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.
C10J 3/18 - Continuous processes using electricity
C07C 1/04 - Preparation of hydrocarbons from one or more compounds, none of them being a hydrocarbon from oxides of carbon from carbon monoxide with hydrogen
2.
PROCESS FOR PRODUCING SYNTHETIC HYDROCARBONS FROM BIOMASS
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 - Self-supporting filtering elements arranged for inward flow filtration
B01D 29/39 - Filters with filtering elements stationary during filtration, e.g. pressure or suction filters, not covered by groups ; Filtering elements therefor with hollow discs side by side on, or around, one or more tubes, e.g. of the leaf type
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 - Separation of gases or vapours; Recovering vapours of volatile solvents from gases; Chemical or biological purification of waste gases, e.g. engine exhaust gases, smoke, fumes, flue gases or aerosols by electrical effects other than those provided for in group
B01D 59/38 - Separation by electrochemical methods
B01D 59/40 - Separation by electrochemical methods by electrolysis
B01D 59/50 - Separation involving two or more processes covered by different groups selected from groups , , , , , , , ,
B01D 59/42 - Separation by electrochemical methods by electrophoresis
B01D 59/30 - Separation by chemical exchange by ion exchange
C25B 9/23 - Cells comprising dimensionally-stable non-movable electrodes; Assemblies of constructional parts thereof with diaphragms comprising ion-exchange membranes in or on which electrode material is embedded
C25B 9/70 - Assemblies comprising two or more cells
C25B 15/08 - Supplying or removing reactants or electrolytes; Regeneration of electrolytes
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.
G21C 3/326 - Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different composition; Comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
G21C 3/328 - Relative disposition of the elements in the bundle lattice
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 - Joints or fittings for double-walled or multi-channel pipes or pipe assemblies
F16L 9/19 - Multi-channel pipes or pipe assemblies
F28F 9/26 - Arrangements for connecting different sections of heat-exchange elements, e.g. of radiators
F28D 7/10 - Heat-exchange apparatus having stationary tubular conduit assemblies for both heat-exchange media, the media being in contact with different sides of a conduit wall the conduits being arranged one within the other, e.g. concentrically
F28F 13/06 - Arrangements for modifying heat transfer, e.g. increasing, decreasing by affecting the pattern of flow of the heat-exchange media
G21C 3/322 - Means to influence the coolant flow through or around the bundles
G21C 15/02 - Arrangement or disposition of passages in which heat is transferred to the coolant, e.g. for coolant circulation through the supports of the fuel elements
G21C 3/328 - Relative disposition of the elements in the bundle lattice
G21C 1/20 - Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor coolant being pressurised moderator being liquid, e.g. pressure-tube reactor
G21C 21/00 - Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
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 - Filters with filtering elements stationary during filtration, e.g. pressure or suction filters, not covered by groups ; Filtering elements therefor
G01N 23/207 - Diffractometry, e.g. using a probe in a central position and one or more displaceable detectors in circumferential positions
10.
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 - Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
G01K 1/143 - Supports; Fastening devices; Arrangements for mounting thermometers in particular locations for measuring surface temperatures
G01K 13/02 - Thermometers specially adapted for specific purposes for measuring temperature of moving fluids or granular materials capable of flow
G01K 7/04 - Measuring temperature based on the use of electric or magnetic elements directly sensitive to heat using thermoelectric elements, e.g. thermocouples the object to be measured not forming one of the thermoelectric materials
11.
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 - Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core
G21C 3/326 - Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different composition; Comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
G21C 3/328 - Relative disposition of the elements in the bundle lattice
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 - Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different composition; Comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
G21C 7/26 - Control of nuclear reaction by displacement of the moderator or parts thereof
G21C 5/20 - Moderator or core structure; Selection of materials for use as moderator characterised by the provision of more than one active zone wherein one zone contains fissile material and another zone contains breeder material
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 - Filters with filtering elements stationary during filtration, e.g. pressure or suction filters, not covered by groups ; Filtering elements therefor with hollow discs side by side on, or around, one or more tubes, e.g. of the leaf type
B01D 29/33 - Self-supporting filtering elements arranged for inward flow filtration
14.
