ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Luloff, Mark Stephen
El Bouzidi, Salim
Feenstra, Paul
Abstract
An electromagnetic shaker apparatus includes a body, and a magnetic device housed within the body and configured to provide a static magnetic field. The apparatus further includes an armature, and a solenoid coil mounted on the armature and configured to receive current from a power supply. Interaction between the static magnetic field and the solenoid coil can generate a Lorentz force that causes movement of the armature relative to the body. The apparatus can withstand high temperatures and/or pressures and/or chemical conditions, and can be used in a fretting wear system in testing environments.
H01F 7/08 - ElectromagnetsActuators including electromagnets with armatures
B06B 1/04 - Processes or apparatus for generating mechanical vibrations of infrasonic, sonic or ultrasonic frequency making use of electrical energy operating with electromagnetism
G01N 3/02 - Investigating strength properties of solid materials by application of mechanical stress Details
ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Smith, Jared
Nordin, Heidi
Turnbull, Joseph
Hanlon, Sean
Mccaugherty, Kevin
Wright, Michael David
Read, Scott
Prudil, Andrew
Abstract
An end fitting for a pressure tube in a nuclear reactor system includes an inboard end configured to surround and be joined to the end of the pressure tube in a fluid tight manner by a rolled joint. The rolled joint includes a grooved region having at least one annular groove. The end fitting also incudes a wettable inner surface that extends axially outboard from an outboard-most annular groove of the grooved region. The end fitting also incudes a corrosion barrier applied to form a coated portion of the wettable inner surface. The coated portion extends from a first position that is at or outboard of a coating reference position at the outside edge of the outboard-most annular groove, to a second position. An axial extent of the coated portion, measured axially from the coating reference position to the second position, is at least about 20 mm.
G21C 13/067 - Sealing-plugs for tubes, e.g. standpipesLocking devices for plugs
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
3.
Use of a Checkpoint Inhibitor in Combination with Ultralow Dose Whole Body Irradiation
ATOMIC ENERGY OF CANADA LIMITED/ÈNERGIE ATOMIQUE DU CANADA LIMITÈE (Canada)
Inventor
Wang, Yi
Bugden, Michelle
Bannister, Laura
Klokov, Dmitry
Abstract
The present invention relates to a method to improve the anti-tumour effects of immune checkpoint therapy by combining the use of a checkpoint inhibitor with ultralow dose whole body irradiation. The present invention enhances the anti-tumour effects of immune checkpoint therapy by reducing tumour volume as well as shortening the response time of the immune checkpoint therapy, as compared to immune checkpoint therapy on its own.
C07K 16/28 - Immunoglobulins, e.g. monoclonal or polyclonal antibodies against material from animals or humans against receptors, cell surface antigens or cell surface determinants
A61K 39/00 - Medicinal preparations containing antigens or antibodies
ATOMIC ENERGY OF CANADA LIMITED/ÈNERGIE ATOMIQUE DU CANADA LIMITÈE (Canada)
Inventor
Cota-Sanchez, German
Abstract
A nuclear fuel element for use in a nuclear reactor may include a plurality of metal fuel sheaths extending along a longitudinal fuel element axis and spaced apart from each other, the plurality of fuel sheaths comprising a first fuel sheath having an inner surface, an opposing outer surface and a hollow interior configured to receive nuclear fuel material. A carbon coating may be on the inner surface of the first fuel sheath. The carbon coating may include more than 99.0% wt of a carbon material including more than 20% wt of carbon nanotubes and less than about 0.01% wt of organic contaminants.
G21C 3/07 - CasingsJackets characterised by their material, e.g. alloys
G21C 3/17 - Means for storage or immobilisation of gases in fuel elements
G21C 3/20 - Details of the construction within the casing with coating on fuel or on inside of casingDetails of the construction within the casing with non-active interlayer between casing and active material
5.
PORTABLE SYSTEM FOR MONITORING AIRBORNE RADIONUCLIDES
ATOMIC ENERGY OF CANADA LIMITED/ ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Lebel, Luke
Clouthier, Anthony
Dickson, Raymond
Abstract
A portable system for measuring airborne radionuclides from a target environment can include a primary gas flowpath including a cartridge dock. At least a first filter cartridge may be connectable to the cartridge dock and may include a cartridge gas inlet sealingly connectable to the sample supply port, a cartridge gas outlet sealingly connectable to the exhaust port; and a cartridge flowpath extending therebetween. The cartridge can include first and second filter chambers housing first and second filters. A gamma detector apparatus may be positionable adjacent the first filter cartridge when the first filter cartridge is connected to the cartridge dock and is configured to detect radiation emitted from the first filter and to detect radiation emitted from the second filter, and to generate a sensor output signal in based on the detected radiation.
ATOMIC ENERGY OF CANADA LIMITED/ ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Korolevych, Volodymyr
Festarini, Dan
Vu, Kim
Grand-Maitre, David
Lebel, Luke
Abstract
A flow-though system and method are provided for measuring radionuclides in an aqueous solution. The method includes: continuously directing a source stream of an aqueous solution into a combined stream; continuously directing a concentrate stream exiting a concentration loop into the combined stream, and wherein the concentration loop comprises a detection portion; continuously directing the combined stream into a reverse osmosis unit and separating the combined stream using the reverse osmosis unit to output the concentrate stream and a filtrate stream; continuously directing the concentrate stream exiting the reverse osmosis unit into the concentration loop to be recirculated into the combined stream upon exiting the concentration loop; and obtaining a measurement of the radionuclides at the detection portion using a spectrometer.
Atomic Energy Of Canada Limited / Énergie Atomique Du Canada Limitée (Canada)
Inventor
Chaudhuri, Ankur
Li, Liqian
Johnston, James
Cusick, Martin-Lee
Abstract
An apparatus for and a method of analyzing a sample. A laser section may include a laser arranged to direct a laser beam in a first direction towards the sample. The laser beam ablating and ionizing at least a portion of the sample to generate ions. An ion source section may include a sample holder for holding the sample. At least one component is arranged to apply an electric field for extracting at least a portion of the ions to form an ion beam traveling in a second direction. A time-of-flight section may include a detector arranged to receive the ion beam.
ATOMIC ENERGY OF CANADA LIMITED/ ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Perron, Randy
Abstract
Disclosed herein are methods for producing a radium or barium target. The methods include providing an organic-aqueous electrolyte bath solution comprising radium or barium ions, exposing a deposition surface of a target substrate to the electrolyte bath solution, wherein the target substrate comprises at least one of copper and aluminum, and wherein the deposition surface comprises at least one of copper, aluminum, gold, platinum, rhodium or silver, and applying an electric potential between an anode and the target substrate for a deposition cycle time, thereby electrodepositing a layer of radium or barium containing material out of the bath solution and onto the deposition surface. Also disclosed are targets for subsequent exposure to an accelerated proton beam.
ATOMIC ENERGY OF CANADA LIMITED/ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Chin, Yu-Shan
Clouthier, Anthony
Liang, Zhe
Gardner, Lee
Murphy, Joshua
Abstract
A hydrogen fusible link may include a first link member having a thermally conductive material, and reaction region and a bonding region. A bonding material may be in a solid state at an operating temperature and may have a melting temperature that is greater than the operating temperature. A catalyst material may coat the reaction region and may facilitate an exothermic chemical reaction when exposed to gaseous hydrogen to produce heat, wherein heat produced by the catalyst material is conducted to the bonding region via the body to heat up the bonding material. When the catalyst material is exposed to a concentration of gaseous hydrogen that is at or above an activation concentration the reaction region produces sufficient heat to raise at least some of the bonding material above the melting temperature thereby failing at least some of the bonding material.
ATOMIC ENERGY OF CANADA LIMITED/ÈNERGIE ATOMIQUE DU CANADA LIMITÈE (Canada)
Inventor
Klokov, Dmitry
Sebastian, Soji
Le, Yevgeniya
Abstract
In one aspect, a method of preconditioning stem cells comprising exposing stem cells to low dose radiation (LDR) is provided. In another aspect, a population of preconditioned stem cells is provided, wherein the population of 5 preconditioned stem cells is obtained by exposing stem cells to LDR. Uses of the preconditioned stem cells are also provided. In other aspects, the stem cells are muscle stem cells.
ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Guérin, Nicolas
Abstract
Methods of determining actinium-225 in a human urine sample can be used to establish the effective dose received by persons working with or otherwise exposed to this isotope. The human urine sample can be prepared to produce a pre-concentrated sample, which can include co-precipitating Ac and separating a first precipitate. At least some organic matter can be broken down in the pre- concentrated sample to produce a decomposed sample, which can include adding an oxidative agent to the pre-concentrated sample. The decomposed sample can be purified to produce a measurement sample, which can include passing the decomposed sample through a purification media and eluting actinium from the purification media.
