SYSTEMS AND METHODS FOR THE PRODUCTION OF ACID DEFICIENT URANYL NITRATE FROM A DILUTE URANYL NITRATE SOLUTION VIA DIFFUSION DIALYSIS AND VACUUM DISTILLATION
Systems and methods for producing acid deficient uranyl nitrate from a dilute uranyl nitrate solution are disclosed. In one form, the present disclosure provides a system comprising a feed evaporation system and a diffusion dialysis system. The feed evaporation system is configured to receive a feed stream and to boil off water, under vacuum, from the feed stream to produce a concentrated uranyl nitrate solution and a distilled water product. The diffusion dialysis system is configured to counter flow the concentrated uranyl nitrate solution and the distilled water product across a plurality of membrane vessels to promote nitrate migration from the concentrated uranyl nitrate solution to the distilled water, and to produce a dialysate stream and a recycle acid stream. The feed stream may include a product of a solvent extraction process used to recycle spent nuclear fuel and/or a recovery stream from other fuel fabrication activities.
SYSTEMS AND METHODS FOR THE PRODUCTION OF ACID DEFICIENT URANYL NITRATE FROM A DILUTE URANYL NITRATE SOLUTION VIA DIFFUSION DIALYSIS AND VACUUM DISTILLATION
Systems and methods for producing acid deficient uranyl nitrate from a dilute uranyl nitrate solution are disclosed. In one form, the present disclosure provides a system comprising a feed evaporation system and a diffusion dialysis system. The feed evaporation system is configured to receive a feed stream and to boil off water, under vacuum, from the feed stream to produce a concentrated uranyl nitrate solution and a distilled water product. The diffusion dialysis system is configured to counter flow the concentrated uranyl nitrate solution and the distilled water product across a plurality of membrane vessels to promote nitrate migration from the concentrated uranyl nitrate solution to the distilled water, and to produce a dialysate stream and a recycle acid stream. The feed stream may include a product of a solvent extraction process used to recycle spent nuclear fuel and/or a recovery stream from other fuel fabrication activities.
A crucible used for forming ceramic particles from metal oxide gel particles includes a tubular graphite housing having an open end, an inner surface, and a seat in the inner surface near the open end. A sleeve lines the inner surface of the tubular housing. The sleeve has at an open end and is formed from a metal which is chemically inert to the metal oxide gel particles. A graphite outer cap removably covers the open end of the tubular housing. An inner cap formed from the chemically inert metal fits into the seat in the inner surface of the tubular housing, and is pressed into the seat against the open end of the sleeve by the outer cap. The crucible may be used for forming ceramic particles from uranium oxide gel particles, and the sleeve and the inner cap may be formed from molybdenum, tungsten, or an alloy thereof.
A crucible used for forming ceramic particles from metal oxide gel particles includes a tubular graphite housing having an open end, an inner surface, and a seat in the inner surface near the open end. A sleeve lines the inner surface of the tubular housing. The sleeve has at an open end and is formed from a metal which is chemically inert to the metal oxide gel particles. A graphite outer cap removably covers the open end of the tubular housing. An inner cap formed from the chemically inert metal fits into the seat in the inner surface of the tubular housing, and is pressed into the seat against the open end of the sleeve by the outer cap. The crucible may be used for forming ceramic particles from uranium oxide gel particles, and the sleeve and the inner cap may be formed from molybdenum, tungsten, or an alloy thereof.
C04B 35/495 - Shaped ceramic products characterised by their composition; Ceramic compositions; Processing powders of inorganic compounds preparatory to the manufacturing of ceramic products based on oxides based on vanadium, niobium, tantalum, molybdenum or tungsten oxides or solid solutions thereof with other oxides, e.g. vanadates, niobates, tantalates, molybdates or tungstates
B65D 25/18 - Linings or internal coatings spaced appreciably from container wall
B65D 85/20 - Containers, packaging elements or packages, specially adapted for particular articles or materials for incompressible or rigid rod-shaped or tubular articles
5.
SYSTEM FOR PNEUMATIC TRANSPORT OF PARTICLES OF A HAZARDOUS SUBSTANCE
A system for transporting hazardous particles includes a pneumatic conveyer for conveying the hazardous particles to an exit using a carrier gas; and an input mechanism for conveying the hazardous particles to the pneumatic conveyer. The input mechanism includes a tubular chamber for receiving the hazardous particles; an input pipe extending from the tubular chamber for conveying the hazardous particles into the tubular chamber; and an output pipe extending from a bottom of the tubular chamber. The output pipe includes an upper valve movable between a closed position and an open position, a middle valve movable between a closed position and an open position, and a lower valve. The upper valve and the middle valve, when in their respective closed positions, define a storage chamber for storing a portion of the hazardous particles. The upper valve in its open position allows the portion of the hazardous particles to enter the storage chamber, and the middle valve in its open position allows the portion of the hazardous particles in the storage chamber to flow to the lower valve. The lower valve is configured to convey the hazardous particles from the storage chamber to the pneumatic conveyer in a gradual fashion.
B65G 53/12 - Gas pressure systems operating without fluidisation of the materials with pneumatic injection of the materials by the propelling gas the gas flow acting directly on the materials in a reservoir
B65G 53/66 - Use of indicator or control devices, e.g. for controlling gas pressure, for controlling proportions of material and gas, for indicating or preventing jamming of material
The present disclosure is directed to drive shaft assemblies for a rotary furnace. In one form, a rotary furnace comprises a crucible and a drive shaft assembly. The drive shaft assembly comprises a primary shaft and a secondary shaft coupled with the primary shaft. The secondary shaft comprises: a first portion comprising a refractory alloy, the first portion defining a first end and a second end, where the first end of the first portion is configured to couple with the primary shaft; and a second portion comprising graphite, the second portion defining a first end and a second end, where the first end of the second portion is configured to couple with the second end of the first portion and the second end of the second portion is configured to couple with the crucible.
