport à la surface à couvrir
B05B 13/06 - Machines ou installations pour appliquer des liquides ou d'autres matériaux fluides sur des surfaces d'objets ou de matériaux par pulvérisation, non couverts par les groupes conçus spécialement pour traiter l'intérieur de corps creux
B05D 1/02 - Procédés pour appliquer des liquides ou d'autres matériaux fluides aux surfaces réalisés par pulvérisation
F16L 9/14 - Tubes en matériaux composites, c. à d. faits de matériaux non complètement couverts dans un seul des groupes précédents
F16L 55/164 - Dispositifs pour aveugler les fuites dans les tuyaux ou manches à partir de l'intérieur du tuyau un fluide d'étanchéité étant introduit à l'intérieur du tuyau
F16L 58/04 - Revêtements caractérisés par les matériaux utilisés
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
73.
PROCESSES AND DEVICES FOR APPLYING COATINGS TO THE INTERIOR OF TUBES
Processes and devices useful in the application of coatings (14) to the interior of tubes (10) are described. Such processes (40, 400) may include applying a layer (20) of coating fluid (18) to the internal surface (16) of the tube (10) and passing a smoothing member (22) through the tube (10) at a distance from the internal surface (16). The viscosity of the coating fluid (18) may be selected so that the layer (20) of coating fluid (18) has a thickness substantially equal to or in excess of a predetermined wet film thickness (Twf) correlated to a desired final thickness (Tf) of the coating (14). The distance between the smoothing member (22) and the internal surface (16) may substantially correspond to the predetermined wet film thickness (Twf). The smoothing member (22) may smooth the coating fluid (18) and remove coating fluid (18) in excess of the wet film thickness (Twf) from the internal surface (16).
B05D 1/40 - Distribution des liquides ou d'autres matériaux fluides, appliqués par des éléments se déplaçant par rapport à la surface à couvrir
B05B 13/06 - Machines ou installations pour appliquer des liquides ou d'autres matériaux fluides sur des surfaces d'objets ou de matériaux par pulvérisation, non couverts par les groupes conçus spécialement pour traiter l'intérieur de corps creux
B05D 1/02 - Procédés pour appliquer des liquides ou d'autres matériaux fluides aux surfaces réalisés par pulvérisation
F16L 55/164 - Dispositifs pour aveugler les fuites dans les tuyaux ou manches à partir de l'intérieur du tuyau un fluide d'étanchéité étant introduit à l'intérieur du tuyau
F16L 58/04 - Revêtements caractérisés par les matériaux utilisés
F16L 9/14 - Tubes en matériaux composites, c. à d. faits de matériaux non complètement couverts dans un seul des groupes précédents
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
74.
CALANDRIA TUBE, PRESSURE TUBE, AND ANNULUS SPACERS REMOVAL APPARATUS AND METHOD FOR NUCLEAR REACTOR RETUBING
Methods, tools, and systems for removing a calandria tube and a pressure tube from a nuclear reactor. One method includes gripping at least a portion of a first diameter of a calandria tube contained at a lattice site with a guide tool, wherein the calandria tube includes a pressure tube rotated from an operational position to a removal position, and gripping at least a portion of a second diameter of the calandria tube with a retrieval tool. The method also includes pulling the calandria tube with the retrieval tool to remove the calandria tube from at least one tube sheet and advancing the calandria tube and the rotated pressure tube as a package with the retrieval tool and the guide tool across at least a portion of the calandria toward a receiving end of the reactor. The method further includes releasing the guide tool from the first diameter of the calandria tube, and retracting the guide tool from the lattice site at the pushing end of the reactor.