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 - Investigating or analysing non-biological materials by the use of the chemical methods specified in the subgroups; Apparatus specially adapted for such methods
G01N 5/04 - Analysing materials by weighing, e.g. weighing small particles separated from a gas or liquid by removing a component, e.g. by evaporation, and weighing the remainder
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 - Investigating or analysing materials by the use of electric, electrochemical, or magnetic means by investigating magnetic variables for investigating the presence of flaws using eddy currents
16.
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 - Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
G21C 3/18 - Internal spacers or other non-active material within the casing, e.g. compensating for expansion of fuel rods or for compensating excess reactivity
F16L 7/00 - Supporting pipes or cables inside other pipes or sleeves, e.g. for enabling pipes or cables to be inserted or withdrawn from under roads or railways without interruption of traffic
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 - Automatic analysis not limited to methods or materials provided for in any single one of groups ; Handling materials therefor using a stream of discrete samples flowing along a tube system, e.g. flow injection analysis
G01N 23/00 - Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups , or
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 15/02 - Arrangement or disposition of passages in which heat is transferred to the coolant, e.g. for coolant circulation through the supports of the fuel elements
G21C 13/024 - Supporting constructions for pressure vessels or containment vessels
G21C 1/20 - Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor coolant being pressurised moderator being liquid, e.g. pressure-tube reactor
19.
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 - Subject matter not provided for in other groups of this subclass
G21G 1/00 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes
20.
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 - Supporting pipes or cables inside other pipes or sleeves, e.g. for enabling pipes or cables to be inserted or withdrawn from under roads or railways without interruption of traffic
G21C 3/18 - Internal spacers or other non-active material within the casing, e.g. compensating for expansion of fuel rods or for compensating excess reactivity
G21C 17/06 - Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
21.
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 15/02 - Arrangement or disposition of passages in which heat is transferred to the coolant, e.g. for coolant circulation through the supports of the fuel elements
23.
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.
C23C 8/08 - Solid state diffusion of only non-metal elements into metallic material surfaces; Chemical surface treatment of metallic material by reaction of the surface with a reactive gas, leaving reaction products of surface material in the coating, e.g. conversion coatings, passivation of metals using gases only one element being applied
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 - Measuring arrangements or details thereof, where the measuring technique is not covered by the other groups of this subclass, unspecified or not relevant for measuring diameters internal diameters
G21C 1/20 - Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor coolant being pressurised moderator being liquid, e.g. pressure-tube reactor
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.
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 - Investigating fluid tightness of structures by using fluid or vacuum by detecting the presence of fluid at the leakage point using special tracer materials, e.g. dye, fluorescent material, radioactive material for valves
F17D 5/04 - Preventing, monitoring, or locating loss by means of a signalling fluid enclosed in a double wall
27.
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.
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 1/29 - Measurement performed on radiation beams, e.g. position or section of the beam; Measurement of spatial distribution of radiation
G01N 23/083 - Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups , or by transmitting the radiation through the material and measuring the absorption the radiation being X-rays
H01J 3/14 - Arrangements for focusing or reflecting ray or beam
G01V 5/00 - Prospecting or detecting by the use of nuclear radiation, e.g. of natural or induced radioactivity
G01N 23/04 - Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups , or by transmitting the radiation through the material and forming images of the material
G01N 23/20 - Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups , or by using reflection of the radiation by the materials
H01J 37/252 - Tubes for spot-analysing by electron or ion beams; Microanalysers
30.