A system for transporting hazardous particles includes a pneumatic conveyer for conveying the particles to an exit using a carrier gas; and an input mechanism for conveying the particles to the conveyer. The input mechanism includes a chamber for receiving the particles; an input pipe extending from the chamber for conveying the particles into the chamber; and an output pipe extending from a bottom of the chamber. The output pipe includes an upper valve movable between closed and open positions, a middle valve movable between closed and open positions, and a lower valve. The upper valve and the middle valve, when in their closed positions, define a storage chamber. The upper valve in its open position allows the particles to enter the storage chamber, and the middle valve in its open position allows the particles in the storage chamber to flow through the lower valve to the conveyer.
B65G 53/58 - Devices for accelerating or decelerating flow of the materials; Use of pressure generators
B65G 53/66 - Use of indicator or control devices, e.g. for controlling gas pressure, for controlling proportions of material and gas, for indicating or preventing jamming of material
Composite gel particles with an ammonium diuranate matrix phase and a phenolic resin phase incorporated within the ammonium diuranate matrix phase are produced from a first solution comprising uranyl nitrate, a phenol, and optionally formaldehyde, wherein the uranyl nitrate and the phenol are present in a ratio ranging from 2:1 to 25:1; and a second solution comprising hexamethylenetetramine and urea. The first solution and the second solution are mixed, and drops of the resulting mixture into a heated second liquid which is immiscible with the mixed solution. Heat from the second liquid causes the hexamethylenetetramine to decompose to form ammonia, which reacts with the uranyl nitrate to cause each of the drops to form an ammonium diuranate gel particle. The ammonium diuranate gel particles are collected. The ammonium diuranate gel particles include the phenolic resin phase within the ammonium diuranate matrix phase, where the phenolic resin phase is formed by reaction between the phenol and formaldehyde. The first solution may include uranyl nitrate, the phenol, and formaldehyde, and the formaldehyde and the phenol may react to form the phenolic resin phase prior to mixing the first solution and the second solution. The first solution may be free of formaldehyde, and heat from the second liquid may causes the hexamethylenetetramine to decompose to form formaldehyde in situ; so that the formaldehyde and the phenol react to form the phenolic resin phase while the ammonia reacts with the uranyl nitrate.
C08G 8/10 - Condensation polymers of aldehydes or ketones with phenols only of aldehydes of formaldehyde, e.g. of formaldehyde formed in situ with phenol
A useful metal may be recovered from a solution of a nitrate salt of a metal cation or a metal oxycation, by adding the solution of the nitrate salt to a formation column having an inlet and an outlet nozzle, the solution of the nitrate salt being added in a dropwise fashion through the inlet. The formation column contains a recirculating solution containing a base selected from the group consisting of ammonia, ammonium hydroxide, an alkali metal hydroxide, and an alkaline earth metal hydroxide. The nitrate salt reacts with the base in the recirculating solution to produce a metal oxide salt or a metal hydroxide salt as a precipitate. The precipitate and the recirculating solution exit the formation column through the outlet nozzle and are captured the precipitate in a basket beneath the formation column while recovering the recirculating solution in a catch tank under the basket.
C22B 3/14 - Extraction of metal compounds from ores or concentrates by wet processes by leaching in inorganic alkaline solutions containing ammonia or ammonium salts
C22B 3/22 - Treatment or purification of solutions, e.g. obtained by leaching by physical processes, e.g. by filtration, by magnetic means
C22B 3/44 - Treatment or purification of solutions, e.g. obtained by leaching by chemical processes
10.
NUCLEAR REACTOR WITH AN AXIALLY STRATIFIED FUEL BED
A nuclear reactor has an axially stratified fuel bed. The reactor features a reactor shell having a base, a top having an exhaust outlet, and an axis. The axially stratified fuel bed is within the reactor shell, and includes: a first zone configured to operate at a first temperature T1, the first zone comprising a plurality of first fuel particles, each first fuel particle comprising a first radioactive ceramic core and a first ceramic seal coating; and a second zone configured to operate at a second temperature T2, where T2>T1, the second zone comprising a plurality of second fuel particles, each second fuel particle comprising a second radioactive ceramic core and a second ceramic seal coating. A coolant fluid flow path carries a coolant fluid from the base of the reactor to the exhaust outlet, along a flow path passing sequentially through the first zone and the second zone. The first ceramic seal coating has greater stability at T1 than at T2, and the second ceramic seal coating has greater stability at T2 than the first ceramic seal coating.
A neutron reflector design which lowers stress in inner reflector members by supporting the inner reflector members on radially adjacent outer reflector members at the interface between the inner and outer reflector members, such that an individual inner reflector member is not supported by an inner reflector member in a layer of the reflector assembly immediately below, and the inner reflector member does not have to bear a load from an inner reflector member in a layer of the reflector assembly immediately above. The lowering of the load carried by the individual inner reflector members with this individual-member-support arrangement reduces stress-induced reflector damage with is enhanced in the high radiation flux environment adjacent to a nuclear reactor core. The inner reflector members are removable for replacement without the need to remove the outer reflector members.
A neutron reflector design which lowers stress in inner reflector members by supporting the inner reflector members on radially adjacent outer reflector members at the interface between the inner and outer reflector members, such that an individual inner reflector member is not supported by an inner reflector member in a layer of the reflector assembly immediately below, and the inner reflector member does not have to bear a load from an inner reflector member in a layer of the reflector assembly immediately above. The lowering of the load carried by the individual inner reflector members with this individual- member-support arrangement reduces stress-induced reflector damage with is enhanced in the high radiation flux environment adjacent to a nuclear reactor core. The inner reflector members are removable for replacement without the need to remove the outer reflector members.
