Abstract

Debris filtering grid for a nuclear fuel assembly The debris filtering grid has flow channels (34, 36) extending through the debris filtering grid, each flow channel (34, 36) having a cross-section exhibiting a cross-sectional shape and a cross-sectional area, the flow channels (34, 36) including first flow channels (34) having a first cross-section and second flow channels having a second cross-section differing from the first cross-section by the cross-sectional shape and/or the cross-sectional area, wherein the debris filtering grid comprises at least one region including first rows (44) of first flow channel (34) aligned in a first direction (D1) and second rows (46) of second flow channels (36) aligned in the first direction (D1), the first rows (44) alternating with the second row (46) in a second direction (D2) perpendicular to the first direction (D1).

IPC Classes  ?

• G21C 3/32 - Bundles of parallel pin-, rod-, or tube-shaped fuel elements
• G21C 3/33 - Supporting or hanging of elements in the bundleMeans forming part of the bundle for inserting it into, or removing it from, the coreMeans for coupling adjacent bundles

Abstract

The maintenance method comprises the following steps: S1: extracting one of the thermocouples (41) from the corresponding upper thermocouple guide conduit (35); S3: inserting a new thermocouple (41) into said upper thermocouple guide conduit (35), the new thermocouple (41) being driven by at least one drive member (45) which comes into contact with the new thermocouple (41) through at least one lateral window (43) formed in the outer part (36) of the upper thermocouple guide conduit (35) and drives the new thermocouple (41) through the at least one lateral window (43).

IPC Classes  ?

• G21C 19/20 - Arrangements for introducing objects into the pressure vesselArrangements for handling objects within the pressure vesselArrangements for removing objects from the pressure vessel
• G21C 5/02 - Moderator or core structureSelection of materials for use as moderator Details
• G21C 17/112 - Measuring temperature

Goods & Services

Electronic components, namely field programmable gate array, central processing unit, application-specific integrated circuit, for instrumentation and control systems for nuclear installation; Sensors and actuators for instrumentation and control systems for nuclear installation; Measurement apparatus and Instrumentation simulators for instrumentation and control systems for nuclear installation; Downloadable Software for control, supervision and data acquisition for instrumentation and control systems for nuclear installation; Embedded systems and industrial electronic circuits boards for instrumentation and control systems for nuclear installation; Downloadable software for designing, modeling and simulating instrumentation and control systems for nuclear installation; Downloadable computer software development tools for field programmable gate array, central processing unit and other programmable circuits for instrumentation and control systems for nuclear installation Installation and commissioning of instrumentation and control systems for nuclear installation; Integration of hardware and software components in nuclear industrial installations; Maintenance and repair and upgrading of instrumentation and control equipment for nuclear installation; Replacement of electronic and programmable components (field programmable gate array, central processing unit, electronic boards) for instrumentation and control systems for nuclear installation Software engineering and hardware of instrumentation and control components for nuclear installation; software consulting services in architecture and development of instrumentation and control systems for nuclear installation; instrumentation and control systems architecture and development consulting for instrumentation and control systems for nuclear installation; engineering services relating to instrumentation and control for instrumentation and control, for nuclear installation; Hardware and software qualification and compliance testing instrumentation and control components for nuclear installation; Development of software solutions for automation and control for nuclear installation; computer software technical support services; technical support services relating to computer software and applications for instrumentation and control systems for nuclear installation; updating of computer program and programming software; computer technology in the field of cybersecurity; computer security monitoring services

Abstract

Spacer grid elements for nuclear fuel assembly spacer grid, spacer grids and nuclear fuel assembly The spacer grid elements (18) define cells (16) for receiving nuclear fuel rods (4). The spacer grid elements (18) are configured to be arranged side-by-side with applying two side walls (22) of two adjacent spacer grid elements (18) one against the other. One of the two side walls (22) of at least one pair of side walls (22) applied against each other is provided with a lower flap (34) protruding from the lower edge of said side wall (22) such as to at least partially cover the lower edge (22A) of the other side wall and/or one of the two side walls (22) of said at least one pair of side walls (22) applied against each other is provided with an upper flap (34) protruding from the upper edge of said side wall (22) such as to at least partially cover the upper edge (22B) of the other side wall.

IPC Classes  ?

• G21C 3/344 - Spacer grids formed of assembled tubular elements
• G21C 3/352 - Spacer grids formed of assembled intersecting strips

Abstract

Improved top nozzle for a nuclear fuel assembly The top nozzle comprises a deflection part (16) and an upper part (18), the deflection part (16) comprising a base plate (24) and a guiding assembly (26) configured for connecting the base plate (24) to the upper part (18), the base plate (24) being formed of plate members (38, 42, 48, 50, 52) connected together with defining flow openings (34, 46) between them, each plate member (38, 42, 48, 50, 52) extending along an extension line (E), wherein one or more of the plate members (38, 42, 48, 50, 52) are streamlined, each streamlined plate member (38, 42, 48, 50, 52) exhibiting a streamlined profile in a cross-section perpendicular to the extension line (E) of the streamlined plate member (38, 42, 48, 50, 52).

IPC Classes  ?

• G21C 3/322 - Means to influence the coolant flow through or around the bundles
• G21C 3/33 - Supporting or hanging of elements in the bundleMeans forming part of the bundle for inserting it into, or removing it from, the coreMeans for coupling adjacent bundles

Abstract

The spacer grid (14) comprises a plurality of tubular cells (18) for receiving fuel rods (4), each cell (18) having a polygonal cross section, with at least two support faces (20) and at least two connecting faces (22) alternating around the central axis (C), each support face (20) having a given at least in part convex shape toward the inside of the cell (18), each support face (18) bearing a protruding element area (24) intended to contact the fuel rod (4); each connecting face (22) having a given at least in part concave shape toward the inside of the cell (18); the support face (20) of a given cell (18) lays against one of the connecting faces (22) of a neighbouring cell (18), the convex shape and the concave shape being such that more than 50% of a surface area of said support face (20) outside the protruding element area (24) is in contact with said connecting face (22).

IPC Classes  ?

• G21C 3/344 - Spacer grids formed of assembled tubular elements
• G21C 3/356 - Spacer grids being provided with fuel element supporting members

Abstract

The present invention relates to a system (1) for extracting UF6 from a UF6 container placed in an autoclave (5), comprising a pump (24) having an inlet port (26) being connected to an upstream supply circuit (10, 20), the upstream supply circuit (10, 20) transporting UF6 from the autoclave to the pump (24); wherein the system further comprises a temperature- controlled subsystem (3) providing a heat supply to the pump (24) and at least a downstream portion of the upstream supply circuit (10, 20), the temperature-controlled subsystem (3) heat supply being adapted to maintain a temperature within the upstream supply circuit and the pump (24) during operation such that said temperature is above the crystallization temperature of UF6.

IPC Classes  ?

• G21C 21/02 - Manufacture of fuel elements or breeder elements contained in non-active casings
• G21C 3/62 - Ceramic fuel
• G21C 17/00 - MonitoringTesting

Abstract

66) in a gas stream (G). The detection method comprises humidifying the gas stream by circulating the gas stream (G) in contact with a sulfonated tetrafluoroethylene-based fluoropolymer copolymer, in particular Nafion, and then detecting the presence of hydrogen fluoride (HF) in the gas stream (G) by means of a sensor.

IPC Classes  ?

• G01N 33/00 - Investigating or analysing materials by specific methods not covered by groups
• G01T 1/00 - Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation

Abstract

The method implemented by a monitoring module (42) programmed in RUST programming language and collecting activity data via an eBPF module (44) installed in the kernel space (28) of a GNU/Linux operating system (26), the monitoring module (42) being configured to perform the steps of: - in a safe operational observing environment, observe behaviors of the at least one software (24) based on activity data collected via the eBPF module (44) and store reference behaviors into a reference behavioral model (52), then - in an autonomous operational monitored environment, monitor at least one behavior of the at least one software (24) based on activity data collected via the eBPF module (44), - if a deviation is detected between the monitored behavior and the expected reference behavior (56), keep the at least one software (24) running and generate and send an event message (58).

IPC Classes  ?

• G06F 21/55 - Detecting local intrusion or implementing counter-measures
• G06F 11/30 - Monitoring
• G06F 21/56 - Computer malware detection or handling, e.g. anti-virus arrangements
• H04L 9/40 - Network security protocols

Abstract

The scintillation detector comprises an annular scintillator (40) circumferentially segmented by being formed of a plurality of distinct scintillation elements (42) arranged in a circle around a central axis (A). Each scintillation element (42) is equipped with one or more silicon photomultipliers (60) for detecting photons emitted by the scintillation element (42).

IPC Classes  ?

• G01T 1/167 - Measuring radioactive content of objects, e.g. contamination
• G01T 1/20 - Measuring radiation intensity with scintillation detectors

Abstract

The present invention relates to a device (10) for ultrasonic testing of a weld (12) of a pipe (14), more particularly of a nuclear reactor, for example a pressurised water reactor, or of a petrochemical facility, the testing device (10) comprising a plurality of support pieces and a plurality of ultrasonic transducers, the support pieces being attached one after another, so as to form a belt suitable for surrounding the entire circumference of the pipe (14), a single transducer being mounted on each of the support pieces.

IPC Classes  ?

• G01N 29/22 - Investigating or analysing materials by the use of ultrasonic, sonic or infrasonic wavesVisualisation of the interior of objects by transmitting ultrasonic or sonic waves through the object Details

Abstract

The invention relates to a steam generator (1) comprising: - U-shaped tubes (5); - a dome (18) covering the curved branches (9) of the U-shaped tubes; - a plurality of steam ducts (23), each connected to a steam port (21) of the dome and arranged in a circle about the central axis (C); the work floor (29) comprising at least one floor sector (31) intended to be arranged circumferentially between two steam ducts (23), the or each floor sector (31) comprising: - a support (33) having a shape designed to be arranged radially between a central zone of the dome (18) and the circle of steam ducts (23) and circumferentially between the two neighbouring steam ducts (23), the support (33) being placed on the dome (18) and having a bearing point (37) on each of the two neighbouring steam ducts (23) and at least one bearing point (39) on the dome (18); - at least one extension plate (35) connected to the support (33) and extending from the support (33) in a longitudinal direction between the two steam ducts (23).