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 - Radioactive sources other than neutron sources
C01G 99/00 - Subject matter not provided for in other groups of this subclass
G01G 1/00 - Weighing apparatus involving the use of a counterweight or other counterbalancing mass
G01G 3/12 - Weighing apparatus characterised by the use of elastically-deformable members, e.g. spring balances wherein the weighing element is in the form of a solid body stressed by pressure or tension during weighing
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 - Radioactive sources other than neutron sources
G01G 1/00 - Weighing apparatus involving the use of a counterweight or other counterbalancing mass
G01G 3/12 - Weighing apparatus characterised by the use of elastically-deformable members, e.g. spring balances wherein the weighing element is in the form of a solid body stressed by pressure or tension during weighing
C01G 99/00 - Subject matter not provided for in other groups of this subclass
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 - Apparatus for, or methods of, measuring force, work, mechanical power, or torque, specially adapted for specific purposes for measuring tension in flexible members, e.g. ropes, cables, wires, threads, belts or bands using mechanical means
G01B 17/00 - Measuring arrangements characterised by the use of infrasonic, sonic, or ultrasonic vibrations
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 - Moderator or core structure; Selection of materials for use as moderator characterised by the provision of more than one active zone wherein one zone contains fissile material and another zone contains breeder material
G21C 3/326 - Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different composition; Comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
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 - Processes, other than flocking, specially adapted for applying liquids or other fluent materials to particular surfaces or for applying particular liquids or other fluent materials to internal surfaces, e.g. of tubes
B05C 7/08 - Apparatus specially designed for applying liquid or other fluent material to the inside of hollow work by devices moving in contact with the work for applying liquids or other fluent materials to the inside of tubes
F16L 58/14 - Coatings characterised by the materials used by ceramic or vitreous materials
G21C 3/20 - Constructional details - Details of the construction within the casing with non-active interlayer between casing and active material
G21C 21/02 - Manufacture of fuel elements or breeder elements contained in non-active casings
B05C 3/18 - Apparatus in which the work is brought into contact with a bulk quantity of liquid or other fluent material only one side of the work coming into contact with the liquid or other fluent material
B05C 11/02 - Apparatus for spreading or distributing liquids or other fluent materials already applied to a surface; Control of the thickness of a coating
B05D 1/40 - Distributing applied liquids or other fluent materials by members moving relatively to surface
B05D 1/42 - Distributing applied liquids or other fluent materials by members moving relatively to surface by non-rotary members
40.
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 - Arrangements for orientation or scanning
G01B 17/02 - Measuring arrangements characterised by the use of infrasonic, sonic, or ultrasonic vibrations for measuring thickness
G21C 17/017 - Inspection or maintenance of pipe-lines or tubes in nuclear installations
G01N 29/22 - Investigating or analysing materials by the use of ultrasonic, sonic or infrasonic waves; Visualisation of the interior of objects by transmitting ultrasonic or sonic waves through the object - Details
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 - Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
G21C 3/326 - Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different composition; Comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
G21C 19/20 - Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
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 - Selection of substances for use as reactor fuel
G21C 1/20 - Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor coolant being pressurised moderator being liquid, e.g. pressure-tube reactor
G21C 3/326 - Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different composition; Comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
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 - Rigid members, e.g. L-shaped members, with parts engaging the under surface of the loads; Crane hooks
B66C 1/46 - Gripping members engaging only the external or internal surface of the articles and applying frictional forces by inflatable elements
B66C 1/62 - Load-engaging elements or devices attached to lifting, lowering, or hauling gear of cranes, or adapted for connection therewith for transmitting forces to articles or groups of articles by mechanical means comprising article-engaging members of a shape complementary to that of the articles to be handled
G21C 19/32 - Apparatus for removing radioactive objects or materials from the reactor discharge area, e.g. to a storage place; Apparatus for handling radioactive objects or materials within a storage place or removing them therefrom
G21F 5/14 - Devices for handling containers or shipping-casks, e.g. transporting devices
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 - Pressure vessels; Containment vessels; Containment in general - Details
G01B 21/20 - Measuring arrangements or details thereof, where the measuring technique is not covered by the other groups of this subclass, unspecified or not relevant for measuring contours or curvatures, e.g. determining profile
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 - Investigating fluid tightness of structures by using fluid or vacuum by detecting the presence of fluid at the leakage point using special tracer materials, e.g. dye, fluorescent material, radioactive material for valves
F17D 5/04 - Preventing, monitoring, or locating loss by means of a signalling fluid enclosed in a double wall
48.