An improved system for receiving and storing a radioactive salt solution includes a tank configured to receive the radioactive salt solution while preventing criticality accidents, a solution inlet for carrying the radioactive salt solution to the tank, an overflow bottle, and a cap sealing the top end of the tank. The cap includes a lateral wye fitting having a lateral pipe configured to direct the radioactive salt solution from the solution inlet into the tank, a vertical pipe configured to direct gases from the tank to a ventilation system, and an overflow line configured to carry excess radioactive salt solution from the tank to the overflow tank. An air gap between the lateral pipe and the solution inlet prevents backflow of the radioactive salt solution into the solution inlet. A control system includes a level switch configured to provide a signal that the tank contains a maximum volume of the radioactive salt solution, a first valve configured to terminate flow of the radioactive salt solution to the lateral pipe upon receipt of the signal from the level switch; and a second valve configured to allow flow of the radioactive salt solution from the tank to the overflow line.
An improved system for receiving and storing a radioactive salt solution includes a tank configured to receive the radioactive salt solution while preventing criticality accidents, a solution inlet for carrying the radioactive salt solution to the tank, an overflow bottle, and a cap sealing the top end of the tank. The cap includes a lateral wye fitting having a lateral pipe configured to direct the radioactive salt solution from the solution inlet into the tank, a vertical pipe configured to direct gases from the tank to a ventilation system, and an overflow line configured to carry excess radioactive salt solution from the tank to the overflow tank. An air gap between the lateral pipe and the solution inlet prevents backflow of the radioactive salt solution into the solution inlet. A control system includes a level switch configured to provide a signal that the tank contains a maximum volume.
A useful metal may be recovered from a solution of a nitrate salt of a metal cation or a metal oxycation, by adding the solution of the nitrate salt to a formation column having an inlet and an outlet nozzle, the solution of the nitrate salt being added in a dropwise fashion through the inlet. The formation column contains a recirculating solution containing a base selected from the group consisting of ammonia, ammonium hydroxide, an alkali metal hydroxide, and an alkaline earth metal hydroxide. The nitrate salt reacts with the base in the recirculating solution to produce a metal oxide salt or a metal hydroxide salt as a precipitate. The precipitate and the recirculating solution exit the formation column through the outlet nozzle and are captured the precipitate in a basket beneath the formation column while recovering the recirculating solution in a catch tank under the basket. The recovered recirculating solution is pumped from the catch tank to the formation column. The nitrate salt of the metal cation may be a nitrate salt of a radioactive metal cation, e.g., uranium or a uranyl cation.
C22B 60/02 - Obtaining thorium, uranium or other actinides
C22B 3/14 - Extraction of metal compounds from ores or concentrates by wet processes by leaching in inorganic alkaline solutions containing ammonia or ammonium salts
C22B 3/44 - Treatment or purification of solutions, e.g. obtained by leaching by chemical processes
C22B 3/22 - Treatment or purification of solutions, e.g. obtained by leaching by physical processes, e.g. by filtration, by magnetic means
16.
Nuclear reactor with an axially stratified fuel bed
a second zone configured to operate at a second temperature T2, where T2>T1, the second zone comprising a plurality of second fuel particles, each second fuel particle comprising a second radioactive ceramic core and a second ceramic seal coating. A coolant fluid flow path carries a coolant fluid from the base of the reactor to the exhaust outlet, along a flow path passing sequentially through the first zone and the second zone. The first ceramic seal coating has greater stability at T1 than at T2, and the second ceramic seal coating has greater stability at T2 than the first ceramic seal coating.
An optical counter is used in a method and system for producing a nuclear fuel element having a known volume of homogeneously distributed nuclear material. The method includes feeding nuclear fuel particles along a channel having a conveyer configured to transmit the nuclear fuel particles to an exit; driving the conveyer until a target number of nuclear fuel particles exits the channel through the exit; and counting a number of nuclear fuel particles which pass through the exit of the channel with an optical counter. The conveyer is stopped after the target number of nuclear fuel particles exits the channel. The target number of nuclear fuel particles are fed into a mold for shaping the nuclear fuel element, and void space remaining in the mold is filled with a particulate matrix material so as to homogeneously distribute the target number of nuclear fuel particles within the particulate matrix material. The particulate matrix material is then converted into a solid matrix material.
B29C 64/165 - Processes of additive manufacturing using a combination of solid and fluid materials, e.g. a powder selectively bound by a liquid binder, catalyst, inhibitor or energy absorber
G21C 3/28 - Fuel elements with fissile or breeder material in solid form within a non-active casing
G01N 15/06 - Investigating concentration of particle suspensions
G21C 1/07 - Pebble-bed reactors; Reactors with granular fuel
18.
SYSTEM AND METHOD FOR MAKING NUCLEAR FUEL ELEMENTS WITH A CONTROLLED NUMBER OF NUCLEAR PARTICLES
An optical counter is used in a method and system for producing a nuclear fuel element having a known volume of homogeneously distributed nuclear material. The method includes feeding nuclear fuel particles along a channel having a conveyer configured to transmit the nuclear fuel particles to an exit; driving the conveyer until a target number of nuclear fuel particles exits the channel through the exit; and counting a number of nuclear fuel particles which pass through the exit of the channel with an optical counter. The conveyer is stopped after the target number of nuclear fuel particles exits the channel. The target number of nuclear fuel particles are fed into a mold for shaping the nuclear fuel element, and void space remaining in the mold is filled with a particulate matrix material so as to homogeneously distribute the target number of nuclear fuel particles within the particulate matrix material. The particulate matrix material is then converted into a solid matrix material.
A metal or ceramic layer may be deposited on nuclear materials by chemical vapor deposition using a non-halogenated liquid organometallic metal precursor. The chemical vapor deposition is carried out by a method including steps of introducing nuclear fuel particles into a fluidized bed reactor, and heating the fluidized bed reactor to a desired operating temperature T1. A flow of a carrier- gas is initiated through a vaporizer, and the non-halogenated liquid organometallic metal precursor is injected into the vaporizer and vaporized. A first mixture of the carrier gas and the vaporized non-halogenated liquid organometallic metal precursor may be mixed with a gaseous carbon source, a gaseous nitrogen source, a gaseous oxygen source, or a mixture thereof to produce a second mixture; and the second mixture flows into the fluidized bed reactor at operating temperature T1, allowing deposition of a desired ceramic coating on the particles. The non-halogenated liquid organometallic metal precursor may be a compound of Zr, Hf, Nb, Ta, W, V, Ti, or a mixture thereof.