Methods and systems for testing a joint assembly coupling a calandria tube to a tube sheet in a reactor. One method includes (a) inserting a test tool into a lattice site containing the joint assembly, the test tool including at least two seals that define an enclosed volume surrounding the joint assembly. The method also includes (b) drawing a vacuum in the enclosed volume, (c) stopping drawing the vacuum in the enclosed volume and allowing the vacuum to decay over a predetermined decay period, (d) measuring a change in pressure in the enclosed volume during the decay period and calculating a leak rate based on the change in pressure, (e) repeating (b) through (d) to generate a plurality of leak rates, and (f) determining an equilibrium leak rate based at least on the plurality of leak rates. The method also includes performing diagnostics during the testing method.
G21C 17/017 - Inspection ou maintenance de tuyaux ou de tubes dans des installations nucléaires
G01M 3/28 - Examen de l'étanchéité des structures ou ouvrages vis-à-vis d'un fluide par utilisation d'un fluide ou en faisant le vide par mesure du taux de perte ou de gain d'un fluide, p.ex. avec des dispositifs réagissant à la pression, avec des indicateurs de débit pour soupapes
76.
CALANDRIA TUBE INSERT REMOVAL FOR REACTOR RETUBING
Methods, apparatuses, and systems for removing an insert attaching a calandria tube to a tube sheet in a nuclear reactor during retubing of the reactor. One method includes (a) advancing a removal tool into a lattice site including a calandria tube and an insert until a head of the removal tool is positioned within a diameter of the calandria tube, (b) expanding at least one retractor of the removal tool radially to align the at least one retractor inboard of the insert, (c) retracting the at least one retractor axially to remove the insert from the calandria tube and the tube sheet and collect the insert on the removal tool, and (d) retracting the removal tool, with the collected insert, from the lattice site.
A method of calandria tube volume reduction during calandria tube replacement. The method includes the steps of removing at least one of an end fitting, a pressure tube, a calandria tube, and a garter spring from a nuclear reactor at the reactor face; placing at least one of an end fitting, a pressure tube, a calandria tube, and a garter spring into a flask at the reactor face; transporting the flask away from the reactor; removing at least one of an end fitting, a pressure tube, a calandria tube, and a garter spring from the flask; and performing volume reduction on the at least one of an end fitting, a pressure tube, a calandria tube, and a garter spring.
An apparatus and method of shielding radiation from a nuclear reactor having at least one fuel channel tube includes inserting a plug into an end of the fuel channel tube, providing a gas-tight seal with the plug in the fuel channel tube, and installing a flange about the plug and/or about the end of a sleeve also inserted within the fuel channel tube. In some embodiments, the sleeve receives the plug, and can protect the fuel channel tube and a wall aperture in which the fuel channel plug is received against damage. Also in some embodiments, radiation leakage can be reduced or prevented by the plug, the flange, and/or by a sealing arrangement between the sleeve and the plug and/or between the sleeve and the fuel channel tube.
A system and method of removing and replacing bellows on a nuclear reactor having a calandria and a fuel channel assembly includes severing the bellows of the fuel channel assembly at a ferrule adjacent a tube sheet of the reactor, removing the severed bellows, installing a replacement bellows at the remaining ferrule stub at or adjacent the tube sheet, and welding the replacement bellows to the ferrule stub at or adjacent the tube sheet.
A material handling system for use during retubing of a CANDU reactor is provided. The material handling system comprises a track system comprising a plurality of track sections; and a trolley comprising a cargo bed. The track sections include at least one curved track section. At least two wheel trucks are operatively coupled to the cargo bed, and a guide mechanism for interacting with the track system is provided where at least one of the wheel trucks pivots relative to the cargo bed.
A method of preparing a calandria tube sheet bore for receiving a calandria tube. The method includes the steps of polishing the bore of the calandria tube sheet; and inspecting the bore, wherein the steps of polishing the bore and inspecting the bore are repeated if there are geometric deviations from a uniform engineered surface in the bore that provide a potential leak pathway in the final fabricated joint.