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 - Cells comprising dimensionally-stable non-movable electrodes; Assemblies of constructional parts thereof with diaphragms two or more diaphragms
C25B 1/04 - Hydrogen or oxygen by electrolysis of water
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 - Investigating fluid tightness of structures by using fluid or vacuum by detecting the presence of fluid at the leakage point using special tracer materials, e.g. dye, fluorescent material, radioactive material for valves
F17D 5/04 - Preventing, monitoring, or locating loss by means of a signalling fluid enclosed in a double wall
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 - Measuring arrangements or details thereof, where the measuring technique is not covered by the other groups of this subclass, unspecified or not relevant for measuring contours or curvatures, e.g. determining profile
G21C 13/02 - Pressure vessels; Containment vessels; Containment in general - Details
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 - Rigid members, e.g. L-shaped members, with parts engaging the under surface of the loads; Crane hooks
B66C 1/46 - Gripping members engaging only the external or internal surface of the articles and applying frictional forces by inflatable elements
B66C 1/62 - Load-engaging elements or devices attached to lifting, lowering, or hauling gear of cranes, or adapted for connection therewith for transmitting forces to articles or groups of articles by mechanical means comprising article-engaging members of a shape complementary to that of the articles to be handled
G21C 19/32 - Apparatus for removing radioactive objects or materials from the reactor discharge area, e.g. to a storage place; Apparatus for handling radioactive objects or materials within a storage place or removing them therefrom
G21F 5/14 - Devices for handling containers or shipping-casks, e.g. transporting devices
52.
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 - Rigid members, e.g. L-shaped members, with parts engaging the under surface of the loads; Crane hooks
B66C 1/46 - Gripping members engaging only the external or internal surface of the articles and applying frictional forces by inflatable elements
B66C 1/62 - Load-engaging elements or devices attached to lifting, lowering, or hauling gear of cranes, or adapted for connection therewith for transmitting forces to articles or groups of articles by mechanical means comprising article-engaging members of a shape complementary to that of the articles to be handled
G21F 5/14 - Devices for handling containers or shipping-casks, e.g. transporting devices
54.
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.
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 - Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different composition; Comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
G21C 3/328 - Relative disposition of the elements in the bundle lattice
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 - Pressure vessels; Containment vessels; Containment in general - Details
G21C 13/00 - Pressure vessels; Containment vessels; Containment in general
G21C 19/20 - Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
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 - Pressure vessels; Containment vessels; Containment in general - Details
G21C 13/00 - Pressure vessels; Containment vessels; Containment in general
G21C 19/20 - Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
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 - Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling-water reactor, integral-superheat reactor, pressurised-water reactor
G21C 5/02 - Moderator or core structure; Selection of materials for use as moderator - Details
G21C 19/19 - Reactor parts specifically adapted to facilitate handling, e.g. to facilitate charging or discharging of fuel elements
G21C 1/10 - Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling-water reactor, integral-superheat reactor, pressurised-water reactor moderator and coolant being different or separated
G21C 15/02 - Arrangement or disposition of passages in which heat is transferred to the coolant, e.g. for coolant circulation through the supports of the fuel elements
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.