C23C 16/448 - Chemical coating by decomposition of gaseous compounds, without leaving reaction products of surface material in the coating, i.e. chemical vapour deposition (CVD) processes characterised by the method of coating characterised by the method used for generating reactive gas streams, e.g. by evaporation or sublimation of precursor materials
C23C 16/442 - Chemical coating by decomposition of gaseous compounds, without leaving reaction products of surface material in the coating, i.e. chemical vapour deposition (CVD) processes characterised by the method of coating using fluidised bed processes
111, allowing deposition of a desired ceramic coating on the particles. The non-halogenated liquid organometallic metal precursor may be a compound of Zr, Hf, Nb, Ta, W, V, Ti, or a mixture thereof.
C23C 16/448 - Chemical coating by decomposition of gaseous compounds, without leaving reaction products of surface material in the coating, i.e. chemical vapour deposition (CVD) processes characterised by the method of coating characterised by the method used for generating reactive gas streams, e.g. by evaporation or sublimation of precursor materials
C23C 16/44 - Chemical coating by decomposition of gaseous compounds, without leaving reaction products of surface material in the coating, i.e. chemical vapour deposition (CVD) processes characterised by the method of coating
C23C 16/452 - Chemical coating by decomposition of gaseous compounds, without leaving reaction products of surface material in the coating, i.e. chemical vapour deposition (CVD) processes characterised by the method of coating characterised by the method used for generating reactive gas streams, e.g. by evaporation or sublimation of precursor materials by activating reactive gas streams before introduction into the reaction chamber, e.g. by ionization or by addition of reactive species
37 - Construction and mining; installation and repair services
42 - Scientific, technological and industrial services, research and design
Goods & Services
(1) Nuclear reactors; nuclear generators; mobile nuclear reactors and nuclear generators (1) Construction of nuclear reactors and nuclear generators
(2) Designing plant components and equipment for nuclear power plants; Providing fuel design services for others in the field of nuclear power plants; Designing components and equipment for fuel fabrication and transportation; Nuclear engineering
37 - Construction and mining; installation and repair services
42 - Scientific, technological and industrial services, research and design
Goods & Services
Nuclear reactors; nuclear generators; mobile nuclear reactors and nuclear generators Construction of nuclear reactors and nuclear generators Designing plant components and equipment for nuclear power plants; Providing fuel design services for others in the field of nuclear power plants; Designing components and equipment for fuel fabrication and transportation; Nuclear engineering
25.
System and method for controlling metal oxide gel particle size
Metal oxide gel particles, may be prepared with a desired particle size, by preparing a low-temperature aqueous metal nitrate solution containing hexamethylene tetramine as a feed solution; and causing the feed solution to flow through a first tube and exit the first tube as a first stream at a first flow rate, so as to contact a high-temperature nonaqueous drive fluid. The drive fluid flows through a second tube at a second flow rate. Shear between the first stream and the drive fluid breaks the first stream into particles of the metal nitrate solution, and decomposition of hexamethylene tetramine converts metal nitrate solution particles into metal oxide gel particles. A metal oxide gel particle size is measured optically, using a sensor device directed at a flow of metal oxide gel particles within the stream of drive fluid. The sensor device measures transmission of light absorbed by either the metal oxide gel particles or the drive fluid, so that transmission of light through the drive fluid changes for a period of time as a metal oxide gel particle passes the optical sensor. If a measured particle size is not about equal to a desired particle size, the particle size may be corrected by adjusting a ratio of the first flow rate to a total flow rate, where the total flow rate is the sum of the first and second flow rates.
G01N 15/02 - Investigating particle size or size distribution
G01N 11/12 - Investigating flow properties of materials, e.g. viscosity or plasticity; Analysing materials by determining flow properties by moving a body within the material by measuring penetration of wedged gauges
G01N 11/00 - Investigating flow properties of materials, e.g. viscosity or plasticity; Analysing materials by determining flow properties
26.
PREPARATION OF ACID-DEFICIENT URANYL NITRATE SOLUTIONS
A solution of acid deficient uranyl nitrate has a formula of UO2(OH)y(NO3)2-y, where y ranges from 0.1 to 0.5. The solution is prepared by placing UxOz in aqueous nitric acid to produce a uranium solution, wherein x is 1 to 3 and z is 2 to 8; placing the uranium solution under a pressure greater than atmospheric pressure in a sealed reaction chamber; and heating the uranium solution to a desired temperature of between 150°C and 250°C by applying microwave energy to the uranium solution. The uranium solution is maintained at the desired temperature under a pressure of from 5 atmospheres to 40 atmospheres for a hold time of 15 minutes to 6 hours to produce the desired acid deficient uranyl nitrate.
B01J 19/12 - Processes employing the direct application of electric or wave energy, or particle radiation; Apparatus therefor employing electromagnetic waves
2y32-yxzz in aqueous nitric acid to produce a uranium solution, wherein x is 1 to 3 and z is 2 to 8; placing the uranium solution under a pressure greater than atmospheric pressure in a sealed reaction chamber; and heating the uranium solution to a desired temperature of between 150°C and 250°C by applying microwave energy to the uranium solution. The uranium solution is maintained at the desired temperature under a pressure of from 5 atmospheres to 40 atmospheres for a hold time of 15 minutes to 6 hours to produce the desired acid deficient uranyl nitrate.
B01J 19/12 - Processes employing the direct application of electric or wave energy, or particle radiation; Apparatus therefor employing electromagnetic waves
28.
Preparation of acid-deficient uranyl nitrate solutions
z in aqueous nitric acid to produce a uranium solution, wherein x is 1 to 3 and z is 2 to 8; placing the uranium solution under a pressure greater than atmospheric pressure in a sealed reaction chamber; and heating the uranium solution to a desired temperature of between 150° C. and 250° C. by applying microwave energy to the uranium solution. The uranium solution is maintained at the desired temperature under a pressure of from 5 atmospheres to 40 atmospheres for a hold time of 15 minutes to 6 hours to produce the desired acid deficient uranyl nitrate.