ATOMIC ENERGY OF CANADA LIMITED/ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Luloff, Mark Stephen
Zaugg, Torin
Hogg, Stephen
Lei, Jia
Abstract
A non-destructive method for determining at least one of a cover depth and a cross-sectional area of at least a first ferrous rebar that is within a non-magnetic can include the steps of: a) establishing an electromagnetic circuit comprising the first ferrous rebar, a electromagnetic coupler, a first transmitter and a first receiver; b) introducing a first pulsed electromagnetic interrogation signal along the electromagnetic circuit; c) receiving a response electromagnetic signal having first magnitude that is induced in the first ferrous rebar and generating a corresponding response electrical signal; d) determining at least one of the cover depth and the cross-sectional area of the first ferrous rebar based on time information and the voltage information and generate a corresponding first output signal using a response signal processor; e) providing a first user output based on the output signal using a user output module.
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
G01N 17/00 - Investigating resistance of materials to the weather, to corrosion or to light
G01B 7/26 - Measuring arrangements characterised by the use of electric or magnetic techniques for measuring depth
G01B 7/12 - Measuring arrangements characterised by the use of electric or magnetic techniques for measuring diameters
13.
METHOD AND APPARATUS FOR DETECTING ALPHA PARTICLES IN A SAMPLE CONTAINING SAMPLE MEDIA AND WATER
ATOMIC ENERGY OF CANADA LIMITED/ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Simpson, Nicholas
Li, Emily
Harris, Tim
Cadieux, Daniel
Yue, Shuwei
Leblond, Guy
Li, Liqian
Bentoumi, Ghaouti
Cudmore, Stephen
Abstract
A method of detecting alpha particles may include providing a layer of a scintillating slurry comprising a granular scintillating material in water onto a measurement surface of a sample; positioning the sample having the scintillating slurry within a detection chamber of detection apparatus; detecting photons produced by the granular scintillating material in the scintillating slurry when the granular scintillating material is excited by ionizing alpha radiation emitted by alpha particles within the sample using a photon detector and generating a corresponding output signal; and removing the sample and the scintillating slurry from the detection chamber.
ATOMIC ENERGY OF CANADA LIMITED/ ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
EXPANDER ENERGY INC. (Canada)
Inventor
Kresnyak, Steve
Crawford, Gord
Suppiah, Sellathurai
Zuniga, Adrian Vega
Gomez, Adriana Gaona
Abstract
22222222, and producing at least an FT product stream that comprises synthetic hydrocarbons by reacting the hydrogen rich syngas in a Fischer-Tropsch (FT) reactor. Processes for reducing methane and soot content during production of an enhanced hydrogen rich syngas are also disclosed.
ATOMIC ENERGY OF CANADA LIMITED/ ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Luloff, Mark Stephen
Zaugg, Torin
Hogg, Stephen
Lei, Jai
Abstract
A method for monitoring a first attribute of a target object within a non-magnetic structure using a first probe coupled to the non-magnetic structure and located proximate the target object at a first detection region, the method includes a) introducing, at the first detection region, a pulsed electromagnetic interrogation signal along the electromagnetic circuit and through the target object using a first transmitter; b) receiving, at the first detection region, a response electromagnetic signal that is induced in the target object and generating a corresponding response electrical signal comprising time information and voltage information using a first receiver; c) determining the first attribute of the target object at the first detection region; d) generating a corresponding first output signal; and e) comparing one of the first output signal and the first attribute, to a stored value for the first detection region to determine if a condition is met.
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
G01N 27/904 - 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 with two or more sensors
Atomic Energy of Canada Limited / Énergie Atomique du Canada Limitée (Canada)
Inventor
Kamaev, Oleg
Rand, Evan T.
Valente, Andrew
Bhullar, Amanjot
Abstract
A method of detecting a material with a high atomic number, including positioning a test object in a muon detection apparatus; gathering a set of test data; reconstructing a set of test muon tracks; identifying a set of outlier muon tracks having large scattering events; identifying an outlier spatial domain region; determining outlier region scattering density estimates; determining if the outlier region scattering density estimates are indicative of the presence of the material with the high atomic number; generating a detector notification, when the outlier region scattering density estimates are indicative of the presence of the material with the high atomic number; and providing the detector notification to a user. A system for detecting a material with a high atomic number may include a muon detection apparatus and a processing system communicatively coupled to the muon detection apparatus and including at least one processor operable to generate a detector notification.
ATOMIC ENERGY OF CANADA LIMITED/ ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Lebel, Luke
Clouthier, Anthony
Dickson, Raymond
Abstract
A portable system for measuring airborne radionuclides from a target environment can include a primary gas flowpath including a cartridge dock. At least a first filter cartridge may be connectable to the cartridge dock and may include a cartridge gas inlet sealingly connectable to the sample supply port, a cartridge gas outlet sealingly connectable to the exhaust port; and a cartridge flowpath extending therebetween. The cartridge can include first and second filter chambers housing first and second filters. A gamma detector apparatus may be positionable adjacent the first filter cartridge when the first filter cartridge is connected to the cartridge dock and is configured to detect radiation emitted from the first filter and to detect radiation emitted from the second filter, and to generate a sensor output signal in based on the detected radiation.
ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Chaudhuri, Ankur
Li, Liqian
Johnston, James
Cusick, Martin-Lee
Abstract
An apparatus for and a method of analyzing a sample. A laser section may include a laser arranged to direct a laser beam in a first direction towards the sample. The laser beam ablating and ionizing at least a portion of the sample to generate ions. An ion source section may include a sample holder for holding the sample. At least one component is arranged to apply an electric field for extracting at least a portion of the ions to form an ion beam traveling in a second direction. A time-of-flight section may include a detector arranged to receive the ion beam.
ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Chin, Yu-Shan
Clouthier, Anthony
Liang, Zhe
Gardner, Lee
Murphy, Joshua
Abstract
A hydrogen fusible link may include a first link member having a thermally conductive material, and reaction region and a bonding region. A bonding material may be in a solid state at an operating temperature and may have a melting temperature that is greater than the operating temperature. A catalyst material may coat the reaction region and may facilitate an exothermic chemical reaction when exposed to gaseous hydrogen to produce heat, wherein heat produced by the catalyst material is conducted to the bonding region via the body to heat up the bonding material. When the catalyst material is exposed to a concentration of gaseous hydrogen that is at or above an activation concentration the reaction region produces sufficient heat to raise at least some of the bonding material above the melting temperature thereby failing at least some of the bonding material.
ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Luloff, Mark Stephen
Zaugg, Torin
Hogg, Stephen
Lei, Jia
Abstract
A non-destructive method for determining at least one of a cover depth and a cross-sectional area of at least a first ferrous rebar that is within a non-magnetic can include the steps of: a) establishing an electromagnetic circuit comprising the first ferrous rebar, a electromagnetic coupler, a first transmitter and a first receiver; b) introducing a first pulsed electromagnetic interrogation signal along the electromagnetic circuit; c) receiving a response electromagnetic signal having first magnitude that is induced in the first ferrous rebar and generating a corresponding response electrical signal; d) determining at least one of the cover depth and the cross-sectional area of the first ferrous rebar based on time information and the voltage information and generate a corresponding first output signal using a response signal processor; e) providing a first user output based on the output signal using a user output module.
ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Kamaev, Oleg
Rand, Evan T.
Valente, Andrew
Bhullar, Amanjot
Abstract
A method of detecting a material with a high atomic number, including positioning a test object in a muon detection apparatus; gathering a set of test data; reconstructing a set of test muon tracks; identifying a set of outlier muon tracks having large scattering events; identifying an outlier spatial domain region; determining outlier region scattering density estimates; determining if the outlier region scattering density estimates are indicative of the presence of the material with the high atomic number; generating a detector notification, when the outlier region scattering density estimates are indicative of the presence of the material with the high atomic number; and providing the detector notification to a user. A system for detecting a material with a high atomic number may include a muon detection apparatus and a processing system communicatively coupled to the muon detection apparatus and including at least one processor operable to generate a detector notification.
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 diffraction of the radiation by the materials, e.g. for investigating crystal structureInvestigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups , or by using scattering of the radiation by the materials, e.g. for investigating non-crystalline materialsInvestigating 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
22.
Single walled carbon nanotube-based slurry for improved nuclear fuel cladding coatings and method of fabrication of same
ATOMIC ENERGY OF CANADA LIMITED/ÈNERGIE ATOMIQUE DU CANADA LIMITÈE (Canada)
Inventor
Cota-Sanchez, German
Abstract
A nuclear fuel element for use in a nuclear reactor may include a plurality of metal fuel sheaths extending along a longitudinal fuel element axis and spaced apart from each other, the plurality of fuel sheaths comprising a first fuel sheath having an inner surface, an opposing outer surface and a hollow interior configured to receive nuclear fuel material. A carbon coating may be on the inner surface of the first fuel sheath. The carbon coating may include more than 99.0% wt of a carbon material including more than 20% wt of carbon nanotubes and less than about 0.01% wt of organic contaminants.
G21C 3/07 - CasingsJackets characterised by their material, e.g. alloys
G21C 3/17 - Means for storage or immobilisation of gases in fuel elements
G21C 3/20 - Details of the construction within the casing with coating on fuel or on inside of casingDetails of the construction within the casing with non-active interlayer between casing and active material
23.