G01N 25/00 - Investigating or analysing materials by the use of thermal means
G01J 5/00 - Radiation pyrometry, e.g. infrared or optical thermometry
G01K 1/00 - MEASURING TEMPERATURE; MEASURING QUANTITY OF HEAT; THERMALLY-SENSITIVE ELEMENTS NOT OTHERWISE PROVIDED FOR - Details of thermometers not specially adapted for particular types of thermometer
G01K 3/00 - Thermometers giving results other than momentary value of temperature
G01K 13/00 - Thermometers specially adapted for specific purposes
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 - Measuring arrangements or details thereof, where the measuring technique is not covered by the other groups of this subclass, unspecified or not relevant
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 - Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
G21C 1/10 - Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling-water reactor, integral-superheat reactor, pressurised-water reactor moderator and coolant being different or separated
G21C 1/20 - Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor coolant being pressurised moderator being liquid, e.g. pressure-tube reactor
G21C 13/04 - Arrangements for expansion and contraction
G21C 15/02 - Arrangement or disposition of passages in which heat is transferred to the coolant, e.g. for coolant circulation through the supports of the fuel elements
G21C 15/20 - Partitions or thermal insulation between fuel channel and moderator, e.g. in pressure tube reactors
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 - Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups , or by transmitting the radiation through the material and forming images of the material
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 - Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups , or by transmitting the radiation through the material and forming images of the material
G01N 23/20 - Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups , or by using reflection of the radiation by the materials
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 - Filters with filtering elements stationary during filtration, e.g. pressure or suction filters, not covered by groups ; Filtering elements therefor with flat filtering elements supported with corrugated, folded or wound filtering sheets
B01D 29/52 - Filters with filtering elements stationary during filtration, e.g. pressure or suction filters, not covered by groups ; Filtering elements therefor with multiple filtering elements, characterised by their mutual disposition in parallel connection
G21C 13/02 - Pressure vessels; Containment vessels; Containment in general - Details
G21C 19/307 - Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products specially adapted for liquids
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 - Distributing applied liquids or other fluent materials by members moving relatively to surface
B05B 13/06 - Machines or plants for applying liquids or other fluent materials to surfaces of objects or other work by spraying, not covered by groups specially designed for treating the inside of hollow bodies
B05D 1/02 - Processes for applying liquids or other fluent materials performed by spraying
F16L 9/14 - Compound tubes, i.e. made of materials not wholly covered by any one of the preceding groups
F16L 55/164 - Devices for covering leaks in pipes or hoses, e.g. hose-menders from inside the pipe a sealing fluid being introduced in the pipe
F16L 58/04 - Coatings characterised by the materials used
G21C 3/20 - Constructional details - Details of the construction within the casing with non-active interlayer between casing and active material
74.
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 - Distributing applied liquids or other fluent materials by members moving relatively to surface
B05B 13/06 - Machines or plants for applying liquids or other fluent materials to surfaces of objects or other work by spraying, not covered by groups specially designed for treating the inside of hollow bodies
B05D 1/02 - Processes for applying liquids or other fluent materials performed by spraying
F16L 55/164 - Devices for covering leaks in pipes or hoses, e.g. hose-menders from inside the pipe a sealing fluid being introduced in the pipe
F16L 58/04 - Coatings characterised by the materials used
F16L 9/14 - Compound tubes, i.e. made of materials not wholly covered by any one of the preceding groups
G21C 3/20 - Constructional details - Details of the construction within the casing with non-active interlayer between casing and active material
75.
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 or maintenance of pipe-lines or tubes in nuclear installations
G01M 3/28 - Investigating fluid tightness of structures by using fluid or vacuum by measuring rate of loss or gain of fluid, e.g. by pressure-responsive devices, by flow detectors for valves
77.
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.
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.
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 - Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different composition; Comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
G21C 1/08 - Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling-water reactor, integral-superheat reactor, pressurised-water reactor
G21C 3/42 - Selection of substances for use as reactor fuel
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 - Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different composition; Comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
G21C 1/08 - Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling-water reactor, integral-superheat reactor, pressurised-water reactor
G21C 3/42 - Selection of substances for use as reactor fuel
91.
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.
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 - Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
G21C 7/22 - Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of a fluid or fluent neutron-absorbing material
G21C 9/00 - Emergency protection arrangements structurally associated with the reactor
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 - Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
G21C 7/08 - Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
G21C 9/033 - Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse by an absorbent fluid
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 - Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
G21C 7/22 - Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of a fluid or fluent neutron-absorbing material
G21C 9/00 - Emergency protection arrangements structurally associated with the reactor
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 - Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
G21C 7/08 - Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
G21C 7/22 - Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of a fluid or fluent neutron-absorbing material