A method of measuring the size of metal oxide gel particles in a flowing stream is provided, comprising: a. causing a stream of a drive fluid containing metal oxide gel particles to flow past at least two optical sensors, the at least two sensors being separated by a distance which is less than a desired particle size; b. measuring a metal oxide gel particle size or flow rate optically with the at least two optical sensors; said optical sensors measuring transmission of light at a defined wavelength absorbed by either the metal oxide gel particles or the drive fluid, so that transmission of light through the drive fluid at the defined wavelength changes for a period of time as a metal oxide gel particle passes the optical sensors. A method of optimizing the size of metal oxide gel particles and a system for producing such particles are also provided.
G01F 1/7086 - Measuring the time taken to traverse a fixed distance using optical detecting arrangements
G01F 1/708 - Measuring the time taken to traverse a fixed distance
G01P 3/68 - Devices characterised by the determination of the time taken to traverse a fixed distance using optical means, i.e. using infrared, visible, or ultraviolet light
30.
SYSTEM AND METHOD FOR CONTROLLING METAL OXIDE GEL PARTICLE SIZE
Metal oxide gel particles, may be prepared with a desired particle size, by preparing a low- temperature aqueous metal nitrate solution containing hexamethylene tetramine as a feed solution; and causing the feed solution to flow through a first tube and exit the first tube as a first stream at a first flow rate, so as to contact a high-temperature nonaqueous drive fluid. The drive fluid flows through a second tube at a second flow rate. Shear between the first stream and the drive fluid breaks the first stream into particles of the metal nitrate solution, and decomposition of hexamethylene tetramine converts metal nitrate solution particles into metal oxide gel particles. A metal oxide gel particle size is measured optically, using a sensor device directed at a flow of metal oxide gel particles within the stream of drive fluid. The sensor device measures transmission of light absorbed by either the metal oxide gel particles or the drive fluid, so that transmission of light through the drive fluid changes for a period of time as a metal oxide gel particle passes the optical sensor. If a measured particle size is not about equal to a desired particle size, the particle size may be corrected by adjusting a ratio of the first flow rate to a total flow rate, where the total flow rate is the sum of the first and second flow rates.
G01F 1/66 - Measuring the volume flow or mass flow of fluid or fluent solid material wherein the fluid passes through a meter in a continuous flow by measuring frequency, phase shift or propagation time of electromagnetic or other waves, e.g. using ultrasonic flowmeters
01 - Chemical and biological materials for industrial, scientific and agricultural use
11 - Environmental control apparatus
37 - Construction and mining; installation and repair services
40 - Treatment of materials; recycling, air and water treatment,
42 - Scientific, technological and industrial services, research and design
Goods & Services
(1) Fuel for nuclear reactors; uranium; uranium fuel for use in commercial nuclear power plants; high-assay, low-enriched uranium.
(2) Nuclear reactors; nuclear generators; mobile nuclear reactors and nuclear generators. (1) Construction of nuclear reactors and nuclear generators.
(2) Fuel processing, namely, producing fuel forms for nuclear power plants.
(3) Designing plant components and equipment for nuclear power plants; providing fuel design services for others in the field of nuclear power plants; designing components and equipment for fuel fabrication and transportation; nuclear engineering; consulting services in the field of nuclear reactors; construction planning of nuclear reactors; consulting services in the field of space crafts and outer space exploration.
40 - Treatment of materials; recycling, air and water treatment,
37 - Construction and mining; installation and repair services
42 - Scientific, technological and industrial services, research and design
Goods & Services
Fuel processing, namely, producing fuel forms for nuclear power plants Construction of nuclear reactors and nuclear generators Designing plant components and equipment for nuclear power plants; Providing fuel design services for others in the field of nuclear power plants; Designing components and equipment for fuel fabrication and transportation; Nuclear engineering
01 - Chemical and biological materials for industrial, scientific and agricultural use
11 - Environmental control apparatus
37 - Construction and mining; installation and repair services
40 - Treatment of materials; recycling, air and water treatment,
42 - Scientific, technological and industrial services, research and design
Goods & Services
(1) Fuel for nuclear reactors; uranium; uranium fuel for use in commercial nuclear power plants; high-assay, low-enriched uranium.
(2) Nuclear reactors; nuclear generators; mobile nuclear reactors and nuclear generators. (1) Construction of nuclear reactors and nuclear generators.
(2) Fuel processing, namely, producing fuel forms for nuclear power plants.
(3) Designing plant components and equipment for nuclear power plants; providing fuel design services for others in the field of nuclear power plants; designing components and equipment for fuel fabrication and transportation; nuclear engineering; consulting services in the field of nuclear reactors; construction planning of nuclear reactors; consulting services in the field of space crafts and outer space exploration.
40 - Treatment of materials; recycling, air and water treatment,
01 - Chemical and biological materials for industrial, scientific and agricultural use
11 - Environmental control apparatus
37 - Construction and mining; installation and repair services
42 - Scientific, technological and industrial services, research and design
Goods & Services
Fuel processing, namely, producing fuel forms for nuclear power plants Fuel for nuclear reactors; Uranium; Uranium fuel for use in commercial nuclear power plants; High-assay, low-enriched uranium Nuclear reactors; nuclear generators; mobile nuclear reactors and nuclear generators Construction of nuclear reactors and nuclear generators Designing plant components and equipment for nuclear power plants; Providing fuel design services for others in the field of nuclear power plants; Designing components and equipment for fuel fabrication and transportation; Nuclear engineering
36.