IPC Classes  ?

• F22B 1/02 - Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
• F22B 37/00 - Component parts or details of steam boilers

Goods & Services

Metal frames, structures, panels and partitions for construction of industrial units for nuclear fuel production. Frames, structures, panels and partitions not of metal for construction of industrial units for nuclear fuel production. Installation and assembly of industrial units for nuclear fuel production; construction and maintenance of industrial units for nuclear fuel production. Custom manufacture of industrial units for nuclear fuel production. Design, engineering and development of industrial units for nuclear fuel production; quality auditing, inspection and certification of industrial units for nuclear fuel production.

Goods & Services

(1) Ossatures, charpentes, panneaux et cloisons métalliques pour la construction d'unités industrielles de production de combustibles nucléaires. (2) Ossatures, charpentes, panneaux et cloisons non-métalliques pour la construction d'unités industrielles de production de combustibles nucléaires. (1) Services d'installation et de montage d'unités industrielles de production de combustible nucléaire; services de construction et de maintenance d'unités industrielles de production de combustible nucléaire. (2) Services de fabrication sur mesure d'unités industrielles pour la production de combustible nucléaire. (3) Services de conception, ingénierie et développement d'unités industrielles de production de combustible nucléaire; services d'audit de qualité, d'inspection et de certification d'unités industrielles de production de combustible nucléaire.

Goods & Services

Metal frames, structures, panels and partitions for construction of industrial units for nuclear fuel production. Frames, structures, panels and partitions not of metal for construction of industrial units for nuclear fuel production. Installation and assembly of industrial units for nuclear fuel production; construction and maintenance of industrial units for nuclear fuel production. Custom manufacture of industrial units for nuclear fuel production. Design, engineering and development of industrial units for nuclear fuel production; quality auditing, inspection and certification of industrial units for nuclear fuel production.

Abstract

A first seat (46) is secured to the piston and a second seat (48) is secured to the support, a set of friction springs (50) extending between the seats along the transverse axis (T). The connection of the support to the piston is rigid in normal operation of the travelling crane such that the piston guides the travelling crane by contact along the structure, and the set of friction springs compresses, extends and/or dissipates energy in accident conditions when the structure is subjected to a deformation and/or to an acceleration above a threshold.

IPC Classes  ?

• B66C 9/16 - Travelling gear incorporated in, or fitted to, trolleys or cranes with means for maintaining alignment between wheels and track
• B66C 15/00 - Safety gear
• B66C 17/00 - Overhead travelling cranes comprising one or more substantially-horizontal girders the ends of which are directly supported by wheels or rollers running on tracks carried by spaced supports
• E04B 1/98 - Protection against other undesired influences or dangers against vibrations or shocksProtection against other undesired influences or dangers against mechanical destruction, e.g. by air-raids
• E04H 9/02 - Buildings, groups of buildings or shelters adapted to withstand or provide protection against abnormal external influences, e.g. war-like action, earthquake or extreme climate withstanding earthquake or sinking of ground
• F16F 7/02 - Vibration-dampersShock-absorbers with relatively-rotatable friction surfaces that are pressed together
• F16F 7/04 - Vibration-dampersShock-absorbers with relatively-rotatable friction surfaces that are pressed together in the direction of the axis of rotation

Abstract

The nuclear fuel assembly comprises grids distributed along the length of nuclear fuel rods (4), the grids including spacer grids (14), at least one reinforcing grid (16), a lower end grid (18) and an upper end grid (20). The spacer grids (14) define, between them and together with the lower end grid (18) and the upper end grid (20), a plurality of intervals (15). The grids further include one or more intermediate mixing grids (22) and, optionally, an anti-debris grid (24) in which the lower ends of the nuclear fuel rods (24) engage.

IPC Classes  ?

• G21C 3/32 - Bundles of parallel pin-, rod-, or tube-shaped fuel elements
• G21C 3/322 - Means to influence the coolant flow through or around the bundles
• G21C 3/34 - Spacer grids

Abstract

The present invention relates to a Radioactive source (3, 32, 50, 60, 70) adapted to be used in a gamma sterilization facility, comprising: a top end (10) and a bottom end (12), the top end and the bottom end being spaced apart from each other, wherein the radioactive source has a source longitudinal axis (X) extending between the top end and the bottom end; an intermediate portion (16) between the top end and the bottom end, wherein the intermediate portion comprises a plurality of capsules (18, 20, 21, 56, 66, 76) of radioactive activated material, wherein at least two of the plurality of capsules are arranged in a same intermediate plane being between the top end and the bottom end, wherein each capsule has a capsule longitudinal axis, wherein the at least two of the capsule longitudinal axes are in parallel to the source longitudinal axis, wherein - the capsules (20, 21, 76) having shape of a portion of a circular cylinder, which is cut along the longitudinal axis; and/or - at least two of the capsules in the same intermediate plane are arranged in a common housing (22, 54, 64, 74), wherein the common housing has non-cylindrical shape in a cross- section in the intermediate plane; and/or- the intermediate portion comprises plurality of housings, wherein each housing includes at least one capsule in the same intermediate plane.

IPC Classes  ?

• G21K 5/00 - Irradiation devices
• G21F 5/015 - Transportable or portable shielded containers for storing radioactive sources, e.g. source carriers for irradiation unitsRadioisotope containers
• G21G 4/06 - Radioactive sources other than neutron sources characterised by constructional features
• G21G 4/08 - Radioactive sources other than neutron sources characterised by constructional features specially adapted for medical applications
• A61N 5/10 - X-ray therapyGamma-ray therapyParticle-irradiation therapy

Abstract

000+T].

IPC Classes  ?

• G21D 3/00 - Control of nuclear power plant
• G21C 7/08 - Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
• G21C 7/32 - Control of nuclear reaction by varying flow of coolant through the core
• G21C 17/10 - Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain

Abstract

Debris filtering grid for a nuclear fuel assembly bottom nozzle The debris filtering grid is configured to be positioned upstream or downstream a tie plate (16) of a bottom nozzle of a nuclear fuel assembly, the tie plate (16) having structural members (20) and flow passages (22) delimited between the structural members (20), wherein the debris filtering grid comprises flow channels (36) for a coolant fluid to flow through the debris filtering grid and ligaments (40) extending across the flow channels (36) for filtering debris, at least a part of the ligaments (40) being streamlined such as to exhibit a streamlined profile and straighten the fluid flow downstream and/or upstream the debris filtering grid.

IPC Classes  ?

• G21C 3/32 - Bundles of parallel pin-, rod-, or tube-shaped fuel elements
• G21C 3/322 - Means to influence the coolant flow through or around the bundles
• G21C 3/33 - Supporting or hanging of elements in the bundleMeans forming part of the bundle for inserting it into, or removing it from, the coreMeans for coupling adjacent bundles

Abstract

The method for producing a nuclear fuel is implemented using nuclear elements (2) comprising a fissile material (4) contained within cladding (6), inside a capsule (8) or in a composite material (10) formed by the fissile material dispersed in a matrix (12). The processing method comprises cutting the nuclear elements into fragments (36), reducing the fragments to a powder in order to obtain a powder, and using the powder to manufacture nuclear fuel.

IPC Classes  ?

• G21C 19/37 - Removing cannings or casings from fuel by separating into pieces both the canning or the casing and the fuel element, e.g. by cutting or shearing
• G21C 3/58 - Solid reactor fuel
• G21C 3/60 - Metallic fuelIntermetallic dispersions
• G21C 3/62 - Ceramic fuel
• G21C 19/46 - Aqueous processes
• G21C 21/02 - Manufacture of fuel elements or breeder elements contained in non-active casings

Abstract

The invention relates to an anchoring device which comprises: - a plate (5) including at least one frustoconical opening (7); - a rod (17) secured in the structure (3); - a positioning ring (29) with a positioning slot (37); - a blocking ring (49) with a blocking slot (57); - a locking member (71) biasing the rings towards the back of the opening; the angle of the opening (α) being chosen so that the force applied by the locking member (71) does not cause the rings to be pushed into the opening (7); the slots having shapes chosen so that the rod (17) is blocked in position relative to the plate (5) in all directions perpendicular to the longitudinal direction by the edges of the slots.

IPC Classes  ?

• F16B 5/02 - Joining sheets or plates to one another or to strips or bars parallel to them by means of fastening members using screw-thread
• F16B 43/02 - Washers or equivalent devicesOther devices for supporting bolt-heads or nuts with special provisions for engaging surfaces which are not perpendicular to a bolt axis or do not surround the bolt

Abstract

The invention relates to a method for determining a delay law for ultrasonic inspection of a weld (10), comprising the following steps: - providing information on the weld (10) comprising the arrangement of grains of the weld and a respective orientation of said grains, - modeling the weld (10) with a digital model based on the provided information, - positioning a defect in the digital model in a desired place, - simulating in the digital model propagation of an ultrasonic wave from a location through the weld (10) to the defect and of a resulting reflected wave, - determining the times of flight of the resulting reflected wave, and - applying time reversal to the times of flight to determine a suitable delay law. The invention also relates to an associated inspecting method, device and computer program product.

IPC Classes  ?

• G01N 29/04 - Analysing solids
• G01N 29/07 - Analysing solids by measuring propagation velocity or propagation time of acoustic waves
• G01N 29/26 - Arrangements for orientation or scanning
• G01N 29/44 - Processing the detected response signal

Abstract

A storage container for uranium oxide powder, comprising: - a drum having a central axis; - an insert comprising several tubes extending in respective directions parallel to the central axis, fastened to the drum and located inside the drum; - neutron absorbing bodies housed inside the tubes.

IPC Classes  ?

• G21F 5/00 - Transportable or portable shielded containers
• G21F 5/06 - Details of, or accessories to, the containers

Abstract

The invention relates to a canned motor pump comprising: - a bowl (3) with a fluid inlet (5) and a fluid outlet (7); - a pump wheel (9) arranged inside the bowl (3); - a motor casing (11) rigidly attached to the bowl (3) and internally defining a chamber (13) in fluid communication with the bowl (3); - a motor (15) comprising a rotor (17) and a stator (19), arranged inside the chamber (13); - a shaft (21) to which the pump wheel (9) is attached, the shaft (21) being rotated about an axis of rotation by the rotor (17); - a heat exchanger (41) arranged inside the chamber (13), with a first side (43) through which the fluid flows and a second side (45) through which a heat transfer fluid flows; - a circuit for cooling the motor (47) with the fluid, wherein a cooling passage (49) through which the fluid flows is in thermal contact with the motor (15), and wherein the first side (43) of the heat exchanger (41) forms part of the cooling circuit (47) and is arranged downstream of the cooling passage (49).