CONTINUOUS WAVE ULTRASOUND OR ACOUSTIC NON-DESTRUCTIVE TESTING
ATOMIC ENERGY OF CANADA LIMITED/ÈNERGIE ATOMIQUE DU CANADA LIMITÈE (Canada)
Inventor
Stoev, Krassimir
Craig, Stuart
Sawadogo, Teguewinde
Abstract
A method of determining a distance to a discontinuity within an object may include the steps of: a) generating a continuous, frequency modulated input signal having a predetermined frequency range and a frequency ramping speed using a signal generator and splitting the input signal into at least a test signal and a reference signal; b) generating an input sound wave based on the test signal and continuously introducing the input sound wave into the object using a transmitter and simultaneously receiving a reflected sound wave reflected by a discontinuity within the object and generating a corresponding return signal using a receiver; c) determining a frequency difference value based on a comparison of the reference signal and the return signal using a controller; and d) automatically determining a distance from the transmitter to the discontinuity within the object based on at least the frequency difference value and the frequency ramping speed.
G01S 13/32 - Systems for measuring distance only using transmission of continuous waves, whether amplitude-, frequency-, or phase-modulated, or unmodulated
G01N 29/34 - Generating the ultrasonic, sonic or infrasonic waves
ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Simpson, Nicholas
Li, Emily
Harris, Tim
Cadieux, Daniel
Yue, Shuwei
Leblond, Guy
Li, Liqian
Bentoumi, Ghaouti
Cudmore, Stephen
Abstract
A method of detecting alpha particles may include providing a layer of a scintillating slurry comprising a granular scintillating material in water onto a measurement surface of a sample; positioning the sample having the scintillating slurry within a detection chamber of detection apparatus; detecting photons produced by the granular scintillating material in the scintillating slurry when the granular scintillating material is excited by ionizing alpha radiation emitted by alpha particles within the sample using a photon detector and generating a corresponding output signal; and removing the sample and the scintillating slurry from the detection chamber.
Atomic Energy Of Canada Limited / Énergie Atomique Du Canada Limitée (Canada)
Inventor
Van Der Ende, Bryan
Sur, Bhaskar
Abstract
A system for monitoring fissile material contents inside of a nuclear reactor can include at least a first neutron detector positioned outside a radiation shield and configured to detect a plurality of neutrons originating from the reactor core and having passed through the radiation shield, and configured to generate a first output signal, and a controller communicably linked to the first neutron detector to receive the first output signal and a power output of the nuclear reactor.
G21C 17/10 - Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
ATOMIC ENERGY OF CANADA LIMITED/ÈNERGIE ATOMIQUE DU CANADA LIMITÈE (Canada)
Inventor
Wang, Yi
Bugden, Michelle
Bannister, Laura
Klokov, Dmitry
Abstract
The present invention relates to a method to improve the anti-tumour effects of immune checkpoint therapy by combining the use of a checkpoint inhibitor with ultralow dose whole body irradiation. The present invention enhances the anti-tumour effects of immune checkpoint therapy by reducing tumour volume as well as shortening the response time of the immune checkpoint therapy, as compared to immune checkpoint therapy on its own.
C07K 16/28 - Immunoglobulins, e.g. monoclonal or polyclonal antibodies against material from animals or humans against receptors, cell surface antigens or cell surface determinants
Atomic Energy of Canada Limited / Énergie Atomique du Canada Limitèe (Canada)
Inventor
Fong, Randy W. L.
Patrick, James
Gale, Michael
Abstract
A hydrogen storage assembly includes at least one wafer formed of a substrate material that produces metal hydride when exposed to a hydrogen-rich carrier fluid. The wafer can be supported by a housing and arranged so that the hydrogen-rich carrier fluid can flow over a reaction surface of the wafer. At least one heating element can be arranged to transfer heat to the wafer to attain an operating temperature suitable for hydrogen charging on the reaction surface. A de-activation material may be provided on the reaction surface for inhibiting formation of surface oxide that impedes hydrogen absorption during charging and hydrogen desorption during discharging. The at least one wafer can include a plurality of monolithic plate wafers spaced apart about a central axis of the assembly. The at least one wafer can include a plurality of monolithic disc wafers in at least one stacked arrangement.
ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Hanlon, Sean
Mccaugherty, Kevin
Read, Scott
Cheung, Daniel S.F.
Abstract
A method of removing hydrogen interstitially dissolved within an object can include: positioning a sorption pad having a contact surface and comprising a sorptive material; urging the contact surface into metallurgical contact with the first target surface while at a treatment temperature that is greater than about 200 degrees Celsius; c) maintaining the metallurgical contact for a treatment period during which the hydrogen migrates from the target object to the sorptive material; and at the conclusion of the treatment period, separating the contact surface from the first target surface and moving the sorption pad and any hydrogen sequestered therein away from the object.
ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
King, James Mitchell
Abstract
The present disclosure relates to a radiation detection vehicle with a directional radiation detection system. The radiation detection vehicle may include a body, a motor supported by the body and configured to propel the vehicle, at least a first power source connectable to the body and configured to provide power to the vehicle, and a directional radiation detection system supported by the body. The directional radiation detection system may include a radiation detector configured to detect incident radiation and a directional shielding assembly configured to partially shield the radiation detector by preventing a portion of the incident radiation originating from a first incident direction from reaching the radiation detector, the directional shielding assembly including the first power source.
ATOMIC ENERGY OF CANADA LIMITED/ENERGIE ATOMIQUE DU CANADA LIMITÈE (Canada)
Inventor
Klokov, Dmitry
Sebastian, Soji
Le, Yevgeniya
Abstract
In one aspect, a method of preconditioning stem cells comprising exposing stem cells to low dose radiation (LDR) is provided. In another aspect, a population of preconditioned stem cells is provided, wherein the population of 5 preconditioned stem cells is obtained by exposing stem cells to LDR. Uses of the preconditioned stem cells are also provided. In other aspects, the stem cells are muscle stem cells.
Atomic Energy of Canada Limited / Énergie Atomique du Canada Limitée (Canada)
Inventor
Mcrae, Glenn Aldon
Coleman, Christopher Edward
St. Louis, Curtis John
Langille, Scott Thomas
Corrigall, James Leigh Mclean
Nordin, Heidi Marie
Hanlon, Sean Michael Kevin
Read, Scott Anthony Douglas
Mccaugherty, Kevin William
Abstract
An article formed of a metal alloy is covered at least partially with a metal hydride and a shell metal to form an assembly. Load is applied to the assembly and the assembly is heated. The shell metal deforms around the article and the metal hydride and forms a gas proof seal. The metal hydride thermally decomposes to form hydrogen gas. At least a portion of the hydrogen gas dissociates and moves as monoatomic hydrogen into the article. The metal alloy can be a zirconium metal alloy, the metal hydride can be a zirconium metal hydride, and the shell metal can be substantially copper.
C23C 8/62 - Solid state diffusion of only non-metal elements into metallic material surfacesChemical 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 solids, e.g. powders, pastes only one element being applied
C21D 9/08 - Heat treatment, e.g. annealing, hardening, quenching or tempering, adapted for particular articlesFurnaces therefor for tubular bodies or pipes
C21D 9/46 - Heat treatment, e.g. annealing, hardening, quenching or tempering, adapted for particular articlesFurnaces therefor for sheet metals
C22C 27/00 - Alloys based on rhenium or a refractory metal not mentioned in groups or
C23C 8/08 - Solid state diffusion of only non-metal elements into metallic material surfacesChemical 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
ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Stoev, Krassimir
Craig, Stuart
Sawadogo, Teguewinde
Abstract
A method of determining a distance to a discontinuity within an object may include the steps of: a) generating a continuous, frequency modulated input signal having a predetermined frequency range and a frequency ramping speed using a signal generator and splitting the input signal into at least a test signal and a reference signal; b) generating an input sound wave based on the test signal and continuously introducing the input sound wave into the object using a transmitter and simultaneously receiving a reflected sound wave reflected by a discontinuity within the object and generating a corresponding return signal using a receiver; c) determining a frequency difference value based on a comparison of the reference signal and the return signal using a controller; and d) automatically determining a distance from the transmitter to the discontinuity within the object based on at least the frequency difference value and the frequency ramping speed.
G01S 15/32 - Systems for measuring distance only using transmission of continuous waves, whether amplitude-, frequency-, or phase-modulated, or unmodulated
G01N 29/46 - Processing the detected response signal by spectral analysis, e.g. Fourier analysis
G01S 15/88 - Sonar systems specially adapted for specific applications
33.
USE OF A CHECKPOINT INHIBITOR IN COMBINATION WITH ULTRALOW DOSE WHOLE BODY IRRADIATION
ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Wang, Yi
Bugden, Michelle
Bannister, Laura
Klokov, Dmitry
Abstract
The present invention relates to a method to improve the anti-tumour effects of immune checkpoint therapy by combining the use of a checkpoint inhibitor with ultralow dose whole body irradiation. The present invention enhances the anti-tumour effects of immune checkpoint therapy by reducing tumour volume as well as shortening the response time of the immune checkpoint therapy, as compared to immune checkpoint therapy on its own.
C07K 16/28 - Immunoglobulins, e.g. monoclonal or polyclonal antibodies against material from animals or humans against receptors, cell surface antigens or cell surface determinants
34.