System and method for controlling metal oxide gel particle size
Metal oxide gel particles, may be prepared with a desired particle size, by preparing a low-temperature aqueous metal nitrate solution containing hexamethylene tetramine as a feed solution; and causing the feed solution to flow through a first tube and exit the first tube as a first stream at a first flow rate, so as to contact a high-temperature nonaqueous drive fluid. The drive fluid flows through a second tube at a second flow rate. Shear between the first stream and the drive fluid breaks the first stream into particles of the metal nitrate solution, and decomposition of hexamethylene tetramine converts metal nitrate solution particles into metal oxide gel particles. A metal oxide gel particle size is measured optically, using a sensor device directed at a flow of metal oxide gel particles within the stream of drive fluid. The sensor device measures transmission of light absorbed by either the metal oxide gel particles or the drive fluid, so that transmission of light through the drive fluid changes for a period of time as a metal oxide gel particle passes the optical sensor. If a measured particle size is not about equal to a desired particle size, the particle size may be corrected by adjusting a ratio of the first flow rate to a total flow rate, where the total flow rate is the sum of the first and second flow rates.
G01N 15/02 - Investigating particle size or size distribution
G01N 11/12 - Investigating flow properties of materials, e.g. viscosity or plasticity; Analysing materials by determining flow properties by moving a body within the material by measuring penetration of wedged gauges
G01N 11/00 - Investigating flow properties of materials, e.g. viscosity or plasticity; Analysing materials by determining flow properties
37.
FLUIDIZED BED REACTOR SYSTEM ALLOWING PARTICLE SAMPLING DURING AN ONGOING REACTION
A fluidized gas reactor includes a system for preventing a fluidizing gas comprising a reactant from premature reaction. The reactor includes a reaction chamber including a particle bed; a gas distribution plate having a plurality of openings therethrough, wherein each opening opens into the reaction chamber; and a plurality of vertical fluidizing gas inlet tubes, each of which is in fluid communication with one of the openings in the distribution plate. Each inlet tube is configured to receive a fluidizing gas from a fluidized gas source and transport the gas to the reaction chamber. A coolant system prevents the gas from undergoing reaction before entering the reaction chamber. Each inlet tube may include a particle outlet and a valve system, the valve system allowing the gas flow to the inlet tubes to be stopped; and allowing recovery of particles from the particle bed while the gas flow is stopped.
B01J 8/24 - Chemical or physical processes in general, conducted in the presence of fluids and solid particles; Apparatus for such processes with fluidised particles according to "fluidised-bed" technique
38.
FLUIDIZED BED REACTOR SYSTEM ALLOWING PARTICLE SAMPLING DURING AN ONGOING REACTION
A fluidized gas reactor includes a system for preventing a fluidizing gas comprising a reactant from premature reaction. The fluidized gas reactor includes a reaction chamber including a particle bed; a gas distribution plate having a plurality of openings therethrough, wherein each opening opens into the reaction chamber; and a plurality of vertical fluidizing gas inlet tubes, each of the fluidizing gas inlet tubes being in fluid communication with one of the openings in the gas distribution plate. Each fluidizing gas inlet tube is configured to receive a fluidizing gas and transport the fluidizing gas to the reaction chamber. A fluidizing gas source provides a stream of the fluidizing gas to the fluidizing gas inlet tubes. A coolant system prevents the fluidizing gas from undergoing reaction before entering the reaction chamber. The coolant system has a fluid inlet; a coolant flow path in fluid communication with the fluid inlet, the coolant flow path being configured to cool each fluidizing gas inlet tube; and a fluid outlet in fluid communication with the coolant flow path. Each fluidizing gas inlet tube may include a particle outlet and a valve system, where the valve system allows the fluidizing gas flow to the fluidizing gas inlet tubes to be stopped; and allows recovery of particles from the particle bed while the fluidizing gas flow is stopped.
B01J 8/24 - Chemical or physical processes in general, conducted in the presence of fluids and solid particles; Apparatus for such processes with fluidised particles according to "fluidised-bed" technique
B01J 8/18 - Chemical or physical processes in general, conducted in the presence of fluids and solid particles; Apparatus for such processes with fluidised particles
39.
SYSTEM FOR RECOVERING ENTRAINED PARTICLES FROM AN EXHAUST GAS STREAM
Entrained particles from an exhaust gas stream may be removed from the gas stream with a device including a housing having a top, an inner surface, and a bottom with a hole passing therethrough, where the housing further includes an impact surface. An entrance pipe guides the exhaust gas stream into the housing toward the impact surface, and is arranged so that the entrance pipe has an inner diameter x; and the impact surface is separated from the opening of the entrance pipe by a distance y, wherein y is between 3x and 3?x. An exit pipe guide the exhaust gas stream out of the housing. A receptacle is removably connected to the hole in the bottom of the housing. The impact surface diverts the exhaust gas stream from a first flow direction to a second flow direction, causing the entrained particles to fall from the exhaust gas stream into the receptacle before entering the exit pipe.
B01D 45/08 - Separating dispersed particles from gases or vapours by gravity, inertia, or centrifugal forces by utilising inertia by impingement against baffle separators
B01J 8/18 - Chemical or physical processes in general, conducted in the presence of fluids and solid particles; Apparatus for such processes with fluidised particles
40.
SYSTEM FOR RECOVERING ENTRAINED PARTICLES FROM AN EXHAUST GAS STREAM
Entrained particles from an exhaust gas stream may be removed from the gas stream with a device including a housing having a top, an inner surface, and a bottom with a hole passing therethrough, where the housing further includes an impact surface. An entrance pipe guides the exhaust gas stream into the housing toward the impact surface, and is arranged so that the entrance pipe has an inner diameter x; and the impact surface is separated from the opening of the entrance pipe by a distance y, wherein y is between 3x and 3⅓x. An exit pipe guide the exhaust gas stream out of the housing. A receptacle is removably connected to the hole in the bottom of the housing. The impact surface diverts the exhaust gas stream from a first flow direction to a second flow direction, causing the entrained particles to fall from the exhaust gas stream into the receptacle before entering the exit pipe.
B01J 8/00 - Chemical or physical processes in general, conducted in the presence of fluids and solid particles; Apparatus for such processes
B01D 45/08 - Separating dispersed particles from gases or vapours by gravity, inertia, or centrifugal forces by utilising inertia by impingement against baffle separators
B01J 8/18 - Chemical or physical processes in general, conducted in the presence of fluids and solid particles; Apparatus for such processes with fluidised particles
41.