IPC Classes  ?

• F04D 7/08 - Pumps adapted for handling specific fluids, e.g. by selection of specific materials for pumps or pump parts of centrifugal type the fluids being radioactive
• F04D 13/06 - Units comprising pumps and their driving means the pump being electrically driven
• F04D 29/58 - CoolingHeatingDiminishing heat transfer

Abstract

The present invention relates to a method (400) for checking the uniformity of the composition of a fissile isotope of interest in a chemical element along a main axis (X) of a nuclear fuel rod (15) to be tested, the method comprising the steps of performing a first scan (401) of the fuel rod to be tested (15) along the main axis (X) using a first gamma radiation detector (20) without prior excitation, wherein the first scan generates a first gamma profile; performing a second scan (402) of the fuel rod to be tested (15) along the main axis (X) using a second gamma radiation detector (25) after excitation by means of a neutron source (30), wherein the second scan generates a second gamma profile; obtaining a third gamma profile by subtracting the first profile from the second profile; and evaluating (403) the uniformity of the composition of the fissile isotope of interest along the main axis (X) of the fuel rod to be tested (15) on the basis of the third gamma profile.

IPC Classes  ?

• G21C 17/06 - Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination

Abstract

The invention relates to cladding comprising a tube (14) that extends along a longitudinal axis and a tubular inner lining (18) housed inside the tube (14), wherein the tube (14) comprises at least one reinforced layer (16) made of a composite material that comprises a ceramic matrix reinforced with ceramic reinforcing fibres, and wherein the thickness of the tube (14) is between 280 µm and 600 µm.

IPC Classes  ?

• G21C 3/07 - CasingsJackets characterised by their material, e.g. alloys
• G21C 3/10 - End closures
• 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

Abstract

The invention relates to a device for qualifying a plurality of specimens (14), each comprising a wire (18) and at least one element (20) crimped onto the wire, the device comprising: - a test zone (28) forming locations (24) intended to receive respective specimens to be tested, - a programmable current source (30), - an electrical circuit (32) for electrically connecting the locations to the current source, the electrical circuit comprising contactors (C1 to C21) configured to be opened or closed and to define, in combination with one another, a plurality of electrical circuit configurations, in particular of a first type, in which: - only one of the locations is selectively electrically connected to the current source, - the others are disconnected from the current source, and - only one of the specimens is intended for a current to pass therethrough.

IPC Classes  ?

• G01R 31/69 - Testing of releasable connections, e.g. of terminals mounted on a printed circuit board of terminals at the end of a cable or a wire harnessTesting of releasable connections, e.g. of terminals mounted on a printed circuit board of plugsTesting of releasable connections, e.g. of terminals mounted on a printed circuit board of sockets, e.g. wall sockets or power sockets in appliances
• G01R 27/20 - Measuring earth resistanceMeasuring contact resistance of earth connections, e.g. plates
• G01R 27/08 - Measuring resistance by measuring both voltage and current

Abstract

The invention concerns a system (10), providing a patch of electrical signals between at least two different devices (12, 14) presenting a different number of connecting points, and comprising: - a connecting panel (161) presenting connecting points of one (12) of these device, - a PCB configuration card (18) configured to route some of the connecting points to a free face comprising at least one board to board connector with a predetermined input/output connection pattern; - a flex PCB comprising two identical ends (20) connected by a flexible PCB link (22), each end presenting at least one flex PCB board to board connector configured to be plugged, according to said predetermined input/output connection pattern, one end being connected to the board to board connector, the other end being connected to the other device (14).

IPC Classes  ?

• H04Q 1/02 - Constructional details

Abstract

This irradiation unit (10) for emitting nuclear radiation having an activity in the range of 9kCi to 15KCi, comprising: - a cylindrical irradiation vessel (18) forming a closed internal volume (22); and - a plurality of irradiation sources (20) located in the closed inner volume (22); wherein: - the irradiation sources (20) are essentially spherical; - the cylindrical irradiation vessel (18) is a single-walled vessel; and - the irradiation unit (10) further comprises a binder (21 ) arranged in the closed inner volume (22), wherein the irradiation sources (20) are embedded in the binder (21).

IPC Classes  ?

• G21G 4/06 - Radioactive sources other than neutron sources characterised by constructional features
• G21G 1/02 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors

Abstract

The present invention relates to a device (10) for scanning a surface (100) by endoscopy, comprising: - a light source (12) capable of generating an emitted light beam (20) having a wavelength selectively chosen from different wavelengths, - an optical guide (14) suitable for transmitting the emitted light beam (20), and - an optical device (16) arranged to receive the emitted light beam transmitted by the optical guide (14) and to emit an exiting light beam (30) from the received light beam, the optical device (16) being suitable for emitting the exiting light beam (30) at a location and/or at an angle depending on its wavelength. The invention also relates to an associated assembly and scanning method.

IPC Classes  ?

• A61B 1/06 - Instruments for performing medical examinations of the interior of cavities or tubes of the body by visual or photographical inspection, e.g. endoscopesIlluminating arrangements therefor with illuminating arrangements
• G02B 23/24 - Instruments for viewing the inside of hollow bodies, e.g. fibrescopes

Abstract

The manufacturing method comprises obtaining a strip of nickel-based alloy having a composition, in percentages by weight: trace amounts ≤ C ≤ 0.08%; trace amounts ≤ Mn ≤ 0.35%; trace amounts ≤ Si ≤ 0.35%; trace amounts ≤ P ≤ 0.015%; trace amounts ≤ S ≤ 0.015%; 17.0% ≤ Cr ≤ 21.0%; trace amounts ≤ Co ≤ 1.0%; 2.80% ≤ Mo ≤ 3.30%; 4.75% ≤ Nb + Ta ≤ 5.50%; 0.65% ≤ Ti ≤ 1.15%; 0.20% ≤ Al ≤ 0.80%; trace amounts ≤ Cu ≤ 0.30%; 50.0% ≤ Ni ≤ 55.0%; trace amounts ≤ B ≤ 0.006%; the balance being Fe and impurities resulting from the production, and performing desensitization annealing in a static furnace at an annealing temperature equal to or higher than 900°C and/or equal to or lower than 1050°C for an annealing time equal to or greater than 1 min and/or equal to or less than 180 min.

IPC Classes  ?

• C22C 19/05 - Alloys based on nickel or cobalt based on nickel with chromium
• C22F 1/10 - Changing the physical structure of non-ferrous metals or alloys by heat treatment or by hot or cold working of nickel or cobalt or alloys based thereon

Goods & Services

Scientific, surveying, electronic, electric, optical, weighing, measuring, signaling, checking (supervision) and emergency (life-saving) used in the nuclear energy industries; apparatus, instruments and devices for monitoring and surveillance of industrial installations in the fields of nuclear energy; apparatus and software for controlling the stability of industrial facilities in the fields of nuclear energy; computer programs, software packages, software and alarms for monitoring and surveillance of industrial installations; computer programs, software packages and software used in the nuclear field; electric or electronic components, particularly semiconductors, semiconductor devices, electronic circuits and microcircuits, chips (integrated circuits), microprocessors, microcontrollers, field-programmable gate array (FPGA) networks and assemblies bundled together; expert system generator, namely, expert systems generation software, knowledge-based construction and operating development software; apparatus and instruments for topographies; artificial intelligence software for monitoring, controlling, optimizing and supporting the operational management of industrial facilities. Construction and implementation service for research and engineering facilities and equipment in the fields of nuclear energy, renewable energies and efforts to combat climate change; installation and maintenance services for control, operational control or safety system facilities in the field of energy. Engineering services for research and development in the fields of computing and the nuclear field; services for scientific calculations, design and engineering services aided or not by computers for the construction or maintenance of nuclear power plants and the equipment thereof; monitoring and control services for monitoring and controlling facilities, equipment in the field of microprocessor-controlled nuclear energy, monitoring and controlling facilities and pilot modules using interactive displays, in the field of computing and the nuclear field; diagnostics and technical expertise with respect to the safety and control of facilities in the nuclear field; technical studies and analyses and diagnostics (provided by engineers) for the installation of control systems in the nuclear field; software maintenance; updating of software; artificial intelligence research in the nuclear field; conducting tests for control-command of nuclear facilities; research in the field of controlled nuclear fusion technology; research work and technical project studies in the field of nuclear energy, connectics and electronics; advice, expertise [engineering works] in the fields of nuclear energy, connectics and electronics; monitoring and information with respect to instrumentation and control-command of infrastructures, facilities, equipment and apparatus in the fields of nuclear energy, renewable energies and efforts to combat climate change; monitoring and control-command service for infrastructure, facilities, equipment and apparatus in the fields of nuclear energy, renewable energies and efforts to combat climate change.

Abstract

The invention relates to a maintenance method comprising the repeated execution of an operating sequence, the operating sequence comprising the following steps: - (S10) acquiring an image by means an image acquisition member (35), the image showing the item of equipment (37) and an environment of the item of equipment (37); - (S12) comparing the image with the image acquired in the preceding operating sequence; - (S14) determining a position of the image acquisition member (35) with respect to the item of equipment (37) using the comparison; - (S16) displaying, in the image, a sign that allows the item of equipment (37) to be distinguished from its environment, in a given position with respect to the item of equipment (37), using the position of the image acquisition member (35) with respect to the item of equipment (37).

IPC Classes  ?

• G21C 17/003 - Remote inspection of vessels, e.g. pressure vessels
• G05D 1/00 - Control of position, course, altitude or attitude of land, water, air or space vehicles, e.g. using automatic pilots
• G21C 17/013 - Inspection vehicles
• G21C 17/017 - Inspection or maintenance of pipe-lines or tubes in nuclear installations

Goods & Services

Digital platform (IT) for design and validation of digital simulators intended for simulation of instrumentation and control of industrial installation operations and safety. Design and development of a digital platform (IT) for design and validation of digital simulators intended for simulation of instrumentation and control of industrial installation operations and safety; design and development of digital simulators intended for simulation of instrumentation and control of industrial installation operations and safety.