System and method for indirectly monitoring one or more environmental conditions
Atomic Energy Of Canada Limited / Energie Atomique Du Canada Limitee (Canada)
Inventor
Liu, Yu
Li, Liqian
Collins, Karen Dawn
Nishimura, Michael
Abstract
A system for monitoring ionizing radiation in a target area, the system may include a first plurality of consumable nodes deployable within the target area to be exposed to the ionizing radiation. Each consumable node may be progressively damageable over a monitoring time as a result of exposure to the ionizing radiation. A base station may be operable to detect an amount of radiation damage sustained by the consumable nodes and to determine a dosage of ionizing radiation received by any one of the consumable nodes based on a pre-determined correlation between the dosage of ionizing radiation and the amount of radiation damage sustained by the consumable node.
Atomic Energy of Canada Limited / Énergie Atomique du Canada Limitée (Canada)
Inventor
Sur, Bhaskar
Li, Gang
Bentoumi, Ghaouti
Li, Liqian
Abstract
An apparatus for use in making localized passive measurements of electromagnetic radiation emitted from an object located in a radioactive environment includes a hollow elongate conduit having a first end, a second end, and a reflective inner surface. The first end of the conduit is positionable in the radioactive environment proximate the object, and the second end of the conduit is positionable outside the radioactive environment. The conduit has at least one bend between the first end and the second end, such that light entering the first end of the conduit is reflected by the inner surface of the conduit at least once as it travels through the conduit before reaching the second end. A detector in optical communication with the second end of the conduit is configured to detect electromagnetic radiation that reaches the second end.
G01T 1/22 - Measuring radiation intensity with Cerenkov detectors
G08C 23/04 - Non-electric signal transmission systems, e.g. optical systems using light waves, e.g. infrared
G01T 1/20 - Measuring radiation intensity with scintillation detectors
G01D 21/00 - Measuring or testing not otherwise provided for
G01T 1/178 - Circuit arrangements not adapted to a particular type of detector for measuring specific activity in the presence of other radioactive substances, e.g. natural, in the air or in liquids such as rain-water
G01T 1/204 - Measuring radiation intensity with scintillation detectors the detector being a liquid
G01T 1/208 - Circuits specially adapted for scintillation detectors, e.g. for the photo-multiplier section
ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Cota-Sanchez, German
Abstract
A nuclear fuel element for use in a nuclear reactor may include a plurality of metal fuel sheaths extending along a longitudinal fuel element axis and spaced apart from each other, the plurality of fuel sheaths comprising a first fuel sheath having an inner surface, an opposing outer surface and a hollow interior configured to receive nuclear fuel material. A carbon coating may be on the inner surface of the first fuel sheath. The carbon coating may include more than 99.0%wt of a carbon material including more than 20%wt of carbon nanotubes and less than about 0.01 %wt of organic contaminants.
G21C 3/20 - Details of the construction within the casing with coating on fuel or on inside of casingDetails of the construction within the casing with non-active interlayer between casing and active material
37.
Apparatus and method for adhering a filament to a surface
Atomic Energy Of Canada Limited / Energie Atomique Du Canada Limitee (Canada)
Inventor
Gaudet, Michel
Yetisir, Metin
Li, Wenhai
Abstract
An apparatus for adhering a filament to a surface can include a body having a filament inlet port, at least a first filament outlet port spaced apart from the filament inlet port, and at least a first filament travel path extending between the filament inlet port and the first filament outlet port. A reservoir chamber can form a portion of the first filament travel path between the filament inlet port and the first filament outlet port and can contain a viscous adhesive material. Imparting relative axial movement between the body and a first filament can urge the first filament along the first filament travel path and through the reservoir chamber so that the first filament is coated with the viscous adhesive material when exiting via the first filament outlet port, for adhesion to the surface.
G02B 6/46 - Processes or apparatus adapted for installing optical fibres or optical cables
G01D 11/00 - Component parts of measuring arrangements not specially adapted for a specific variable
G01D 5/26 - Mechanical means for transferring the output of a sensing memberMeans for converting the output of a sensing member to another variable where the form or nature of the sensing member does not constrain the means for convertingTransducers not specially adapted for a specific variable using optical means, i.e. using infrared, visible or ultraviolet light
Atomic Energy of Canada Limited/ Energie Atomique Du Canada Limitess (Canada)
Inventor
Horn, Dag
Stoev, Krassimir
Abstract
A method for assaying a wall of a pressure tube for a nuclear reactor is disclosed. The wall has a matrix material and deuterium nuclei in the matrix material. The method includes: (a) transmitting gamma rays into the matrix material to induce photodisintegration of at least some of the deuterium nuclei, whereby reaction particles of the nuclei are emitted from the wall; (b) detecting at least some of the reaction particles emitted in step (a) using a particle detector; and (c) generating particle signals in response to detecting the particles in step (b).
G21C 17/017 - Inspection or maintenance of pipe-lines or tubes in nuclear installations
G01N 23/221 - Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups , or by measuring secondary emission from the material by activation 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
G01N 23/22 - Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups , or by measuring secondary emission from the material
G21G 4/04 - Radioactive sources other than neutron sources
H05G 2/00 - Apparatus or processes specially adapted for producing X-rays, not involving X-ray tubes, e.g. involving generation of a plasma
Atomic Energy Of Canada Limited / Energie Atomique Du Canada Limitee (Canada)
Inventor
Jessup, Howard
Guerout, Fabrice M.
Abstract
A surface treating apparatus for treating an inner surface of a bore containing a shaft may include a body connectable to a drive apparatus and configured to movably receive a shaft extending through a bore, and at least one surface treating member connected to and movable with the body relative to the shaft, the at least one surface treating member sized to be inserted within an annular gap formed between the shaft and an inner surface of the bore and to bear against the inner surface of the bore when the shaft is received by the body.
B24B 33/02 - Honing machines or devicesAccessories therefor designed for working internal surfaces of revolution, e.g. of cylindrical or conical shapes
ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Klokov, Dmitry
Sebastian, Soji
Le, Yevgeniya
Abstract
In one aspect, a method of preconditioning stem cells comprising exposing stem cells to low dose radiation (LDR) is provided. In another aspect, a population of preconditioned stem cells is provided, wherein the population of 5 preconditioned stem cells is obtained by exposing stem cells to LDR. Uses of the preconditioned stem cells are also provided. In other aspects, the stem cells are muscle stem cells.
ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Mcrae, Glenn, Aldon
Coleman, Christopher, Edward
St. Louis, Curtis, John
Langille, Scott, Thomas
Corrigall, James, Leigh, Mclean
Nordin, Heidi, Marie
Hanlon, Sean, Michael, Kevin
Read, Scott, Anthony, Douglas
Mccaugherty, Kevin, William
Abstract
An article formed of a metal alloy is covered at least partially with a metal hydride and a shell metal to form an assembly. Load is applied to the assembly and the assembly is heated. The shell metal deforms around the article and the metal hydride and forms a gas proof seal. The metal hydride thermally decomposes to form hydrogen gas. At least a portion of the hydrogen gas dissociates and moves as monoatomic hydrogen into the article. The metal alloy can be a zirconium metal alloy, the metal hydride can be a zirconium metal hydride, and the shell metal can be substantially copper.
C23C 8/08 - Solid state diffusion of only non-metal elements into metallic material surfacesChemical 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
C01B 3/04 - Production of hydrogen or of gaseous mixtures containing hydrogen by decomposition of inorganic compounds, e.g. ammonia
C23C 8/06 - Solid state diffusion of only non-metal elements into metallic material surfacesChemical 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
ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Fong, Randy W. L.
Patrick, James
Gale, Michael
Abstract
A hydrogen storage assembly includes at least one wafer formed of a substrate material that produces metal hydride when exposed to a hydrogen-rich carrier fluid. The wafer can be supported by a housing and arranged so that the hydrogen-rich carrier fluid can flow over a reaction surface of the wafer. At least one heating element can be arranged to transfer heat to the wafer to attain an operating temperature suitable for hydrogen charging on the reaction surface. A de-activation material may be provided on the reaction surface for inhibiting formation of surface oxide that impedes hydrogen absorption during charging and hydrogen desorption during discharging. The at least one wafer can include a plurality of monolithic plate wafers spaced apart about a central axis of the assembly. The at least one wafer can include a plurality of monolithic disc wafers in at least one stacked arrangement.
Atomic Energy Of Canada Limited / Energie Atomique Du Canada Limitee (Canada)
Inventor
Van Der Ende, Bryan
Sur, Bhaskar
Abstract
A system for monitoring fissile material contents inside of a nuclear reactor can include at least a first neutron detector positioned outside a radiation shield and configured to detect a plurality of neutrons originating from the reactor core and having passed through the radiation shield, and configured to generate a first output signal, and a controller communicably linked to the first neutron detector to receive the first output signal and a power output of the nuclear reactor.
G21C 17/10 - Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
ATOMIC ENERGY OF CANADA LIMITED/ ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Khumsa-Ang, Kittima
Turner, Carl W.
Qian, Jing
Abstract
A method of preparing magnetite particles may include providing a first solution of substantially ferrous sulphate. The first solution may be converted by replacing sulphate ions with chloride ions to produce a second solution of substantially ferrous chloride. The second solution may be oxidized to produce a third solution of substantially iron oxide. A system for purifying a solution of substantially iron oxide may include a solution reservoir, at least one membrane unit, and at least one pump for circulating the solution between the solution reservoir and the membrane unit. The solution may be delivered from the solution reservoir to an inlet of the membrane unit, and/or the solution may be returned from an outlet of the membrane unit to the solution reservoir.