Fluidized bed reactor system allowing particle sampling during an ongoing reaction
A fluidized gas reactor includes a system for preventing a fluidizing gas comprising a reactant from premature reaction. The fluidized gas reactor includes a reaction chamber including a particle bed; a gas distribution plate having a plurality of openings therethrough, wherein each opening opens into the reaction chamber; and a plurality of vertical fluidizing gas inlet tubes, each of the fluidizing gas inlet tubes being in fluid communication with one of the openings in the gas distribution plate. Each fluidizing gas inlet tube is configured to receive a fluidizing gas and transport the fluidizing gas to the reaction chamber. A fluidizing gas source provides a stream of the fluidizing gas to the fluidizing gas inlet tubes. A coolant system prevents the fluidizing gas from undergoing reaction before entering the reaction chamber. The coolant system has a fluid inlet; a coolant flow path in fluid communication with the fluid inlet, the coolant flow path being configured to cool each fluidizing gas inlet tube; and a fluid outlet in fluid communication with the coolant flow path. Each fluidizing gas inlet tube may include a particle outlet and a valve system, where the valve system allows the fluidizing gas flow to the fluidizing gas inlet tubes to be stopped; and allows recovery of particles from the particle bed while the fluidizing gas flow is stopped.
B01J 8/18 - Chemical or physical processes in general, conducted in the presence of fluids and solid particles; Apparatus for such processes with fluidised particles
B01J 8/00 - Chemical or physical processes in general, conducted in the presence of fluids and solid particles; Apparatus for such processes
42.
System for recovering entrained particles from an exhaust gas stream
Entrained particles from an exhaust gas stream may be removed from the gas stream with a device including a housing having a top, an inner surface, and a bottom with a hole passing therethrough, where the housing further includes an impact surface. An entrance pipe guides the exhaust gas stream into the housing toward the impact surface, and is arranged so that the entrance pipe has an inner diameter x; and the impact surface is separated from the opening of the entrance pipe by a distance y, wherein y is between 3x and ⅓x. An exit pipe guide the exhaust gas stream out of the housing. A receptacle is removably connected to the hole in the bottom of the housing. The impact surface diverts the exhaust gas stream from a first flow direction to a second flow direction, causing the entrained particles to fall from the exhaust gas stream into the receptacle before entering the exit pipe.
B01J 8/00 - Chemical or physical processes in general, conducted in the presence of fluids and solid particles; Apparatus for such processes
B01D 45/08 - Separating dispersed particles from gases or vapours by gravity, inertia, or centrifugal forces by utilising inertia by impingement against baffle separators
B01J 8/18 - Chemical or physical processes in general, conducted in the presence of fluids and solid particles; Apparatus for such processes with fluidised particles
43.
Nuclear fuel pebble and method of manufacturing the same
A method of manufacturing nuclear fuel elements may include: forming a base portion of the fuel element by depositing a powdered matrix material including a mixture of a graphite material and a fibrous material; depositing particles on the base portion in a predetermined pattern to form a first particle layer, by controlling the position of each particle in the first particle layer; depositing the matrix material on the first particle layer to form a first matrix layer; depositing particles on the first matrix layer in a predetermined pattern to form a second particle layer by controlling positions of each particle in the second particle layer; depositing the matrix material on the second particle layer to form a second matrix layer; and forming a cap portion of the fuel pebble by depositing the matrix material. The particles in the first particle layer and the second particle layer include nuclear fuel particles.
G21C 1/07 - Pebble-bed reactors; Reactors with granular fuel
B29C 64/165 - Processes of additive manufacturing using a combination of solid and fluid materials, e.g. a powder selectively bound by a liquid binder, catalyst, inhibitor or energy absorber
B33Y 80/00 - Products made by additive manufacturing
44.
Nuclear fuel pebble and method of manufacturing the same
Nuclear fuel elements may include: a fuel zone including fuel particles disposed in parallel layers in a matrix including graphite powder; and a shell comprising graphite and surrounding the fuel zone. The fuel particles may include fissile particles, burnable poison particles, breeder particles, or a combination thereof. The fuel zone may include a central region and a peripheral region surrounding the central region, and a fuel particle density of the peripheral region may be greater than a fuel particle density of the central region.
G21C 21/02 - Manufacture of fuel elements or breeder elements contained in non-active casings
B29C 64/165 - Processes of additive manufacturing using a combination of solid and fluid materials, e.g. a powder selectively bound by a liquid binder, catalyst, inhibitor or energy absorber
G21C 21/14 - Manufacture of fuel elements or breeder elements contained in non-active casings by plating in a fluid
B33Y 80/00 - Products made by additive manufacturing
G21C 1/07 - Pebble-bed reactors; Reactors with granular fuel
A multi-inlet gas distributor for a fluidized bed chemical vapor deposition reactor may include a distributor body having an inlet surface, an exit surface opposed to the inlet surface, and a side perimeter surface. The distributor body may also include multiple-inlets evenly spaced from each other, wherein the multiple-inlets penetrate the distributor body from the inlet surface to a first depth. The distributor body may additionally include cone-shaped apertures connecting to corresponding ones of the multiple-inlets at the first depth and extend from the first depth toward the exit surface. An apex may be formed on the exit surface at the intersection of the cone-shaped apertures.
A multi-inlet gas distributor for a fluidized bed chemical vapor deposition reactor may include a distributor body having an inlet surface, an exit surface opposed to the inlet surface, and a side perimeter surface. The distributor body may also include multiple-inlets evenly spaced from each other, wherein the multiple-inlets penetrate the distributor body from the inlet surface to a first depth. The distributor body may additionally include cone-shaped apertures connecting to corresponding ones of the multiple-inlets at the first depth and extend from the first depth toward the exit surface. An apex may be formed on the exit surface at the intersection of the cone-shaped apertures.