Goods & Services

Digital computer software platform, downloadable, for design and validation of digital simulators intended for simulation of instrumentation and control of industrial installation operations and safety; Digital computer software platform, recorded, for design and validation of digital simulators intended for simulation of instrumentation and control of industrial installation operations and safety Design and development of a digital computer software platform, downloadable, for design and validation of digital simulators intended for simulation of instrumentation and control of industrial installation operations and safety; Design and development of a digital computer software platform, recorded, for design and validation of digital simulators intended for simulation of instrumentation and control of industrial installation operations and safety; design and development of digital simulators intended for simulation of instrumentation and control of industrial installation operations and safety

Goods & Services

Scientific, surveying, electronic, electric, optical, weighing, measuring, signaling, checking, supervision and emergency life-saving apparatus, namely sensing and signaling devices for tracking and monitoring energy usage used in the nuclear energy industries; apparatus, instruments and devices for monitoring and surveillance of industrial installations in the fields of nuclear energy; apparatus and downloadable software for controlling the stability of industrial facilities in the fields of nuclear energy; apparatus and recorded software for controlling the stability of industrial facilities in the fields of nuclear energy; downloadable computer programs, software packages, software and alarms for monitoring and surveillance of industrial installations; recorded computer programs, software packages, software and alarms for monitoring and surveillance of industrial installations; downloadable computer programs, software packages and software for monitoring and surveillance of nuclear facilities used in the nuclear field; recorded computer programs, software packages and software for monitoring and surveillance of nuclear facilities used in the nuclear field; electric or electronic components, particularly semiconductors, semiconductor devices, electronic circuits and microcircuits, chips for the manufacture of integrated circuits, microprocessors, microcontrollers, field-programmable gate array networks and assemblies bundled together; expert system generator, namely, downloadable expert systems generation software, downloadable knowledge-based construction and operating development software; expert system generator, namely, recorded expert systems generation software, recorded knowledge-based construction and operating development software; apparatus and instruments, namely surveying machines, surveying compass needles, tripods for topographical uses; downloadable artificial intelligence software for monitoring, controlling, optimizing and supporting the operational management of industrial facilities; recorded artificial intelligence software for monitoring, controlling, optimizing and supporting the operational management of industrial facilities Construction and implementation service for research and engineering facilities and equipment, namely, construction of buildings and installation of equipment, in the fields of nuclear energy, renewable energies and efforts to combat climate change; installation and maintenance services for control, operational control and safety system facilities, being building automation equipment, in the field of energy Engineering services for research and development in the fields of computing and the nuclear field; services for scientific calculations, namely, design and engineering services aided or not by computers for the construction and maintenance of nuclear power plants and the equipment thereof; monitoring and control services for monitoring and controlling facilities and equipment in the field of microprocessor-controlled nuclear energy, monitoring and controlling facilities and pilot modules using interactive displays, in the field of computing and the nuclear field; diagnostics and technical consultancy expertise services with respect to the safety and control of facilities in the nuclear field; scientific and technological services, namely, technical research studies and analyses and diagnostics provided by engineers for the installation of control systems in the nuclear field; computer software maintenance; updating of computer software; artificial intelligence research services in the nuclear field; conducting safety tests for control-command of nuclear facilities; research in the field of controlled nuclear fusion technology; research work and scientific technical project studies in the field of nuclear energy, connectics and electronics; providing advice, expertise and engineering services in the fields of nuclear energy, connectics and electronics; monitoring services, namely technical reactor core monitoring services and providing information with respect to instrumentation and control-command of infrastructures, facilities, equipment and apparatus in the fields of nuclear energy, renewable energies and efforts to combat climate change; monitoring services, namely technical reactor core monitoring services and control-command service, namely, real-time control-command services for nuclear reactor core system for infrastructure, facilities, equipment and apparatus in the fields of nuclear energy, renewable energies and efforts to combat climate change

Abstract

The manufacturing method is intended for the manufacture of a nuclear fuel rod cladding (4) comprising a substrate (14) covered with a protective coating (16). The manufacturing method comprises providing the substrate (14) and applying the protective coating (16) to the substrate (14) by physical vapour deposition by sputtering, simultaneously employing two or more mutually different techniques of physical vapour deposition by sputtering.

IPC Classes  ?

• G21C 3/06 - CasingsJackets
• G21C 3/07 - CasingsJackets characterised by their material, e.g. alloys
• G21C 21/02 - Manufacture of fuel elements or breeder elements contained in non-active casings
• C23C 14/16 - Metallic material, boron or silicon on metallic substrates or on substrates of boron or silicon
• C23C 28/00 - Coating for obtaining at least two superposed coatings either by methods not provided for in a single one of main groups , or by combinations of methods provided for in subclasses and
• C23C 14/34 - Sputtering
• C23C 30/00 - Coating with metallic material characterised only by the composition of the metallic material, i.e. not characterised by the coating process
• H01J 37/34 - Gas-filled discharge tubes operating with cathodic sputtering

Abstract

The spot welding electrode has an active surface (14) for contact with a part to be welded (4, 6), wherein the active surface (14) is convex and profiled along a longitudinal axis (A).

IPC Classes  ?

• B23K 11/31 - Electrode holders
• B23K 11/11 - Spot welding
• B23K 101/04 - Tubular or hollow articles

Abstract

The invention relates to a nuclear fuel pellet which has a rotationally symmetrical shape about a central axis (B) and contains a fissile material, the pellet having concentric layers including a proximal layer (20), an intermediate layer (22) and a distal layer (24), in which the enrichment of fissile material within the pellet varies radially, the intermediate layer (22) comprising a high enrichment zone in which the enrichment is strictly greater than the enrichment in the proximal layer (20) and/or than the enrichment in the distal layer (24).

IPC Classes  ?

• G21C 3/04 - Constructional details
• 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
• G21C 3/58 - Solid reactor fuel

Abstract

Disclosed is a debris filter formed by a grid (32) having a first face (32A) and an opposite second face (32B), the grid (36) having passages (36) which extend between an inlet (36A) located on the first face (32A) and an outlet (36B) located on the second face (32B) and which allow a cooling fluid to flow through the grid (32), the grid (32) having a first zone (Z1) and at least one second zone (Z2) in which the grid (32) has a thickness greater than that of the grid (32) in the first zone (Z1), passages (36) being present in the first zone (Z1) and in each second zone (Z2).

IPC Classes  ?

• G21C 3/32 - Bundles of parallel pin-, rod-, or tube-shaped fuel elements
• G21C 3/33 - Supporting or hanging of elements in the bundleMeans forming part of the bundle for inserting it into, or removing it from, the coreMeans for coupling adjacent bundles
• B01D 29/01 - Filters with filtering elements stationary during filtration, e.g. pressure or suction filters, not covered by groups Filtering elements therefor with flat filtering elements
• B01D 35/02 - Filters adapted for location in special places, e.g. pipe-lines, pumps, stop-cocks

Abstract

Disclosed is a debris filter formed by a grid (32) having a first face (32A) and an opposite second face (32B), the grid (36) having passages (36) to allow a cooling fluid to flow through the grid (32), each passage (36) extending between an inlet (36A), located on the first face (32A) and having an inlet axis (A1), and an outlet (36B), located on the second face (32B) and having an outlet axis (A2), an inclination angle being defined between the inlet axis (A1) and the outlet axis (A2), the grid (32) comprising passages (36) having different inclination angles between their inlet axis (A1) and their outlet axis (A2).

IPC Classes  ?

• G21C 3/32 - Bundles of parallel pin-, rod-, or tube-shaped fuel elements
• G21C 3/33 - Supporting or hanging of elements in the bundleMeans forming part of the bundle for inserting it into, or removing it from, the coreMeans for coupling adjacent bundles
• B01D 35/02 - Filters adapted for location in special places, e.g. pipe-lines, pumps, stop-cocks
• B01D 29/01 - Filters with filtering elements stationary during filtration, e.g. pressure or suction filters, not covered by groups Filtering elements therefor with flat filtering elements

Abstract

The invention relates to a maintenance method for a control rod drive assembly. The method comprises the steps of: - removing the initial weld (67) from the omega seal (65) and removing the jacket (25); - performing at least one maintenance operation on the control assembly (17); - cutting an edge (69) of the first lip (61) of the omega seal (65); - obtaining a replacement jacket (25R) comprising a new second lip (71); - creating a new sealed weld (73) between the first lip (61) and the new second lip (71), the new weld (73) being angularly offset by an angle (α) of between 15° and 80° in relation to the initial weld.

IPC Classes  ?

• G21C 7/08 - Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
• G21C 13/028 - Seals, e.g. for pressure vessels or containment vessels
• G21C 19/20 - Arrangements for introducing objects into the pressure vesselArrangements for handling objects within the pressure vesselArrangements for removing objects from the pressure vessel

Abstract

The control system (1) comprises at least one cabinet (3) containing hardware components (5) comprising software components or giving access to software components. The monitoring method comprising: - determining a plurality of physical intrusion ways to the software components for which monitoring is desired; - providing tamperproof elements (23) at respective defined marking locations on the hardware components (5) and/or on the cabinet (3), each tamperproof element (23) having a unique identification code, the marking locations being chosen such that an intrusion through one of said physical intrusion ways causes at least one of the tamperproof elements (23) to be damaged; - storing in a database (35) a reference status comprising the unique identification code of the tamperproof elements (23) and the corresponding marking locations; and - during a monitoring phase, checking at least some of the marking locations and comparing with the reference status

IPC Classes  ?

• G06F 21/57 - Certifying or maintaining trusted computer platforms, e.g. secure boots or power-downs, version controls, system software checks, secure updates or assessing vulnerabilities

Abstract

The inspection method is for detecting a defect on an object, in particular a nuclear reactor component, e.g. a nuclear fuel assembly, the inspection method comprising the steps of: - obtaining a first image (F1) of a region of interest of the nuclear component; - inputting the first image (F1) to an autoencoder (34) configured for encoding the first image (F1) into an image code and decoding the image code to output a second image (F2); and - comparing the first image (F1) with the second image (F2) for detecting the representation of a defect in the first image (F1).