A retube platform system for installation in a reactor vault adjacent an end face of a CANDU reactor core during a retube process. The retube platform system includes a plurality of columns, a platform, and an elevator system. Each of the plurality of columns is supported on at least one floor surface of the vault. The platform includes a frame and a decking surface secured to the frame to provide a working surface for personnel and retube tooling. The platform includes a front end adjacent the end face and a rear end remote from the end face. The elevator system is provided between the plurality of columns and the platform and is configured to move the platform with a vertical travel substantially equal to a height of the end face.
G21C 21/00 - Appareillage ou procédés spécialement adaptés pour la fabrication des réacteurs ou de pièces de ceux-ci
E04G 1/15 - Echafaudages reposant principalement sur le sol comprenant essentiellement des moyens particuliers pour supporter ou former des plates-formes; Plates-formes
G21C 17/017 - Inspection ou maintenance de tuyaux ou de tubes dans des installations nucléaires
A feeder platform system for installation in a reactor vault adjacent an end of a CANDU.TM. reactor core for accessing a feeder cabinet and feeder tubes therein during a retube process. The feeder platform system includes front and rear platforms. The front platform is movable between a variety of heights in a first vertical space adjacent the reactor core. The rear platform is movable between a variety of heights in a second vertical space adjacent the first vertical space. The front and rear platforms define respective lengths parallel to and spaced from the end of the reactor core. At least one of the lengths can be increased with a plurality of extensions releasably connectable with at least one of the front and rear platforms. Lifting mechanisms are coupled to each of the front and rear platforms and configured to raise and lower the front and rear platforms independently within the respective first and second vertical spaces.
G21C 21/00 - Appareillage ou procédés spécialement adaptés pour la fabrication des réacteurs ou de pièces de ceux-ci
E04G 1/15 - Echafaudages reposant principalement sur le sol comprenant essentiellement des moyens particuliers pour supporter ou former des plates-formes; Plates-formes
G21C 17/017 - Inspection ou maintenance de tuyaux ou de tubes dans des installations nucléaires
A method of removing feeders from a nuclear reactor includes removing at least a portion of a feeder cabinet that can include a feeder cabinet wall and a feeder cabinet soffit, followed by disconnection and removal of feeders used to supply and remove coolant from fuel channel assemblies of the reactor.
A pallet for supporting one of a plurality of tools for a nuclear reactor retubing operation, the pallet positionable adjacent to an end-face of a nuclear reactor core having a plurality of fuel channel assemblies having longitudinal axes aligned substantially parallel to each other. The pallet includes an elongated frame extending generally parallel to the longitudinal axes of the fuel channel assemblies for supporting one of the tools for the nuclear reactor retubing operation, the frame having guide surfaces for aligning the tool parallel to the longitudinal axes of the fuel channel assemblies. The pallet also includes an electrical cable connectable to the tool and a hydraulic hose for providing a pressurized fluid to the tool. The pallet is configured to interchangeably accommodate another of the plurality of tools using the same elongated frame, electrical cable and hydraulic hose.
A tool is provided for separating a feeder coupling from an end-fitting of a CANDU .TM.-type nuclear reactor fuel channel by shearing one or more feeder coupling fasteners. A gripper has an inside surface and an outside surface. A portion of the inside surface is configured to engage a snout of the end fitting. A pusher is disposed about the gripper. The pusher has a nose portion for contact with the feeder coupling. An actuator controllably acts between the pusher and the gripper to drive the pusher into the feeder coupling to shear the feeder coupling fasteners.
A worktable for supporting a tool for a nuclear reactor retubing operation. The worktable is positionable adjacent to an end-face of a nuclear reactor core and movable in a direction parallel to the end-face. The worktable includes a frame, a top member supported by the frame and having a surface for supporting a tool for the nuclear reactor retubing operation, a drive unit for moving the top member in the direction parallel to the end-face of the nuclear reactor core to position the tool adjacent to the end-face at a desired location, and a controller operably connected to the drive unit for controlling movement of the top member in the direction parallel to the end-face of the nuclear reactor core.