G21H 5/02 - Applications of radiation from radioactive sources or arrangements therefor, not otherwise provided for as tracers
G21G 1/00 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes
45.
Fuel channel assembly and fuel bundle for a nuclear reactor
Atomic Energy of Canada Limited / Energie Atomique Du Canada Limitee (Canada)
Inventor
Pencer, Jeremy
Bromley, Blair
Nava-Dominguez, Armando
Abstract
A fuel assembly for a pressure-tube nuclear reactor includes a fuel channel assembly. The fuel channel assembly has an outer conduit and an inner conduit received within the outer conduit. The conduits define an annular fuel bundle chamber for receiving a flow of a coolant in one direction. The inner conduit includes a central flow passage for receiving a flow of the coolant in an opposite direction. A fuel bundle positioned within the fuel bundle chamber consists of fuel elements arranged to form an inner ring surrounding the inner conduit, and an outer ring surrounding the inner ring. The coolant may be light water, and geometries of the fuel assembly may be selected so moderation by the volume of coolant promotes generally uniform power distribution in the fuel elements.
G21C 3/328 - Relative disposition of the elements in the bundle lattice
G21C 3/322 - Means to influence the coolant flow through or around the bundles
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 15/06 - 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 from fissile or breeder material in fuel elements
G21C 5/12 - Moderator or core structureSelection of materials for use as moderator characterised by composition, e.g. the moderator containing additional substances which ensure improved heat resistance of the moderator
Atomic Energy of Canada Limited / Energie Atomique Du Canada Limitee (Canada)
Inventor
Dai, Xiongxin
Li, Liqian
Jonkmans, Guy
Ho, Aaron
Abstract
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.
ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Liu, Yu
Li, Liqian
Colins, Karen Dawn
Nishimura, Michael
Abstract
A system for monitoring ionizing radiation in a target area, the system may include a first plurality of consumable nodes deployable within the target area to be exposed to the ionizing radiation. Each consumable node may be progressively damageable over a monitoring time as a result of exposure to the ionizing radiation. A base station may be operable to detect an amount of radiation damage sustained by the consumable nodes and to determine a dosage of ionizing radiation received by any one of the consumable nodes based on a pre- determined correlation between the dosage of ionizing radiation and the amount of radiation damage sustained by the consumable node.
ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Stevenson, Mathew
Guerout, Fabrice
Boor, Rick
Abstract
A packing assembly for a valve includes a first segment having at least one first guiding surface, and a second segment having at least one second guiding surface in engagement with at least a portion of the at least one first guiding surface. A shape-memory member couples the first and second segments. The shape-memory member may be formed of a material that is responsive to changes in temperature, so that, in response to a change in temperature, the shape-memory member may cause relative movement of the first and second segments in a first direction. In response to the movement, the first and second guiding surfaces may cause relative displacement of the first and second segments in a second direction.
F16J 15/18 - Sealings between relatively-moving surfaces with stuffing-boxes for elastic or plastic packings
F16J 15/16 - Sealings between relatively-moving surfaces
F16K 41/04 - Spindle sealings with stuffing-box with at least one ring of rubber or like material between spindle and housing
F16K 3/24 - Gate valves or sliding valves, i.e. cut-off apparatus with closing members having a sliding movement along the seat for opening and closing with sealing faces shaped as surfaces of solids of revolution with cylindrical valve members
ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Sur, Bhaskar
Li, Gang
Bentoumi, Ghaouti
Li, Liqian
Abstract
An apparatus for use in making localized passive measurements of electromagnetic radiation emitted from an object located in a radioactive environment includes a hollow elongate conduit having a first end, a second end, and a reflective inner surface. The first end of the conduit is positionable in the radioactive environment proximate the object, and the second end of the conduit is positionable outside the radioactive environment. The conduit has at least one bend between the first end and the second end, such that light entering the first end of the conduit is reflected by the inner surface of the conduit at least once as it travels through the conduit before reaching the second end. A detector in optical communication with the second end of the conduit is configured to detect electromagnetic radiation that reaches the second end.
G01T 1/22 - Measuring radiation intensity with Cerenkov detectors
G01D 5/12 - Mechanical means for transferring the output of a sensing memberMeans for converting the output of a sensing member to another variable where the form or nature of the sensing member does not constrain the means for convertingTransducers not specially adapted for a specific variable using electric or magnetic means
G01T 1/20 - Measuring radiation intensity with scintillation detectors
G01T 1/204 - Measuring radiation intensity with scintillation detectors the detector being a liquid
G08C 23/00 - Non-electric signal transmission systems, e.g. optical systems
50.
APPARATUS AND METHOD FOR ADHERING A FILAMENT TO A SURFACE
ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Gaudet, Michel
Yetisir, Metin
Li, Wenhai
Abstract
An apparatus for adhering a filament to a surface can include a body having a filament inlet port, at least a first filament outlet port spaced apart from the filament inlet port, and at least a first filament travel path extending between the filament inlet port and the first filament outlet port. A reservoir chamber can form a portion of the first filament travel path between the filament inlet port and the first filament outlet port and can contain a viscous adhesive material. Imparting relative axial movement between the body and a first filament can urge the first filament along the first filament travel path and through the reservoir chamber so that the first filament is coated with the viscous adhesive material when exiting via the first filament outlet port, for adhesion to the surface.
Atomic Energy of Canada Limited / Energie Atomique du Canada Limitee (Canada)
Inventor
Bodner, Robert
Tyo, Jonathan
Popov, Dan
Kuran, Sermet
Abstract
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 1/20 - 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 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 5/02 - Moderator or core structureSelection 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 1/08 - 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 15/08 - 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 from moderating material
G21C 15/20 - Partitions or thermal insulation between fuel channel and moderator, e.g. in pressure tube reactors
G21C 19/14 - 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 characterised by their adaptation for use with horizontal channels in the reactor core
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
ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Jessup, Howard
Guérout, Fabrice M.
Abstract
A surface treating apparatus for treating an inner surface of a bore containing a shaft may include a body connectable to a drive apparatus and configured to movably receive a shaft extending through a bore, and at least one surface treating member connected to and movable with the body relative to the shaft, the at least one surface treating member sized to be inserted within an annular gap formed between the shaft and an inner surface of the bore and to bear against the inner surface of the bore when the shaft is received by the body.
B24B 33/02 - Honing machines or devicesAccessories therefor designed for working internal surfaces of revolution, e.g. of cylindrical or conical shapes
ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Fong, Randy W.L.
Patrick, James
Gale, Michael
Abstract
A hydrogen storage assembly includes at least one wafer formed of a substrate material that produces metal hydride when exposed to a hydrogen-rich carrier fluid. The wafer can be supported by a housing and arranged so that the hydrogen-rich carrier fluid can flow over a reaction surface of the wafer. At least one heating element can be arranged to transfer heat to the wafer to attain an operating temperature suitable for hydrogen charging on the reaction surface. A de-activation material may be provided on the reaction surface for inhibiting formation of surface oxide that impedes hydrogen absorption during charging and hydrogen desorption during discharging. The at least one wafer can include a plurality of monolithic plate wafers spaced apart about a central axis of the assembly. The at least one wafer can include a plurality of monolithic disc wafers in at least one stacked arrangement.
C01B 3/00 - HydrogenGaseous mixtures containing hydrogenSeparation of hydrogen from mixtures containing itPurification of hydrogen
B01J 20/02 - Solid sorbent compositions or filter aid compositionsSorbents for chromatographyProcesses for preparing, regenerating or reactivating thereof comprising inorganic material
C01B 6/00 - Hydrides of metalsMonoborane or diboraneAddition complexes thereof
C01B 3/56 - Separation of hydrogen or hydrogen containing gases from gaseous mixtures, e.g. purification by contacting with solidsRegeneration of used solids
54.
PREPARATION OF MAGNETITE FROM FERROUS CHLORIDE SUBSEQUENT TO SULPHATE REMOVAL BY ION-EXCHANGE
ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Khumsa-Ang, Kittima
Turner, Carl W.
Qian, Jing
Abstract
A method of preparing magnetite particles may include providing a first solution of substantially ferrous sulphate. The first solution may be converted by replacing sulphate ions with chloride ions to produce a second solution of substantially ferrous chloride. The second solution may be oxidized to produce a third solution of substantially iron oxide. A system for purifying a solution of substantially iron oxide may include a solution reservoir, at least one membrane unit, and at least one pump for circulating the solution between the solution reservoir and the membrane unit. The solution may be delivered from the solution reservoir to an inlet of the membrane unit, and/or the solution may be returned from an outlet of the membrane unit to the solution reservoir.
Atomic Energy of Canada Limited/ Énergie Atomique du Canada Limitée (Canada)
Inventor
Dai, Xiongxin
Li, Liqian
Jonkmans, Guy
Ho, Aaron
Abstract
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.
ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Nitheanandan, Thambiayah
Abstract
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 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
ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
King, James M.
Kittmer, Andrew B.
Schaubel, Terry J.