IPC Classes  ?

• G06T 7/00 - Image analysis

Abstract

The present application relates in particular to a welding method comprising the following successive steps: removing a layer of an inner surface (9) of the end (11, 13) of at least one of the pipes, thereby creating a recessed zone (15) extending in the inner surface (9) to the free edge (14); filling the recessed zone (15) by deposition of a stainless steel (17); welding the pipe ends (11, 13) to each other by end-to-end welding.

IPC Classes  ?

• B23K 9/00 - Arc welding or cutting
• B23K 9/028 - Seam weldingBacking meansInserts for curved planar seams
• B23K 9/167 - Arc welding or cutting making use of shielding gas and of a non-consumable electrode
• B23K 9/173 - Arc welding or cutting making use of shielding gas and of consumable electrode
• B23K 9/23 - Arc welding or cutting taking account of the properties of the materials to be welded
• B23K 9/235 - Preliminary treatment
• B23K 33/00 - Specially-profiled edge portions of workpieces for making soldering or welding connectionsFilling the seams formed thereby
• G21D 1/00 - Details of nuclear power plant
• F16L 13/02 - Welded joints
• G21C 17/017 - Inspection or maintenance of pipe-lines or tubes in nuclear installations
• B23K 101/06 - Tubes
• B23K 103/04 - Steel alloys

Abstract

Nuclear fuel element containing a core made of fissile material and a reinforcement cover and method of manufacturing the same The nuclear fuel element is configured for insertion into a cladding tube of a nuclear fuel rod, the nuclear fuel element extending along a central axis and comprising a fissile core made of fissile material and a reinforcement cover made of a thread winding and/or interlaced threads, the reinforcement cover surrounding the fissile core.

IPC Classes  ?

• G21C 3/06 - CasingsJackets
• G21C 3/07 - CasingsJackets characterised by their material, e.g. alloys
• 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
• G21C 21/02 - Manufacture of fuel elements or breeder elements contained in non-active casings

Abstract

The invention relates to a nuclear fuel cladding produced with a substrate (14), which is made of pure zirconium or of a zirconium-based alloy, and a multilayer protective coating (16), which covers a surface (14B) of the substrate (14), the protective coating (16) comprising a main layer (18) made of pure chromium and one or more additional layers (20), each additional layer (20) being made of pure chromium or from a material consisting of chromium and, additionally, oxygen and/or nitrogen, with the optional presence of unavoidable impurities.

IPC Classes  ?

• G21C 3/07 - CasingsJackets characterised by their material, e.g. alloys
• G21C 21/02 - Manufacture of fuel elements or breeder elements contained in non-active casings
• C23C 14/00 - Coating by vacuum evaporation, by sputtering or by ion implantation of the coating forming material
• B32B 9/00 - Layered products essentially comprising a particular substance not covered by groups

Abstract

The invention relates to a flow calming assembly (10) for a nuclear reactor comprising a vessel (12) and an enclosure (14) situated in the vessel (12) wherein a fluid circulates from the vessel (12) to the enclosure (14) at a bottom part of the vessel (12). The flow calming assembly (10) comprises an outer calming device (28) with openings for fluid passage, the outer calming device (28) comprising an upper part (34) and a lower part (36), the upper part (34) comprising a flared or conical collar extending between an upper end (38) and a lower end (40), the lower part (36) having a shape presenting a symmetry along a main axis (D), the lower part (36) extending from the lower end (40) of the upper part (34). The invention further relates to associated reactor and installing method.

IPC Classes  ?

• G21C 15/243 - Promoting flow of the coolant for liquids

Abstract

The invention relates to a method for the maintenance of an in-core neutron measuring device (3) of a nuclear reactor (1), which has a device (33) for selecting the measurement passage (11) into which the neutron measuring probe (25) is to be sent. The maintenance method comprises the following steps: - removing the input part (35) from the selection device (33); - attaching a replacement input part (63) to the selection device (33), the replacement input part (63) comprising a replacement input passage (65) having the same geometry as the input passage (31) of the input part (35); - inserting an adjustment probe (71) into the replacement input passage (65) and adjusting the detector (45); - removing the replacement input part (63) from the selection device (33); - placing the input part (35) back on the selection device (33).

IPC Classes  ?

• G21C 17/00 - MonitoringTesting
• G21C 17/108 - Measuring reactor flux
• G21C 17/116 - Passages or insulators, e.g. for electric cables
• G21C 19/02 - Details of handling arrangements
• G21C 19/19 - Reactor parts specifically adapted to facilitate handling, e.g. to facilitate charging or discharging of fuel elements
• G21C 19/20 - Arrangements for introducing objects into the pressure vesselArrangements for handling objects within the pressure vesselArrangements for removing objects from the pressure vessel

Abstract

The invention relates to a device (10) for raising or lowering a nuclear fuel assembly (12) out of and into a pool (14) of a nuclear facility, comprising: - a guide system (20); and - a vertically movable gondola (22) that defines a housing (24) for accommodating the nuclear fuel assembly and water; - a movable cover (28) for closing the gondola (22) in a watertight manner, the housing (24) containing a gas layer (44), or for allowing loading of the nuclear fuel assembly; - at least one sampling system (30) for providing at least one water sample (32) taken from the housing; and - a depressurization system (34) for extracting some of the gas layer and lowering the pressure in the housing (24) when the cover is closed.

IPC Classes  ?

• G21C 17/07 - Leak testing
• G21C 19/06 - Means for supporting or storing fuel elements or control elements
• G21C 19/07 - Storage racksStorage pools

Abstract

A test method is for testing a spacer grid (14) of a nuclear fuel assembly (2) comprising a bundle of nuclear fuel rods (4) and N spacer grids distributed along the bundle of nuclear fuel rods, where N is a positive integer equal to or greater than four. The method of testing includes providing a test assembly (20) comprising a bundle of test rods (20) shorter than the nuclear fuel rods and three spacer grids distributed along the test rods, generating an impact on the centrally located spacer grid, and measuring and recording at least one impact parameter and/or at least one displacement of said centrally located spacer grid.

IPC Classes  ?

• G21C 17/06 - Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination

Abstract

The invention relates to a wheel chock (23) comprising: - two wedges (25) arranged longitudinally on either side of a space (27) for accommodating the wheel (5); - a lateral member (37) delimiting the accommodating space (27) on a first transverse side and connecting respective first lateral sides of the two wedges (25) to one another, the lateral member (37) being made of a flexible material; - two partial lateral members (47) which delimit the accommodating space (27) on a second transverse side opposite the first and are secured to respective second lateral sides of the two wedges (25), the two partial lateral members (47) being separated from one another; the two wedges (25) having respective sloped surfaces (29) each with a planar region (31) for contact with the wheel (5), forming an angle (α) of between 15° and 45° with the lower plane I of the wedges.

IPC Classes  ?

• B65G 69/34 - Accessories, e.g. vehicle restrainers, wheel blockers, positioners or bumpers
• B65G 69/00 - Auxiliary measures taken, or devices used, in connection with loading or unloading
• B60T 3/00 - Portable devices for preventing unwanted movement of vehicles, e.g. chocks

Goods & Services

Downloadable computer software for use in computer network management; downloadable computer software for computer system security and enterprise system management; downloadable computer software for monitoring computer networks, computer systems security and computer enterprise systems; downloadable computer software for managing compliance and certification of computer networks, computer systems security and enterprise systems; downloadable software for assessing and correcting computer network vulnerabilities, intrusion detection, managing computer software updates, and managing regulatory compliance, security accreditation and certification Maintenance and updating of computer software; technical support services, namely, troubleshooting of computer software problems; computer hardware and computer software consultation in the fields of selection, implementation and use of computer hardware and software systems for others; computer network services, namely, configuring, maintaining and troubleshooting problems with computer network software systems and remote and on-site management of enterprise information technology systems for others; Computer system security services, namely, monitoring of computer systems for protecting data and information from unauthorized access and featuring assessment and correction of computer network vulnerabilities, network intrusion detection, compliance management and security accreditation, all for security purposes; providing temporary use of online non-downloadable computer software for use in computer network management; providing temporary use of online non-downloadable computer software for computer system security and enterprise system management; providing temporary use of online non-downloadable computer software for monitoring computer networks, computer systems security and computer enterprise systems; providing temporary use of online non-downloadable computer software for managing compliance and certification of computer networks, computer systems security and enterprise systems; providing temporary use of online non-downloadable computer software for assessing and correcting computer network vulnerabilities, intrusion detection, managing computer software updates, and managing regulatory compliance, security accreditation and certification

Abstract

The present invention concerns a computer implemented method for simulating an operation of a reactor core (7), the method comprising: determining (100) an initial state of the reactor core (7), the reactor core (7) comprising a plurality of fuel assemblies (10), wherein the core is partitioned in cubes to constitute nodes of a grid; calculating (102, 104), based on the initial state, a nodal target power distribution (p) and/or the target 3D neutron flux distribution (Φ); obtaining (106) an actual power distribution and/or the actual 3D neutron flux distribution of the nuclear reactor core; determining (108) a difference between the target power distribution (p) and the actual power distribution of the nuclear reactor core and/or determining (108) a difference (δΦ) between the target 3D neutron flux distribution (Φ) and the actual 3D neutron flux distribution of the nuclear reactor core; determining (110) modal expansion coefficients (δcℓ) using a Fourier modal decomposition based on the determined difference (δΦ) and applying a Modal Generalized Perturbation Theory, MGPT, to the modal expansion coefficients (δcℓ) for determining a 3D cross-section distribution perturbation (δΣ) causing the determined difference (δΦ); and determining (112) a 3D adaptation distribution (δx) for the determined difference (δΦ) based on the determined 3D cross-section distribution perturbation (δΣ).

IPC Classes  ?

• G21D 3/00 - Control of nuclear power plant
• G21C 17/00 - MonitoringTesting

Abstract

The plate-shaped nuclear fuel element (2) comprises a core (4) made of a fissile material and a cladding (6), the cladding comprising a frame (8) defining a central aperture (10) receiving the core (4) and two cover plates (12) sandwiching the frame (8) and the core (4), wherein the frame (8) is made of a metallic first cladding material and the cover plates (12) are made of a metallic second cladding material, the first cladding material having a hardness strictly greater than the hardness of the second cladding material.

