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 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
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.
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
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
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
10.
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.
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 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
13.
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
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 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.
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
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
18.
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 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 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
21.
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 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 application is related to a concentrated decontaminating reagent composition and related method useful for decontamination of nuclear reactors, or components thereof. The concentrated reagent composition is injected into the nuclear reactor, or component thereof, to form a dilute reagent that comprises from about 0.6 to about 3.0 g/L (2.1-10.3 mM) EDTA and from about 0.4 to about 2.2 g/L (2.1-11.5 mM) citric acid. The composition and method of this application can be used effectively in a regenerative process to decontaminate a nuclear reactor, or a component of thereof, with high efficiency without causing significant corrosion to the components of the cooling systems.
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.
The present invention provides a probe apparatus and an associated method for measuring a magnetite deposit thickness, which apparatus and method is independent of the porosity and magnetic permeability of the magnetite deposit. The probe apparatus of this invention is an axial scanning and inside surface-following probe that can accurately and reliably measure the inside diameter of a tube. The probe apparatus of the present invention optionally comprises two modules: the first module is the surface-following module and the second module is a conventional eddy current probe.
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
G01B 7/06 - Measuring arrangements characterised by the use of electric or magnetic techniques for measuring length, width, or thickness for measuring thickness
G01N 27/82 - Investigating or analysing materials by the use of electric, electrochemical, or magnetic means by investigating magnetic variables for investigating the presence of flaws
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.
The present invention provides an apparatus for detecting and/or repositioning annulus spacers used to maintain the position of a pressure tube withm 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
G01V 1/00 - Seismology; Seismic or acoustic prospecting or detecting
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
Disclosed herein is provided an evaporator/calciner in which hazardous materials, such as radioactive liquids, are converted into chemically stable, solid forms by evaporating, drying and calcination within a single vessel, that can then be sealed and used for long term storage.
A62D 3/00 - Processes for making harmful chemical substances harmless, or less harmful, by effecting a chemical change in the substances
A62D 3/40 - Processes for making harmful chemical substances harmless, or less harmful, by effecting a chemical change in the substances by heating to effect chemical change, e.g. by pyrolysis
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.
patents