Abstract
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.
Atomic Energy of Canada Limited / Énergie Atomique Du Canada Limitée (Canada)
Inventor
Sur, Bhaskar
Rodrigo, Lakshman
Didsbury, Richard
Abstract
− decay and at least a portion of the 3He gas escapes from the heavy water and mixes with the cover gas, d) extracting an outlet gas stream, the outlet gas stream comprising a mixture of the cover gas and the 3He gas and e) separating the 3He gas from the outlet gas stream.
G21C 23/00 - Adaptations of reactors to facilitate experimentation or irradiation
G21G 1/02 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
G21G 1/00 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes
ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Stevenson, Mathew
Guerout, Fabrice
Boor, Rick
Abstract
A packing assembly for a valve includes a first segment having at least one first guiding surface, and a second segment having at least one second guiding surface in engagement with at least a portion of the at least one first guiding surface. A shape-memory member couples the first and second segments. The shape-memory member may be formed of a material that is responsive to changes in temperature, so that, in response to a change in temperature, the shape-memory member may cause relative movement of the first and second segments in a first direction. In response to the movement, the first and second guiding surfaces may cause relative displacement of the first and second segments in a second direction.
F16J 15/18 - Sealings between relatively-moving surfaces with stuffing-boxes for elastic or plastic packings
F16K 3/00 - Gate valves or sliding valves, i.e. cut-off apparatus with closing members having a sliding movement along the seat for opening and closing
60.
NICKEL-CHROMIUM-IRON ALLOYS WITH IMPROVED RESISTANCE TO STRESS CORROSION CRACKING IN NUCLEAR ENVIRONMENTS
ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Tapping, Robert L.
Staehle, Roger W.
Arioka, Koji
Abstract
A Ni-Cr-Fe alloy with improved resistance to stress corrosion cracking in nuclear environments, the alloy comprising 23-28 wt% Cr, 25-35 wt% Ni,< 0.03 wt% C, <0.70 wt% Si, <1.0 wt% Mn, <0.015 wt% S, >0.35 wt% Ti, 0.15-0.45 wt% A1, <0.75 wt% Cu, and balance Fe and incidental impurities. The alloy may be used in steam generator tubing of a nuclear reactor. A method of producing an article includes: providing the alloy as disclosed herein; forming the alloy into the article by cold working the alloy to 20%; and heat treating the article.
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
Atomic Energy of Canada Limited / Énergie Atomique du Canada Limitée (Canada)
Inventor
Seydaliev, Marat
Dubeau, Jacques
Abstract
A method of measuring ionizing radiation may include the steps of: a) creating charged particles; b) causing the charged particles to generate the electrons; c) collecting at least a portion of the multiplied free electrons using at least two anode pads provided within the chamber, each anode pad producing a corresponding anode output signal, to provide higher sensitivity; and d) recording each anode output signal.
ATOMIC ENERGY OF CANADA LIMITED/ÉNERGY ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Hersak, Greg
Wray, Richard Wilfrid
Abstract
A regulator apparatus for distributing a fluid may include a charging valve assembly and a flow multiplier assembly. In a recharge mode, a valve of the charging valve assembly is in an open position, and the fluid is received in a second cylinder of the flow multiplier assembly, causing first and second pistons of the flow multiplier assembly to move in a first direction. In a purge mode, the valve is in the seated position, and the fluid is received in a first cylinder of the flow multiplier assembly, causing the first and second pistons to move in a second direction, and discharging an outlet flow through an outlet of the flow multiplier assembly. The second cylinder may have a bore cross sectional area that is greater than a bore cross sectional area of the first cylinder. Apparatuses disclosed herein may be implemented in a circumferential sampling tool.
F15B 3/00 - Intensifiers or fluid-pressure converters, e.g. pressure exchangersConveying pressure from one fluid system to another, without contact between the fluids
G21C 17/017 - Inspection or maintenance of pipe-lines or tubes in nuclear installations
G01N 1/08 - Devices for withdrawing samples in the solid state, e.g. by cutting involving an extracting tool, e.g. core bit
ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Clough, Malcolm James
Jackson, Austin Thomas
Dugal, Clifford John Joseph
Martin, Daniel Harry
Mcgregor, James Edward Allan
Diamond, William Thomas
Abstract
An apparatus for holding radioactive objects includes a base and a central pillar extending upwardly between a bottom end coupled to the base and a top end above the base. A plurality of inner segments are spaced around the central pillar, and a plurality of outer segments are spaced around the inner segments to form pairs. The inner segments, the outer segments and the central pillar may be coupled together to permit limited radial movement of at least one of the segments of each pair. Each pair may define a generally vertical, object-receiving channel arranged between the inner and outer segment of the pair. The segments of each pair may be adapted to bear against an object in the channel of the pair to laterally restrain the object and facilitate heat transfer from the object.
G21F 5/015 - Transportable or portable shielded containers for storing radioactive sources, e.g. source carriers for irradiation unitsRadioisotope containers
64.
PHOTOGRAPHIC METHODS OF QUANTIFICATION FOR WATER AND DEBRIS MIXTURES
ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Rhodes, David Bruce
Adams, Harry Millan
Abstract
With a water and debris mixture, a method of quantifying debris content may include obtaining at least one image of a sample of the water and debris mixture. The image may be analyzed to quantify the debris content.
ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Rhodes, David Bruce
Simister, Claire Emmalyn
Abstract
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.
ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Dai, Xiongxin
Qureshi, Junaid
Jonkmans, Guy
Abstract
A system for determining a radiation dose in real time can include at least one three- dimensional target object to be exposed to ionizing radiation. The at least one target object may include a scintillating gel material. The scintillating gel material may emit light when exposed to the ionizing radiation. An imaging system may be configured to capture at least a first image of the target object from a first position, and a second image of the target object from a second position relative to the target object. A controller may be connected to the imaging system and may be configured to the process the first and second images to provide a three-dimensional dose distribution in real-time.
ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Seydaliev, Marat
Dubeau, Jacques
Abstract
A method of measuring ionizing radiation may include the steps of: a) creating charged particles; b) causing the charged particles to generate the electrons; c) collecting at least a portion of the multiplied free electrons using at least two anode pads provided within the chamber, each anode pad producing a corresponding anode output signal, to provide higher sensitivity; and d) recording each anode output signal.
ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Clough, Malcolm James
Li, Jintong
Adams, Harry
Hampel, Randy
Briden, Neil
Munir, Naweed
Abstract
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.
A62D 3/30 - Processes for making harmful chemical substances harmless, or less harmful, by effecting a chemical change in the substances by reacting with chemical agents
F16L 55/07 - Arrangement or mounting of devices, e.g. valves, for venting or aerating or draining
F17C 13/00 - Details of vessels or of the filling or discharging of vessels
G21F 5/12 - Closures for containersSealing arrangements
ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Hersak, Greg
Wray, Richard Wilfrid
Abstract
A regulator apparatus for distributing a fluid may include a charging valve assembly and a flow multiplier assembly. In a recharge mode, a valve of the charging valve assembly is in an open position, and the fluid is received in a second cylinder of the flow multiplier assembly, causing first and second pistons of the flow multiplier assembly to move in a first direction. In a purge mode, the valve is in the seated position, and the fluid is received in a first cylinder of the flow multiplier assembly, causing the first and second pistons to move in a second direction, and discharging an outlet flow through an outlet of the flow multiplier assembly. The second cylinder may have a bore cross sectional area that is greater than a bore cross sectional area of the first cylinder. Apparatuses disclosed herein may be implemented in a circumferential sampling tool.
F15B 21/00 - Common features of fluid actuator systemsFluid-pressure actuator systems or details thereof, not covered by any other group of this subclass
ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Yetisir, Metin
Gaudet, Michel
Rhodes, David, Bruce
King, James, Mitchell
Diamond, William, T.
Li, Jintong
Abstract
A nuclear fuel bundle may include a first end face and a second end face axially spaced apart from the first end face and a plurality of elongate nuclear fuel elements supported by at least one spacer. The plurality of fuel elements and spacer being sized to be removably received within the fuel channel assembly. A coolant tube passage may extend axially through the fuel bundle between a first aperture in the first end face and a second aperture in the second end face. The coolant tube passage sized to removably receive a coolant fluid downflow tube provided in the fuel channel assembly. The tube passage extending from the first end face to the second end face to enable the coolant fluid downflow tube to pass through the fuel bundle.
ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Pencer, Jeremy
Bromley, Blair
Nava-Dominguez, Armando
Abstract
A fuel assembly for a pressure-tube nuclear reactor includes a fuel channel assembly. The fuel channel assembly has an outer conduit and an inner conduit received within the outer conduit. The conduits define an annular fuel bundle chamber for receiving a flow of a coolant in one direction. The inner conduit includes a central flow passage for receiving a flow of the coolant in an opposite direction. A fuel bundle positioned within the fuel bundle chamber consists of fuel elements arranged to form an inner ring surrounding the inner conduit, and an outer ring surrounding the inner ring. The coolant may be light water, and geometries of the fuel assembly may be selected so moderation by the volume of coolant promotes generally uniform power distribution in 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 15/06 - 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 from fissile or breeder material in fuel elements
72.