IPC Classes  ?

• G21C 3/16 - Details of the construction within the casing
• G21C 3/58 - Solid reactor fuel
• G21G 1/02 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors

Abstract

The present invention relates to an ultrasound probe (10) for inspecting a component at a temperature above 150°C. The probe (10) comprises a shoe (14) that makes contact with the component and an ultrasonic transducer (16). The transducer comprises: - a probe body (24) defining an internal volume (30) having a body length (LC), the probe body further defining an aperture (32); - a disc (26) of piezoelectric material placed in the aperture, the disc having a front side (38) making contact with the shoe, the disc having an acoustic impedance comprised between 7 Mrayl and 25 Mrayl and a Curie temperature above 250°C; - a damper (28) fastened to the back side (40) of the disc and extending from the back side into the internal volume over a damper length (LA) smaller than the body length (LC).

IPC Classes  ?

• G01N 29/04 - Analysing solids
• G01N 29/22 - Investigating or analysing materials by the use of ultrasonic, sonic or infrasonic wavesVisualisation of the interior of objects by transmitting ultrasonic or sonic waves through the object Details
• G01N 29/24 - Probes
• B06B 1/06 - Processes or apparatus for generating mechanical vibrations of infrasonic, sonic or ultrasonic frequency making use of electrical energy operating with piezoelectric effect or with electrostriction

Abstract

The invention relates to a production method which comprises the following steps: - obtaining an initial metal oxide powder, consisting of particles of a metal oxide, by hydrolysing a chloride of said metal; - forming a suspension containing the initial metal oxide powder and an organic binder suspended in a suspension medium; and - drying the suspension so as to obtain granulated metal oxide powder, consisting of grains formed of agglomerates of particles of the initial metal oxide powder.

IPC Classes  ?

• C01G 1/02 - Oxides
• C01G 25/02 - Oxides
• C01G 27/02 - Oxides
• C04B 35/48 - Shaped ceramic products characterised by their compositionCeramic compositionsProcessing powders of inorganic compounds preparatory to the manufacturing of ceramic products based on oxides based on zirconium or hafnium oxides or zirconates or hafnates

Abstract

The monitoring method comprises, for each steam generator of a plurality of steam generators, and for at least one of the parameters of a set of parameters representative of the functioning of the steam generator: - the determination of a deviation between a measured value of the parameter for this steam generator and the mean value of this parameter for all of the steam generators, in order to detect an imbalance of this parameter on the steam generator; and - the characterization of the imbalance according to one or more other parameters of the set of representative parameters, so as to generate a signal of a physical problem or a signal of a measurement drift.

IPC Classes  ?

• F22B 35/00 - Control systems for steam boilers
• F22B 35/18 - Applications of computers to steam-boiler control
• G21D 3/00 - Control of nuclear power plant
• G21D 3/08 - Regulation of any parameters in the plant
• G21D 3/04 - Safety arrangements

Abstract

The manufacturing method comprises the obtaining of a core (4), the coating of the core (4) with an anti-diffusion layer (8) so as to obtain a coated core (10), the insertion of the coated core (10) into a cladding (6) with interposition, between the coated core (10) and the cladding (6), of one or more intermediate layers (12), and the pressing of the multilayer assembly (22) thus obtained, each intermediate layer (12) being made from a ductile metal alloy and/or a metal alloy having a conventional yield strength that does not differ by more than 30% from that of the material of the cladding (6), an elongation at break that does not differ by more than 30% from that of the material of the cladding (6) and/or a distributed relative elongation that does not differ by more than 30% from that of the material of the cladding (6).

IPC Classes  ?

• G21C 3/36 - Assemblies of plate-shaped fuel elements or coaxial tubes
• G21C 3/06 - CasingsJackets
• 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
• G21C 21/02 - Manufacture of fuel elements or breeder elements contained in non-active casings
• G21C 21/10 - Manufacture of fuel elements or breeder elements contained in non-active casings by extrusion, drawing, or stretching

Abstract

The bottom nozzle comprises a tubular body (16) having a lower opening (18) and an upper opening (20), a lower tie plate (24) extending across the upper opening (20) and a debris filter (28) received inside the tubular body (16) below the lower tie plate (24), wherein the bottom nozzle comprises connection members (32), each connection member (32) being configured for securing a lower end of a respective guide tube (12) of the nuclear fuel assembly to the lower tie plate (24) and being operable from below the debris filter (28) for attaching the guide tube (12) to the lower tie plate (24) and detaching the guide tube (12) from the lower tie plate (24).

IPC Classes  ?

• G21C 3/32 - Bundles of parallel pin-, rod-, or tube-shaped fuel elements
• G21C 3/33 - Supporting or hanging of elements in the bundleMeans forming part of the bundle for inserting it into, or removing it from, the coreMeans for coupling adjacent bundles
• G21C 3/334 - Assembling the bundles

Abstract

The top nozzle comprises an intermediate plate (26) axially positioned between an upper plate (24) and a lower plate (22) with being axially movable between an upper position and a lower position, one or several main spring member(s) (28) arranged such as to permanently push the intermediate plate (26) towards the upper plate (24), one or several spring member(s) (30) arranged to push to intermediate plate (26) towards the upper plate (24) when the intermediate plate (26) is located between the lower position and an intermediate position associated to this auxiliary spring member (30), and a preload element (32) associated to each auxiliary spring member (30) with being arranged such that the auxiliary spring member (30) abuts against the upper plate (24) via the preload element (32) when the intermediate plate (26) is located between the intermediate position associated to said auxiliary spring member (30) and the upper position.

IPC Classes  ?

• G21C 3/33 - Supporting or hanging of elements in the bundleMeans forming part of the bundle for inserting it into, or removing it from, the coreMeans for coupling adjacent bundles

Abstract

This control method comprises the following steps: S20/ acquiring current values of operating parameters of the reactor; S30/ iteratively, implementing the following sub-steps: S31/ generating a sequence of injection of neutron poison and/or water S32/ computing a variation in at least one characteristic quantity of the state of the core (3) of the nuclear reactor during said determined time interval using a power programme, current values of operating parameters and the injection sequence in question, the variation being computed using a predictive model of the core of the reactor; S33/ evaluating a cost function, using the computed variation; sub-steps S31/ to S33/ being repeated until a convergence criterion of the cost function is met; steps S20/ and S30/ being repeated with a period shorter than 60 minutes.

IPC Classes  ?

• G21C 7/22 - Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of a fluid or fluent neutron-absorbing material
• G21D 3/00 - Control of nuclear power plant
• G21D 3/10 - Regulation of any parameters in the plant by a combination of a variable derived from neutron flux with other controlling variables, e.g. derived from temperature, cooling flow, pressure
• G21D 3/16 - Varying reactivity

Goods & Services

Encoded, electronic, electromagnetic, photographic, cinematographic, optical data media with holograms, containing information, data and/or recorded elements, in particular in the nature of electronic labels, encoded adhesive labels, encoded barcode labels, labels with machine-readable codes, rapid response bidimensional barcode labels, magnetic labels, encoded badges, magnetic cards, electronic security tags, smart labels, RFID labels, labels with RFID chips [RFID], radio-frequency identification tags [RFID], encoded identification labels; Computing equipment, namely Computer software, in particular for the providing, entry, storage, security and administration of data and information from the aforesaid data media; Software for physical intrusion or network intrusion detection systems; Apparatus for recording, transmitting, processing and reproducing data and information from the aforesaid data media, Holograms; Electronica devices for detecting opening doors; Non-downloadable computer network security software. Paper; Cardboard; Printed matter, Including, in particular Tag labels, Vignettes. Sheets of plastic, namly Labels of plastic. Recording, transcription as well as management and compilation of data recorded on data media with security features; Data mining, Data management, Amongst others in relation to the following goods: Labels, Vignettes, Smart labels, RFID tags, the aforesaid goods being data media. Programming for computers, Design of data processing programs; Development of data processing programs; Computer network security services.

Abstract

The maintenance method is applied to a nuclear reactor (1) having at least one control assembly (17) for controlling a rod cluster control assembly (13) comprising a casing (21) for receiving a lifting mechanism (23) and a sheath (25) for receiving the control rod (15), a first lip (61) at an upper casing end (35) and a second lip (63) at a lower sheath end (43) forming an omega seal (65). The maintenance method comprises the following steps: - removing the first and second lips (61, 63); - carrying out at least one maintenance operation on the control assembly (17); - creating a welding surface (67) by machining the upper casing end (35); - creating a sealed welded connection (69) by welding the welding surface (67) and a complementary welding surface (73) provided at the lower end of the sheath or of a replacement sheath (71).

IPC Classes  ?

• G21C 19/20 - Arrangements for introducing objects into the pressure vesselArrangements for handling objects within the pressure vesselArrangements for removing objects from the pressure vessel
• G21C 13/032 - Joints between tubes and vessel walls, e.g. taking into account thermal stresses
• G21C 13/036 - Joints between tubes and vessel walls, e.g. taking into account thermal stresses the tube passing through the vessel wall, i.e. continuing on both sides of the wall

Abstract

A device (7) for raising or lowering a nuclear fuel assembly (12) in a pool (14) of a nuclear installation, comprising: - a guiding system (20) intended to be fastened to the pool, and - a basket (22) defining a housing (24) for receiving the nuclear fuel assembly and water (40) around the nuclear fuel assembly, the basket being mounted on the guiding system so as to be able to move translationally in a direction (V) that is intended to be substantially vertical, the basket comprising an upper end (32) defining a passage (33) intended to allow the nuclear fuel assembly to be loaded into the housing from above, and a lateral jacket (34) that is intended to encircle the nuclear fuel assembly about the direction (V) and that is seal-tight to water, and - at least one sampling system (62) suitable for delivering at least one water sample (68) sampled from the housing.

IPC Classes  ?

• G21C 17/07 - Leak testing
• G21C 19/08 - Means for heating fuel elements before introduction into the coreMeans for heating or cooling fuel elements after removal from the core
• G21C 19/07 - Storage racksStorage pools

Abstract

The invention relates to a control method which comprises, when no imbalance is detected between a primary power signal (S1) and a secondary power signal (S2), implementing a setpoint monitoring mode, in which the nuclear power plant is controlled in accordance with an operational power setpoint (COP), and in the event of detecting an imbalance, automatically implementing a power limitation mode, which comprises calculating a target equilibrium power (PEC) equal to or less than the primary power (P1) and equal to or less than the secondary power (P2), and controlling the nuclear power plant (2) in accordance with the target equilibrium power (PEC).