Fuel bundles for a nuclear reactor are described and illustrated, and in some cases include fuel elements each having a fissile content of 235U between about 0.9 wt% 235U and 5.0 wt% 235U, and wherein at least one of the fuel elements is a poisoned low-enriched uranium fuel element including a neutron poison in a concentration greater than about 5.0 vol%.
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 1/08 - Réacteurs hétérogènes, c. à d. dans lesquels le combustible et le modérateur sont séparés le modérateur étant hautement pressurisé, p.ex. réacteur à eau bouillante, réacteur à surchauffe intégrale, réacteur à eau pressurisée
G21C 3/42 - Emploi de substances spécifiées comme combustibles pour réacteurs
Fuel bundles for a nuclear reactor are described and illustrated, and in some cases include fuel elements each having a fissile content of 235U between about 0.9 wt% 235U and 5.0 wt% 235U, and wherein at least one of the fuel elements is a poisoned low-enriched uranium fuel element including a neutron poison in a concentration greater than about 5.0 vol%.
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 1/08 - Réacteurs hétérogènes, c. à d. dans lesquels le combustible et le modérateur sont séparés le modérateur étant hautement pressurisé, p.ex. réacteur à eau bouillante, réacteur à surchauffe intégrale, réacteur à eau pressurisée
G21C 3/42 - Emploi de substances spécifiées comme combustibles pour réacteurs
90.
NUCLEAR FUEL CONTAINING RECYCLED AND DEPLETED URANIUM, AND NUCLEAR FUEL BUNDLE AND NUCLEAR REACTOR COMPRISING SAME
Nuclear fuels for nuclear reactors are described, and include nuclear fuels having a first fuel component of recycled uranium, and a second fuel component of depleted uranium blended with the first fuel component, wherein the blended first and second fuel components have a fissile content of less than 1.2wt% of 2.35U. Also described are nuclear fuels having a first fuel component of recycled uranium, and a second fuel component of natural uranium blended with the first fuel component, wherein the blended first and second fuel components have a fissile content of less than 1.2wt% of 2.35U.
Nuclear fuels for nuclear reactors are described, and include nuclear fuels having a first fuel component of recycled uranium, and a second fuel component of depleted uranium blended with the first fuel component, wherein the blended first and second fuel components have a fissile content of less than 1.2wt% of 235U. Also described are nuclear fuels having a first fuel component of recycled uranium, and a second fuel component of natural uranium blended with the first fuel component, wherein the blended first and second fuel components have a fissile content of less than 1.2wt% of 235U.
The present invention provides a radiation detector for detecting both the intensity and direction of one or more sources of radiation comprising a radiation sensor, an inverse collimator that shields the sensor from at least a portion of the incident radiation originating from the direction in which the inverse collimator is pointed and a means for pointing the inverse collimator in different directions. In accordance with another aspect of the invention, there is provided a method for detecting both the intensity and direction of one or more sources of radiation comprising the steps of providing a radiation sensor, providing an inverse collimator that shields the sensor from at least a portion of the incident radiation originating from the direction in which the inverse collimator is pointed, providing a means for pointing the inverse collimator in different directions, pointing the inverse collimator in a direction, recording the direction in which the inverse collimator is pointed and recording the signal from the sensor, repeating the preceding two steps one or more times for one or more different directions.
A circumferential sampling tool for obtaining a sample from an interior wall of a tube has a cylindrical body with an aperture therein. First and second cutters are operatively connected to a shaft for rotation therewith. The first and second cutter are each movable radially between a retracted position and an extended position. First and second actuators are operatively connected to the first and second cutters respectively for moving the first and second cutters between their respective retracted and extended positions as the shaft rotates. Rotating the shaft causes the first cutter to move to the extended position thereby cutting a portion of the interior wall and then causes the second cutter to move to the extended position thereby cutting the sample from the interior wall from a location in the tube revealed by cutting the portion of the interior wall.