A PRESSURE-TUBE NUCLEAR REACTOR WITH A LOW PRESSURE MODERATOR AND FUEL CHANNEL ASSEMBLY
ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Yetisir, Metin
Gaudet, Michel
Rhodes, David, Bruce
King, James, Mitchell
Diamond, William, T.
Li, Jintong
Abstract
A fuel channel assembly for a nuclear reactor may include an inner conduit received within an outer conduit that has an outer upper end connectable to a coolant outlet and an outer lower end. The inner conduit may have an inner upper end connectable to a coolant source and an inner lower end axially spaced apart from the inner upper end and disposed within the outer conduit to enable coolant to circulate from the coolant source to the coolant outlet through both the inner and outer conduits. A fuel bundle chamber may be between an inner surface of the outer conduit and an outer surface of the inner conduit and may at least partially laterally surround the inner conduit. The fuel bundle chamber fluidly connecting the inner lower end and the outer upper end to enable the coolant to flow upward through the fuel bundle chamber.
G21C 15/06 - 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 from fissile or breeder material in fuel elements
G21C 1/06 - Heterogeneous reactors, i.e. in which fuel and moderator are 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 3/30 - Assemblies of a number of fuel elements in the form of a rigid unit
G21C 19/32 - Apparatus for removing radioactive objects or materials from the reactor discharge area, e.g. to a storage placeApparatus for handling radioactive objects or materials within a storage place or removing them therefrom
G21G 1/02 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
G21G 1/00 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes
G21C 23/00 - Adaptations of reactors to facilitate experimentation or irradiation
ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Clough, Malcolm James
Jackson, Austin Thomas
Dugal, Clifford John Joseph
Martin, Daniel Harry
Mcgregor, James Edward Allan
Diamond, William Thomas
Abstract
An apparatus for holding radioactive objects includes a base and a central pillar extending upwardly between a bottom end coupled to the base and a top end above the base. A plurality of inner segments are spaced around the central pillar, and a plurality of outer segments are spaced around the inner segments to form pairs. The inner segments, the outer segments and the central pillar may be coupled together to permit limited radial movement of at least one of the segments of each pair. Each pair may define a generally vertical, object- receiving channel arranged between the inner and outer segment of the pair. The segments of each pair may be adapted to bear against an object in the channel of the pair to laterally restrain the object and facilitate heat transfer from the object.
ATOMIC ENERGY OF CANADA LIMITED/ ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Dai, Xiongxin
Li, Liqian
Jonkmans, Guy
Ho, Aaron
Abstract
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.
ATOMIC ENERGY OF CANADA LIMITED/ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Diamond, William T.
Yetisir, Metin
Duffey, Romney
Leung, Laurence
Abstract
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 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
G21C 5/12 - Moderator or core structureSelection of materials for use as moderator characterised by composition, e.g. the moderator containing additional substances which ensure improved heat resistance of the moderator
G21C 13/04 - Arrangements for expansion and contraction
G21C 15/20 - Partitions or thermal insulation between fuel channel and moderator, e.g. in pressure tube reactors
ATOMIC ENERGY OF CANADA LIMITED/ÉNERGIE ATOMIQUE DU CANADA LIMITÉE (Canada)
Inventor
Bodner, Robert
Tyo, Jonathan
Popov, Dan
Kuran, Sermet
Abstract
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 1/06 - Heterogeneous reactors, i.e. in which fuel and moderator are separated
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 19/19 - Reactor parts specifically adapted to facilitate handling, e.g. to facilitate charging or discharging of fuel elements
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) Nuclear reactors; installations for processing nuclear fuel and nuclear moderating material; parts and fittings for all of the aforesaid. (1) Maintenance services and repair services in the field of nuclear reactor construction.
(2) Nuclear reactor decontamination services.
(3) Material testing services in the field of nuclear reactor design, research and development, and in-service inspection; nuclear reactor project management services; consulting services in the field of nuclear reactor construction.
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) Nuclear reactors; installations for processing nuclear fuel and nuclear moderating material; parts and fittings for all of the aforesaid. (1) Maintenance services and repair services in the field of nuclear reactor construction.
(2) Nuclear reactor decontamination services.
(3) Material testing services in the field of nuclear reactor design, research and development, and in-service inspection; nuclear reactor project management services; consulting services in the field of nuclear reactor construction.
01 - Chemical and biological materials for industrial, scientific and agricultural use
09 - Scientific and electric apparatus and instruments
11 - Environmental control apparatus
35 - Advertising and business services
37 - Construction and mining; installation and repair services
40 - Treatment of materials; recycling, air and water treatment,
41 - Education, entertainment, sporting and cultural services
42 - Scientific, technological and industrial services, research and design
Goods & Services
(1) Moderating materials for nuclear reactors; heavy water; fuel for nuclear reactors.
(2) Safeguard systems, namely surveillance cameras, radiation sensors and detectors, seals (mechanical, fibre optic or electronic), and associated instrumentation to monitor the movement of nuclear material to detect the removal of nuclear material from designated storage locations.
(3) Nuclear reactors; installations for processing nuclear fuel and nuclear moderating material; parts and components for all of the aforesaid; instrumentation which is an integral part of the applicant's nuclear reactors; storage and disposal facilities for used nuclear fuel and radioactive waste materials. (1) Procurement, commissioning, operation and decommissioning services in the field of nuclear reactors.
(2) Construction and maintenance services in the field of nuclear reactors.
(3) Decontamination services in the field of nuclear reactors.
(4) Training services in the field of nuclear reactors.
(5) Material testing services, research and development, and in-service inspection in the field of nuclear reactors; engineering design, project management and inspection services in the field of nuclear reactors.
01 - Chemical and biological materials for industrial, scientific and agricultural use
09 - Scientific and electric apparatus and instruments
11 - Environmental control apparatus
35 - Advertising and business services
37 - Construction and mining; installation and repair services
40 - Treatment of materials; recycling, air and water treatment,
41 - Education, entertainment, sporting and cultural services
42 - Scientific, technological and industrial services, research and design
Goods & Services
(1) Moderating materials for nuclear reactors; heavy water; fuel for nuclear reactors.
(2) Safeguard systems, namely surveillance cameras, radiation sensors and detectors, seals (mechanical, fibre optic or electronic), and associated instrumentation to monitor the movement of nuclear material to detect the removal of nuclear material from designated storage locations.
(3) Nuclear reactors; installations for processing nuclear fuel and nuclear moderating material; parts and components for all of the aforesaid; instrumentation which is an integral part of the applicant's nuclear reactors; storage and disposal facilities for used nuclear fuel and radioactive waste materials. (1) Procurement, commissioning, operation and decommissioning services in the field of nuclear reactors.
(2) Construction and maintenance services in the field of nuclear reactors.
(3) Decontamination services in the field of nuclear reactors.
(4) Training services in the field of nuclear reactors.
(5) Material testing services, research and development, and in-service inspection in the field of nuclear reactors; engineering design, project management and inspection services in the field of nuclear reactors.
Atomic Energy of Canada Limited/ Energie Atomique du Canada Limitee (Canada)
Inventor
Majarais, Bernard A.
Korell, Norman
Kamler, Frank
Bains, Narinder
Scott, David
Abstract
An apparatus for cleaning heat exchanger tubes and in particular an improved collection system for nuclear generator cleaning and blasting media and deposit material. A suction line having a downwardly directed suction inlet is effective to vacuum airborne media and debris in said chamber and vacuum media and debris deposited on the bottom of said chamber below said suction inlet. A hopper, air jet and shaker means are provided to transport deposited media and debris toward the suction inlet. Breaker and partition means are provided to reduce back-streaming of debris into heat exchanger tubes.
09 - Scientific and electric apparatus and instruments
42 - Scientific, technological and industrial services, research and design
Goods & Services
(1) Integrated package of software tools that facilitate on-line monitoring, diagnostics, analysis and control of processes and equipment at a CANDU nuclear power plant to optimize plant operation and maximize plant life. (1) Remote monitoring of current conditions of processes or equipment in nuclear facilities to determine immediate or future actions to properly maintain these processes or equipment.
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) Nuclear reactors; installations for processing nuclear fuel and nuclear moderating material; parts and fittings for all of the aforesaid. (1) Maintenance services and repair services. Consulting services in the field of nuclear reactor construction.
(2) Nuclear reactor decontamination services.
(3) Material testing services in the field of nuclear reactor design, research and development, and in-service inspection. Nuclear reactor project management services.
03 - Cosmetics and toiletries; cleaning, bleaching, polishing and abrasive preparations
07 - Machines and machine tools
09 - Scientific and electric apparatus and instruments
11 - Environmental control apparatus
19 - Non-metallic building materials
21 - HouseHold or kitchen utensils, containers and materials; glassware; porcelain; earthenware
42 - Scientific, technological and industrial services, research and design
Goods & Services
(1) Debris collection devices having the following characteristics for use in nuclear reactors: compact, modular, low head loss, large surface area, high debris collection capacity (large debris to fine-particulate removal capabilities), passive, adaptive configuration, low maintenance, custom-made and engineered for customer specific conditions. (1) Combined engineering, technological consulting and fabrication services providing quality custom-made solutions for removing large quantities of debris from fluids flowing through open systems.