IPC Classes  ?

• 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
• G21D 3/00 - Control of nuclear power plant

Abstract

The invention relates to a method comprising the following steps: - attaching a plurality of proximity sensors (11) around the side surface of the load (3); - lifting and moving the load (3) using the lifting and moving device (7); - transmitting and displaying the signals generated by the proximity sensors (11) on at least one display device (15).

IPC Classes  ?

• B66C 13/46 - Position indicators for suspended loads or for crane elements
• B66C 15/04 - Safety gear for preventing collisions, e.g. between cranes or trolleys operating on the same track
• G01S 17/46 - Indirect determination of position data

Abstract

The spacer grid element define a cell (17) extending along an extension axis (A) for receiving a nuclear fuel rod (4) and exhibits a polygonal cross-section including at least three supporting sides (20) distributed around the extension axis (A), wherein each supporting side (20) comprises an inwardly protruding corrugation (24) onto which is formed at least one spring (32) for supporting a fuel rod (4) extending through the spacer grid element.

IPC Classes  ?

• G21C 3/356 - Spacer grids being provided with fuel element supporting members

Abstract

Connection arrangement for mechanically connecting a first element and a second element, such as a guide tube and a tie plate of a nuclear fuel assembly The connection arrangement is for the mechanical connection of a first element (4) having a connection portion (8) to a second element (6) having a housing (10), the connection arrangement comprising a connection ring (12) received inside the housing (10) with being pivotable between an insertion/extraction position allowing insertion/extraction of the connection portion (8) into the housing (10) and a connection position preventing extraction of the connection portion (8) from the housing (10), and a locking ring (20) axially movable along the center axis (A) between a locked position preventing rotation of the connection ring (12) and an unlocked position allowing rotation of the connection ring (12) between the connection position and the insertion/extraction position.

IPC Classes  ?

• G21C 3/334 - Assembling the bundles
• F16B 7/20 - Connections of rods or tubes, e.g. of non-circular section, mutually, including resilient connections using bayonet connections

Goods & Services

Metal oxides; metal salts; hafnium oxides; hafnium salts.

Abstract

The platform (1) comprises: a floor (17) comprising beams (19) and removable slabs (21) carried by the beams (19); a floating support (13), arranged to float on the water filling a pool of the nuclear facility, a peripheral edge of the floor (17) resting on the floating support (13).

IPC Classes  ?

• G21C 17/013 - Inspection vehicles
• G21C 17/003 - Remote inspection of vessels, e.g. pressure vessels
• B63B 35/00 - Vessels or similar floating structures specially adapted for specific purposes and not otherwise provided for

Abstract

The invention concerns a method and system for accelerating the convergence of an iterative computation code of physical parameters of a multi- parameter system, in particular in the field of fluid dynamic computation. The method comprises obtaining (12,14) first parameter values, of first dimensionality by applying the iterative computation code. The method further comprises applying (18) a data dimensionality reduction on at least a part of the first parameter values of first dimensionality to compute representative second parameters of second dimensionality smaller than the first dimensionality; applying (20) an extrapolation on at least a subset of the second parameters of second dimensionality to predict a set of predicted second parameter values, computing (22) predicted first parameter values from the predicted second parameter values, and using the predicted first parameter values as an input data set for a new iterative computation with the iterative computation code.

IPC Classes  ?

• G06F 17/11 - Complex mathematical operations for solving equations
• G06F 30/28 - Design optimisation, verification or simulation using fluid dynamics, e.g. using Navier-Stokes equations or computational fluid dynamics [CFD]

Abstract

This method for assisting with surveillance of an element of a nuclear reactor, which method is implemented by an electronic device, comprises the steps of: - (120) training an artificial-intelligence algorithm; - (140) acquiring an image of the element; - (150) estimating, on the basis of the image and via the artificial-intelligence algorithm, whether a fault is present in the element; - (160) displaying the image of the element; and - if at least one fault is estimated to be present, (170) generating an alarm. In the estimating step, an input of the artificial-intelligence algorithm is an image of a region comprising the element, and an output is a level of confidence as regards an absence of fault in the element for said region. If the level of confidence is lower than a threshold, then a fault is estimated to be present. In the training step, only images of fault-free elements are input into the artificial-intelligence algorithm.

IPC Classes  ?

• G21C 17/08 - Structural combination of reactor core or moderator structure with viewing means, e.g. with television camera, periscope, window
• G21D 3/00 - Control of nuclear power plant
• G06K 9/62 - Methods or arrangements for recognition using electronic means
• G06N 7/00 - Computing arrangements based on specific mathematical models
• G06T 7/00 - Image analysis
• G06V 20/52 - Surveillance or monitoring of activities, e.g. for recognising suspicious objects
• G21C 17/00 - MonitoringTesting

Goods & Services

Scientific, surveying, measuring, signalling, checking (supervision) apparatus and instruments; apparatus and instruments for conducting, switching, transforming, accumulating, regulating or controlling electricity; magnetic data carriers; computer operating systems for use in nuclear safety; sensors; neutron detectors; electric actuators; signal conditioning and communication devices for industrial process control; racks adapted for scientific, surveying, measuring, signalling, checking (supervision) apparatus; digital controls; software operating systems for use in nuclear safety. Industrial analysis and research services; design and development of computer hardware and software; installation, maintenance and repair of computer software.

Abstract

The inspection system comprises a supporting device (20) for supporting the fuel pellet(s) (4) such that the pellet axis (A) of each fuel pellet (4) coincides with a reference axis (B), and an optical measuring device (40) arranged for optically measuring the fuel pellet(s) (4), the optical measuring device (40) comprising a light emitter (42) configured for emitting a light beam propagating along an optical axis (C) and a light detector (46) arranged for receiving the light beam (44), wherein each fuel pellet (4) interrupts the light beam (44) and generates a shadow projected on the light detector (46), the optical measuring device (40) comprising a measuring module (48) configured for analyzing the shadow for detecting possible defects on the end faces (10) and/or the lateral face (8) of each fuel pellet (4).

IPC Classes  ?

• G21C 3/04 - Constructional details
• G21C 17/06 - Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
• G21C 21/00 - Apparatus or processes specially adapted to the manufacture of reactors or parts thereof

Abstract

The invention relates to a method and assembly for inspecting a plurality of elements of an industrial plant. The method comprises the following steps: a/ creating an application (3) having a user interface (5) with one command (7) for each element to be inspected; b/ repeatedly acquiring image data of the elements of the industrial plant using a mobile device (13), and storing these image data in an acquisition memory (15), each item of image data comprising at least one image and a time stamp indicating a time at which the image data was acquired; c/ activating the commands (7) at respective activation times; d/ associating the image data with the elements, the image data associated with a given element being exclusively selected from the image data having a time stamp between the activation time of the command corresponding to said image element and the activation time of the preceding or following command.

IPC Classes  ?

• G06F 16/58 - Retrieval characterised by using metadata, e.g. metadata not derived from the content or metadata generated manually

Abstract

The nuclear fuel rod comprises nuclear fuel contained in a cladding (4), the cladding (4) comprising a tube (6) and two end caps (8), the tube (6) extending along a central axis (A) and having two ends, each end cap (8) being fastened to a respective end of the tube (6), sealingly closing this end. The tube (6) is covered by a tube coating (16) extending over the entire length of the tube (16), from one end of the tube (6) to the other.

IPC Classes  ?

• G21C 3/07 - CasingsJackets characterised by their material, e.g. alloys
• G21C 3/10 - End closures
• G21C 21/02 - Manufacture of fuel elements or breeder elements contained in non-active casings
• B23K 11/00 - Resistance weldingSevering by resistance heating
• B23K 11/093 - Seam welding not restricted to one of the preceding subgroups for curved planar seams
• B23K 11/16 - Resistance weldingSevering by resistance heating taking account of the properties of the material to be welded
• B23K 11/18 - Resistance weldingSevering by resistance heating taking account of the properties of the material to be welded of non-ferrous metals
• C23C 30/00 - Coating with metallic material characterised only by the composition of the metallic material, i.e. not characterised by the coating process
• C23C 28/02 - Coating for obtaining at least two superposed coatings either by methods not provided for in a single one of main groups , or by combinations of methods provided for in subclasses and only coatings of metallic material
• F16L 57/06 - Protection of pipes or objects of similar shape against external or internal damage or wear against wear
• B23K 101/12 - Vessels
• B23K 101/34 - Coated articles
• B23K 103/08 - Non-ferrous metals or alloys
• B23K 103/18 - Dissimilar materials

Abstract

The extraction device (10) comprises an attachment portion (12) configured to be inserted into a sleeve (4) of the rod (2) through an end without a cap, and a grip portion (14), the attachment portion (12) comprising an elongate body (16) following a longitudinal axis (A) and at least one tooth (18) projecting from the body (16), the or each tooth (18) being configured to allow the attachment portion (12) to be forcibly inserted into the sleeve (4) axially, and to engage with the internal surface (4A) of the sleeve (4) so as to prevent the attachment portion (12) from being extracted from the sleeve (4).

IPC Classes  ?

• G21C 3/334 - Assembling the bundles
• G21C 19/20 - Arrangements for introducing objects into the pressure vesselArrangements for handling objects within the pressure vesselArrangements for removing objects from the pressure vessel
• G21C 19/26 - Arrangements for removing jammed or damaged fuel elements or control elementsArrangements for moving broken parts thereof

Goods & Services

(1) Poudres d'oxydes métalliques à usage industriel, sels métalliques en poudre à usage industriel, oxydes de hafnium à usage industriel et à usage scientifique et de recherche médicale.

Goods & Services

metal oxide powders for industrial purposes; metal salts in powder form for industrial purposes; hafnium oxides for industrial purposes and for scientific or medical-research use; hafnium salts for industrial purposes and for scientific or medical-research use

Abstract

The manufacturing method makes it possible to obtain a nuclear reactor component comprising a substrate (4) and a coating (8) covering a surface (4A) of the substrate. The manufacturing method comprises laser marking a pattern (6) on the surface (4A) of the substrate (4), the marking being carried out in such a way so as to form hollow raised portions (10) forming the pattern (6) in the surface (4A) of the substrate (4), and subsequently applying the coating (8) to the surface (4A) of the substrate (4), above the pattern (6).