A multi-inlet gas distributor for a fluidized bed chemical vapor deposition reactor that may include a distributor body having an inlet surface, an exit surface opposed to the inlet surface, and a side perimeter surface. The distributor body may also include multiple-inlets evenly spaced from each other, wherein the multiple-inlets penetrate the distributor body from the inlet surface to a first depth. The distributor body may additionally include cone-shaped apertures connecting to corresponding ones of the multiple-inlets at the first depth and extend from the first depth toward the exit surface. An apex may be formed on the exit surface at the intersection of the cone-shaped apertures.
C23C 16/455 - Chemical coating by decomposition of gaseous compounds, without leaving reaction products of surface material in the coating, i.e. chemical vapour deposition (CVD) processes characterised by the method of coating characterised by the method used for introducing gases into the reaction chamber or for modifying gas flows in the reaction chamber
C23C 16/442 - Chemical coating by decomposition of gaseous compounds, without leaving reaction products of surface material in the coating, i.e. chemical vapour deposition (CVD) processes characterised by the method of coating using fluidised bed processes
C23C 16/44 - Chemical coating by decomposition of gaseous compounds, without leaving reaction products of surface material in the coating, i.e. chemical vapour deposition (CVD) processes characterised by the method of coating
C04B 35/626 - Preparing or treating the powders individually or as batches
C04B 35/16 - Shaped ceramic products characterised by their composition; Ceramic compositions; Processing powders of inorganic compounds preparatory to the manufacturing of ceramic products based on oxides based on silicates other than clay
Nuclear fuel elements may include: a fuel zone including fuel particles disposed in parallel layers in a matrix including graphite powder; and a shell comprising graphite and surrounding the fuel zone. The fuel particles may include fissile particles, burnable poison particles, breeder particles, or a combination thereof. The fuel zone may include a central region and a peripheral region surrounding the central region, and a fuel particle density of the peripheral region may be greater than a fuel particle density of the central region.
G21C 1/07 - Pebble-bed reactors; Reactors with granular fuel
B29C 64/165 - Processes of additive manufacturing using a combination of solid and fluid materials, e.g. a powder selectively bound by a liquid binder, catalyst, inhibitor or energy absorber
A method of manufacturing nuclear fuel elements may include: forming a base portion of the fuel element by depositing a powdered matrix material including a mixture of a graphite material and a fibrous material; depositing particles on the base portion in a predetermined pattern to form a first particle layer, by controlling the position of each particle in the first particle layer; depositing the matrix material on the first particle layer to form a first matrix layer; depositing particles on the first matrix layer in a predetermined pattern to form a second particle layer by controlling positions of each particle in the second particle layer; depositing the matrix material on the second particle layer to form a second matrix layer; and forming a cap portion of the fuel pebble by depositing the matrix material. The particles in the first particle layer and the second particle layer include nuclear fuel particles.
A method of manufacturing nuclear fuel elements may include: forming a graphite base of the fuel element; depositing a first layer of graphite and/or graphite spheres on the base portion; depositing a first layer of fuel, burnable poison and/or breeder particles on the first layer of graphite and/or graphite spheres; forming a second layer of graphite and/or graphite spheres on the first layer of particles; depositing a second layer of fuel, burnable poison and/or breeder particles on the second layer of graphite and/or graphite spheres; and forming a graphite cap portion of the fuel element. Adjacent fuel, burnable poison and/or breeder particles of the first layer are spaced apart by substantially the same distance, and adjacent fuel, burnable poison and/or breeder particles of the second layer are spaced apart by substantially the same distance. Fuel elements may be spherical fuel pebbles. Fuel particles may be tri-structural-isotropic particles without an overcoat.
A method of mass producing nuclear fuel elements may include: forming a graphite base portion of the fuel elements; repeatedly performing a sequence of operations comprising depositing a uniform graphite layer over a previous layer, depositing a layer of particles on the uniform graphite layer within a fuel zone diameter, so that the particles are spaced apart in a predefined pattern, and applying a binder using additive manufacturing methods to bind each layer with successively increasing and then decreasing diameters to form a central portion of fuel elements including a fuel-containing fuel zone; and repeatedly performing a sequence of operations comprising forming a uniform graphite layer on a previous layer and applying a binder using additive manufacturing methods to bind each layer with successively decreasing diameters to form a cap portion of fuel elements. The particles may include one or more of a nuclear fuel material, burnable poison material, or breeder material. The fuel particles may be tri-structural-isotropic (TRISO) particles that do not have an overcoat.
A method of manufacturing nuclear fuel elements may include: forming a graphite base portion of the fuel element; depositing a first layer of graphite spheres on the base portion; depositing a first layer of fuel, burnable poison and/or breeder particles on the first layer of graphite spheres; forming a second layer of graphite spheres on the first layer of particles; depositing a second layer of fuel, burnable poison and/or breeder particles on the second layer of graphite spheres; and forming a graphite cap portion of the fuel element. Fuel, burnable poison and/or breeder particles of the first layer may be are spaced apart by substantially the same distance, and fuel, burnable poison and/or breeder particles of the second layer may be spaced apart by substantially the same distance. The fuel element may be a spherical fuel pebble. The fuel particles may be tri-structural-isotropic (TRISO) particles without an overcoat.
A method of manufacturing nuclear fuel elements may include: forming a graphite base of the fuel element; depositing a first layer of graphite and/or graphite spheres on the base portion; depositing a first layer of fuel, burnable poison and/or breeder particles on the first layer of graphite and/or graphite spheres; forming a second layer of graphite and/or graphite spheres on the first layer of particles; depositing a second layer of fuel, burnable poison and/or breeder particles on the second layer of graphite and/or graphite spheres; and forming a graphite cap portion of the fuel element. Adjacent fuel, burnable poison and/or breeder particles of the first layer are spaced apart by substantially the same distance, and adjacent fuel, burnable poison and/or breeder particles of the second layer are spaced apart by substantially the same distance. Fuel elements may be spherical fuel pebbles. Fuel particles may be tri-structural-isotropic particles without an overcoat.