09 - Scientific and electric apparatus and instruments
10 - Medical apparatus and instruments
Goods & Services
(1) System health monitor and related software for power plant chemistry providing automated monitoring, alarming, diagnostics, prediction and on-line execution of analysis codes to assist and improve in the monitoring and control of power plant chemistry and to improve capacity factors and extend power plant life.
01 - Chemical and biological materials for industrial, scientific and agricultural use
04 - Industrial oils and greases; lubricants; fuels
05 - Pharmaceutical, veterinary and sanitary products
07 - Machines and machine tools
09 - Scientific and electric apparatus and instruments
11 - Environmental control apparatus
19 - Non-metallic building materials
35 - Advertising and business services
37 - Construction and mining; installation and repair services
39 - Transport, packaging, storage and travel services
40 - Treatment of materials; recycling, air and water treatment,
41 - Education, entertainment, sporting and cultural services
42 - Scientific, technological and industrial services, research and design
Goods & Services
(1) Radioisotopes for scientific and industrial purposes; heavy water; fuel for nuclear reactors; metal containing catalysts for chemical reactions.
(2) Radon canisters and parts, and fittings and accessories therefor; canisters for storage of nuclear spent fuel.
(3) Radioisotopes for medical purposes.
(4) Machine tooling and instrumentation for repair of nuclear reactors and parts, components and systems.
(5) Calibration instruments, monitors and probes used for measuring and testing nuclear and non-nuclear materials and machines; level and pressure recorders; computer software and manuals; instrumentation for determining fluid flows; electron accelerators; charged particle accelerators.
(6) Safeguard systems for nuclear reactors; nuclear reactors, and parts, components and systems thereof; steam generating apparatus, namely, pump seals used in industrial machinery.
(7) High performance valves. (1) Operation of a business manufacturing, repairing, servicing and consulting with respect to the above goods; the provision of project management services to others; the sale , for others, of cobalt-60 sources, gamma irradiators and electron accelerators; the provision of procurement services to the nuclear power plants of others which are under construction or in operation.
(2) The construction, including construction engineering, maintenance and repair, for others, of nuclear installations; the maintenance and repair, for others, of steam generators forming part of nuclear installations; the construction, including construction engineering, maintenance and repair, for others, of irradiation units.
(3) Storage, for others, of radioactive waste material.
(4) The decontamination, for others, of nuclear installations; the decommissioning, for others, of nuclear installations; the disposal, for others, of radioactive waste material, the provision to others of material treatment services; the provision to others of mechanical and chemical processing services such as heavy water upgrading, isotope production and tritium removal; the provision to others of a hydraulic cutting service.
(5) The provision of training services, to others, in connection with nuclear technology and radiation protection.
(6) The provision to others of quality control and inspection services relating to nuclear installations, steam generators and irradiation units; ; the provision to others of technical, chemical and medical research services, industrial design services, engineering and engineering design services, material testing services, professional consultation services and geological research services; the provision to others of vibration analysis services; research, for others, to develop practical uses of radiation in industry; the provision of irradiation facilities; the development, for others, of high-power particle accelerators; the design, manufacture and servicing, for others, of cobalt-60 sources, gamma irradiators and electron accelerators; research, for others, to develop practical uses of radiation in industry; the provision of irradiation facilities; the development, for others, of high-power particle accelerators; ; research and development, for others, in the field of gamma and electron beam radiation processing; and research and development, for others, into industrial radiation processing applications using ionizing radiation from radioisotopes and electron accelerators; the design and development, for others, of robotic systems; the post-irradiation examination, for others, of fuel and pressure tubes; the non-destructive examination, for others, of flaws or damage to materials; the development and application, for others, of operations procedures and reliability studies in evaluation of petrochemical plants and aluminum smelters.
09 - Scientific and electric apparatus and instruments
11 - Environmental control apparatus
36 - Financial, insurance and real estate services
42 - Scientific, technological and industrial services, research and design
Goods & Services
(1) Computer hardware and software and a related computer relay network system for use in process control, monitoring and protection systems in power plants, particularly nuclear power and fossil fuel plants. (1) Assisting others in process control, monitoring and protection systems in power plants particularly nuclear power and fossil fuel plants.
36 - Financial, insurance and real estate services
40 - Treatment of materials; recycling, air and water treatment,
41 - Education, entertainment, sporting and cultural services
42 - Scientific, technological and industrial services, research and design
Goods & Services
(1) Nuclear reactors. (1) Nuclear reactor design, construction know-how, performance, backup research and development, in-service inspection, decontamination and general project management, rendered to others.
(2) Establishment of co-operative arrangements, the administration of research programs and projects, and the provision of mutual assistance and exchange of information, equipment, and procedures among operators, designers and developers of nuclear electric generating stations.
09 - Scientific and electric apparatus and instruments
11 - Environmental control apparatus
14 - Precious metals and their alloys; jewelry; time-keeping instruments
37 - Construction and mining; installation and repair services
42 - Scientific, technological and industrial services, research and design
Goods & Services
(1) Nuclear reactors and their auxiliary control equipment and housing therefor. (1) Installation and service of nuclear reactors to be used by research, hospitals and industries as a source of neutrons for any application.
01 - Chemical and biological materials for industrial, scientific and agricultural use
04 - Industrial oils and greases; lubricants; fuels
05 - Pharmaceutical, veterinary and sanitary products
06 - Common metals and ores; objects made of metal
07 - Machines and machine tools
09 - Scientific and electric apparatus and instruments
10 - Medical apparatus and instruments
11 - Environmental control apparatus
12 - Land, air and water vehicles; parts of land vehicles
16 - Paper, cardboard and goods made from these materials
17 - Rubber and plastic; packing and insulating materials
21 - HouseHold or kitchen utensils, containers and materials; glassware; porcelain; earthenware
28 - Games; toys; sports equipment
35 - Advertising and business services
37 - Construction and mining; installation and repair services
39 - Transport, packaging, storage and travel services
40 - Treatment of materials; recycling, air and water treatment,
41 - Education, entertainment, sporting and cultural services
42 - Scientific, technological and industrial services, research and design
44 - Medical, veterinary, hygienic and cosmetic services; agriculture, horticulture and forestry services
Goods & Services
(1) Irradiation units and accessories for use therewith for use in the industrial, medical and research fields.
(2) Isotopes.
(3) Radioisotopes for scientific and industrial purposes; moderating materials for nuclear reactors; heavy water; fuel for nuclear reactors; radioactive preparations and substances for industrial purposes; metal containing catalysts for chemical reactions; charged particle accelerators; radioisotopes for medical purposes; radioactive preparations and substances for medical purposes; apparatus and instrumentation which measures, tests and/or repairs nuclear reactors and parts, components and systems thereof; level and pressure recorders; radon canisters and parts, and fittings and accessories therefor; canisters for storage of nuclear spent fuel; computer software and manuals; safeguard systems for nuclear reactors; nuclear reactors, and parts, components and systems thereof; lighting, heating and steam generating apparatus; instrumentation for determining fluid flows; electron accelerators; and high performance valves.
(4) High performance pump seals.
(5) Passive autocatalytic recombiners.
(6) Machine vision inspection systems.
(7) Seals for airlock doors. (1) Consultant services and equipment servicing.
(2) Research programs.
(3) Engineering designs for medical sterilization plants.
(4) Room and building layouts for use in association with irradiation equipment.
(5) Operation of a business manufacturing, selling, repairing, servicing and consulting with respect to the above goods; the construction, including construction engineering, maintenance and repair, for others, of nuclear installations; the maintenance and repair, for others, of steam generators forming part of nuclear installations; the decontamination, for others of nuclear installations; the decommissioning, for others, of nuclear installations; the construction, including construction engineering, maintenance and repair, for others, of irradiation units; the provision to others of quality control and inspection services relating to nuclear installations, steam generators and irradiation units; the disposal and storage, for others, of radioactive waste material; the provision to others of material treatment services; the provision to others of mechanical and chemical processing services such as heavy water upgrading, isotope production and tritium removal; the provision to others of a hydraulic cutting service; the provision of training services, to others, in connection with nuclear technology and radiation protection; the provision to others of technical, chemical and medical research services, industrial design services, engineering and engineering design services, material testing services, professional consultation services and geological research services; the design and development, for others, of robotic systems; the provision of project management services to others; the provision to others of vibration analysis services; the post-irradiation examination, for others, of fuel and pressure tubes; the non-destructive examination, for others, of flaws or damage to materials; the provision of procurement services to the nuclear power plants of others which are under construction or in operation; the development and application, for others, of operations procedures and reliability studies in evaluation of petrochemical plants and aluminum smelters; research, for others, to develop practical uses of radiation in industry; the provision of irradiation facilities; the development, for others, of high-power particle accelerators; the design, manufacture, sale and servicing, for others, of cobalt-60 sources, gamma irradiators and electron accelerators; research and development, for others, in the field of gamma and electron beam radiation processing; and research and development, for others, into industrial radiation processing applications using ionizing radiation from radioisotopes and electron accelerators.
(6) Provision, to others, of CADS and kinematic simulation services.
(7) Design and construction, for others, of facilities for storage of used nuclear fuels and high level radioactive wastes.