IPC Classes  ?

• G21C 3/06 - CasingsJackets
• G21C 17/06 - Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
• G21C 21/02 - Manufacture of fuel elements or breeder elements contained in non-active casings
• G21C 3/04 - Constructional details

Abstract

The non-destructive inspection system comprises a base (14), an inspection head (16) carrying one or several inspection probe(s) (48), a chain (18) having a distal end (20) supporting the inspection head (16), the chain (18) being movable relative to the base (14) via a driving unit (28) configured for driving the chain (18) to selectively push the inspection head (16) away from the base (14) and pull the inspection head (16) closer to the base (14).

IPC Classes  ?

• G21C 17/007 - Inspection of the outer surfaces of vessels
• B23Q 1/25 - Movable or adjustable work or tool supports
• B25J 18/00 - Arms
• F16G 13/00 - Chains

Goods & Services

Soldering chemicals. Rods of metal for welding. Welding apparatus and instruments; Machining (Apparatus for -). Machining of parts for others, Metalworking, Welding, Mechanical processing of metals. Engineering, research and development.

Goods & Services

Soldering chemicals. Rods of metal for welding. Welding apparatus and instruments; Machining (Apparatus for -). Machining of parts for others, Metalworking, Welding, Mechanical processing of metals. Engineering, research and development.

Goods & Services

(1) Scientific apparatus and instruments for surveying, measuring, signalling, and supervising power plants namely analog electronic sensors, digital electronic sensors, analog printed circuit board (PCB) hardware, digital printed circuit board (PCB) hardware for power plants; apparatus and instruments for conducting, switching, transforming, accumulating, regulating or controlling electricity; blank magnetic data carriers for use in power plants, namely, blank magnetic disks, blank magnetic computer tapes, blank hard disks; computer operating systems for use in nuclear safety; analog electronic sensors and digital electronic sensors for use in safety installation of power plant, not for medical purposes; neutron detectors; electric valve actuators for use in power plants, electric linear actuators for use in power plants; analog devices and digital processor for signal conditioning and communication for industrial process control for use in power plants namely analog devices for signal conditioning and digital processor for signal conditioning, transmitters of electronic cable signals; racks in the nature of stands adapted for analog printed circuit board (PCB) hardware for power plants and racks in the nature of stands adapted for digital printed circuit board (PCB) hardware for power plants, surveying, measuring, signalling, checking (supervision) apparatus; power controllers namely microcontrollers , low power microcontrollers; software operating systems for use in nuclear safety. (1) Scientific and technological services namely, industrial analysis and research services in the field of electrical power generation; design and development of computer hardware and software; installation, maintenance and repair of computer software.

Goods & Services

Oxides of metal; Metal salts; Hafnium oxides; Hafnium salts.

Abstract

The method for determining the burnup rate of a nuclear fuel element (2) comprises determining the burnup rate of the nuclear fuel element (2) as a function of a coloration of an outer surface of a cladding (4) of the nuclear fuel element (2).

IPC Classes  ?

• G21C 17/06 - Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
• G21C 3/06 - CasingsJackets

Abstract

The nuclear fuel cladding element comprises a substrate (16) made of a material based on zirconium and a protective coating (18) externally covering the substrate (16), the protective coating (18) being made of a material based on chromium, and having a columnar microstructure composed of columnar grains (20) and having on its outer surface (18B) a microdroplet density of less than 100 per mm2.

IPC Classes  ?

• G21C 3/07 - CasingsJackets characterised by their material, e.g. alloys

Goods & Services

Scientific, surveying, measuring, signalling, checking (supervision) apparatus and instruments; apparatus and instruments for conducting, switching, transforming, accumulating, regulating or controlling electricity; magnetic data carriers; computer operating systems for use in nuclear safety; sensors; neutron detectors; electric actuators; signal conditioning and communication devices for industrial process control; racks adapted for supporting the conditioning and processing of scientific, surveying, measuring, signalling, checking (supervision) apparatus; digital controls; software operating systems for use in nuclear safety. Industrial analysis and research services; design and development of computer hardware and software; installation, maintenance and repair of computer software.

Goods & Services

Scientific apparatus and instruments for surveying, measuring, signaling, and supervising power plants, namely, electronic sensors and printed circuit board (PCB) hardware for power plants; apparatus and instruments for conducting, switching, transforming, accumulating, regulating or controlling electricity in a nuclear power plant; blank magnetic data carriers for use in power plants; recorded computer operating systems for use in nuclear safety; electronic sensors for use in safety installation of power plant, not for medical purposes; scientific apparatus, namely, neutron detectors; electric actuators for use in power plants; signal conditioning and communication devices for industrial process control for use in power plants; racks in the nature of stands adapted for printed circuit board (PCB) hardware for power plants; power controllers, namely, digital controls in the nature of printed circuit board hardware components and recorded computer operating software sold as a unit for use in control systems and instrumentation of power plants; recorded operating system software for use in nuclear safety

Goods & Services

Computer software for use in computer network management; computer software for computer system security and enterprise system management; computer software for monitoring computer networks, computer systems security and computer enterprise systems; computer software for managing compliance and certification of computer networks, computer systems security and enterprise systems; software for assessing and correcting computer network vulnerabilities, intrusion detection, managing computer software updates, and managing regulatory compliance, security accreditation and certification. Maintenance and updating of computer software; technical support services, namely, troubleshooting of computer software problems; consultation services in the fields of selection, implementation and use of computer hardware and software systems for others; computer network services, namely, configuring, maintaining and troubleshooting computer network software systems and remote and on-site management of enterprise systems for others; computer system security services, namely, monitoring of computer systems for security purposes, namely, assessing and correcting computer network vulnerabilities, network intrusion detection, compliance management and security accreditation.

Abstract

The digitally-controlled machining device (1) comprises a control console (3) and a digitally-controlled machining machine (5). The training assembly (33) comprises: - a training control console (35) substantially identical to the control console (3) of the digitally-controlled machining device (1); - a digital duplicate (36) of the digitally-controlled machining machine (5) comprising a simulator (37) configured to simulate the effect of the commands from the training control console (35) on the digitally-controlled machining machine (5); - a display device (39) configured so that an operator in training can view the current state of the simulator (37).

IPC Classes  ?

• G05B 19/4069 - Simulating machining process on screen

Goods & Services

Computer software for use in computer network management; computer software for computer system security and enterprise system management; computer software for monitoring computer networks, computer systems security and computer enterprise systems; computer software for managing compliance and certification of computer networks, computer systems security and enterprise systems; software for assessing and correcting computer network vulnerabilities, intrusion detection, managing computer software updates, and managing regulatory compliance, security accreditation and certification. Maintenance and updating of computer software; technical support services, namely, troubleshooting of computer software problems; consultation services in the fields of selection, implementation and use of computer hardware and software systems for others; computer network services, namely, configuring, maintaining and troubleshooting computer network software systems and remote and on-site management of enterprise systems for others; Computer system security services, namely, monitoring of computer systems for security purposes, namely, assessing and correcting computer network vulnerabilities, network intrusion detection, compliance management and security accreditation.

Abstract

The invention relates to a platform that is configured to span a pool (4) of a nuclear power plant, being movable along two parallel rails (6) disposed on either side of the pool (4). The platform comprises at least one platform module (16) having a module floor (18) defining at least one portion of a platform floor (14) and two sets of guides (20) for interacting with the rails (6) for guiding the platform along said rails (6). Each platform module can be extended so as to vary the spacing between the two sets of guides (20) of the platform module (16), the two sets of guides (20) being brought together in a storage configuration and separated in a use configuration.

IPC Classes  ?

• G21C 19/18 - Apparatus for bringing fuel elements to the reactor charge area, e.g. from a storage place
• 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
• G21D 1/02 - Arrangements of auxiliary equipment
• B66C 19/00 - Cranes comprising trolleys or crabs running on fixed or movable bridges or gantries
• G21C 19/02 - Details of handling arrangements

Goods & Services

Computer software for voice and video over Internet or for screen sharing or for digital file transfer dedicated to brodcasting of live or recorded remote audit, inspection or visit of industrial installation or industrial process or product qualification. Providing voice and video over internet services or screen sharing services or digital file transfer services in the field of live or recorded remote audit, inspection or visit of industrial installation or industrial process or product qualification.

Abstract

The invention concerns a thermal sleeve (60) for a control rod drive mechanism of a nuclear reactor pressure vessel (4). The thermal sleeve (60) comprises : - a tube (62) comprising an upper end (68) and a lower end, the tube (62) comprising also an outer surface (70) and an inner surface (72), the outer surface (70) and the inner surface (72) extending from the upper end (68) to the lower end; - a plurality of protrusions (64) disposed at the upper end (68) of the tube (62), each protrusion (64) extending radially outward the tube (62); and - a collar (66) protruding radially outward the outer surface (70) of the tube (62) and extending circumferentially all around the tube (62), away from the upper end (68).

IPC Classes  ?

• G21C 7/14 - Mechanical drive arrangements

Abstract

The inventions concerns a method of determination of a nuclear core loading pattern defining the disposition of fuel assemblies (40) in the nuclear core, the method comprising the following steps: - definition of at least one potential core loading pattern, - calculation of predictive bowing of the fuel assemblies (40) at the end of the operation cycle for each potential core loading pattern, the calculation being carried out by an automatic learning algorithm trained on a training data set comprising a plurality of others loading patterns and, for each of them, the measures of bowing of fuel assemblies (40) at the end of cycle, - evaluation of the at least one core loading pattern based on the predictive bowing calculations and at least one predetermined criteria, and - selection of one of the potential core loading patterns.

IPC Classes  ?

• G21D 3/00 - Control of nuclear power plant
• G21C 19/20 - Arrangements for introducing objects into the pressure vesselArrangements for handling objects within the pressure vesselArrangements for removing objects from the pressure vessel

Goods & Services

Metal oxides; metal salts; hafnium oxides; hafnium salts.

Goods & Services

Metal oxides; metal salts; hafnium oxides; hafnium salts.