The present invention provides a radiation detector for detecting both the intensity and direction of one or more sources of radiation comprising a radiation sensor, an inverse collimator that shields the sensor from at least a portion of the incident radiation originating from the direction in which the inverse collimator is pointed and a means for pointing the inverse collimator in different directions. In accordance with another aspect of the invention, there is provided a method for detecting both the intensity and direction of one or more sources of radiation comprising the steps of providing a radiation sensor, providing an inverse collimator that shields the sensor from at least a portion of the incident radiation originating from the direction in which the inverse collimator is pointed, providing a means for pointing the inverse collimator in different directions, pointing the inverse collimator in a direction, recording the direction in which the inverse collimator is pointed and recording the signal from the sensor, repeating the preceding two steps one or more times for one or more different directions.
The present invention provides a polymer indentation method and tester that includes measuring the time taken by a polymeric material to recover a set portion of an initial deformation and use this duration as a material degradation indicator. The recovery time was found to be more sensitive to cable degradation than the specific compressive stiffness (or indenter modulus) measured during the indentation phase, and this high sensitivity was achieved for both thermally aged and irradiated polymer samples.
G01N 3/42 - Recherche de la dureté ou de la dureté au rebondissement en effectuant des empreintes sous une charge permanente par des dispositifs de pénétration, p.ex. sphère, pyramide
A controller for producing a nuclear reactor shutdown system trip signal in response to at least one detector signal. The controller includes a signal conditioning module receiving the at least one detector signal and outputting a measured flux signal. A rate module generates a rate signal from the measured flux signal. A comparator circuit compares the rate signal to a trip setpoint and generates a first trip signal.
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 7/22 - 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 d'un matériau fluide ou fluent absorbant les neutrons
G21C 9/00 - Dispositions pour la protection d'urgence structurellement associées avec le réacteur
A method for producing a nuclear reactor shutdown system trip signal in response to at least one detector signal, and a controller for doing so. The controller includes a signal conditioning module receiving the at least one detector signal and outputting a measured flux signal. A rate module generates a rate signal from the measured flux signal. A comparator circuit comapares the rate signal to a trip setpoint and generates a first trip signal.
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
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 9/033 - Moyens pour effectuer une réduction très rapide du facteur de réactivité dans des conditions défectueuses, p.ex. fusible pour réacteur par un fluide absorbant
A controller for producing a nuclear reactor shutdown system trip signal in response to at least one detector signal. The controller includes a signal conditioning module receiving the at least one detector signal and outputting a measured flux signal. A rate module generates a rate signal from the measured flux signal. A comparator circuit compares the rate signal to a trip setpoint and generates a first trip signal.
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 7/22 - 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 d'un matériau fluide ou fluent absorbant les neutrons
G21C 9/00 - Dispositions pour la protection d'urgence structurellement associées avec le réacteur
A controller for producing a nuclear reactor shutdown system trip signal in response to at least one detector signal. The controller includes a signal conditioning module receiving the at least one detector signal and outputting a measured flux signal. A rate module generates a rate signal from the measured flux signal. A comparator circuit compares the rate signal to a trip setpoint and generates a first trip signal.
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
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 7/22 - 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 d'un matériau fluide ou fluent absorbant les neutrons
G21C 15/18 - Dispositions pour le refroidissement d'urgence; Mise hors circuit de la chaleur
Fuel bundles for a nuclear reactor are disclosed, and in some embodiments include a first fuel element including thorium dioxide; a second fuel element including uranium having a first fissile content; and a third fuel element including uranium having a second fissile content different from the first fissile content. Nuclear reactors using such fuel bundles are also disclosed, including pressurized heavy water nuclear reactors. The uranium having the different fissile contents can include combinations of natural uranium, depleted uranium, recycled uranium, slightly enriched uranium, and low enriched uranium.
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 3/328 - Disposition relative des éléments dans le réseau
