The present invention relates to a method for dynamically controlling corrosion in a steam- water circuit of a nuclear power plant, the method comprising: injecting the compounds ethanolamine and optionally ammonia, the system comprising: injection units, located at a dosing point and configured for injecting the compounds ethanolamine and ammonia in the fluid circulating in the circuit; and measurement units, configured for measuring a value of the parameters pH and at least one of the parameters selected from redox potential and corrosion potential in the circuit; the system being characterized in that it further comprises a control unit, the control unit comprising: a first acquisition module, connected to the measurement unit and configured for acquiring the measured values of the parameters and configured for acquiring at least one set-point value for said parameters; a command module, connected to the injection units and configured for commanding the injection of the compounds ethanolamine and ammonia by the injection unit as a function of the acquired at least one set-point value and measured values of the parameters, characterized in that ethanolamine is used as reducing agent. The present invention further relates to a system for dynamically controlling corrosion in a steam-water circuit of a nuclear power plant.
A method is for automatically mapping the radiation in a portion of a building (7) using a robot vehicle (1). The portion of the building includes a plurality of building surfaces (9, 10). The method includes acquiring (1010) a 3D map (42) of a portion of a building (7). The 3D map (42) includes a plurality of segments (44), each representing a substantially flat building surface. The method further comprises applying (1020) to each segment (44) a plurality sectors forming a grid of sectors (46), each sector (46) having a border (48); physically marking, by the robot vehicle (1), the border (48) of each sector (46) with paint on the corresponding building surface (9, 10); and for one or more sectors (46), scanning, by the robot vehicle (1), with a radiation sensor (28) each sector (46), to measure the radioactive radiation within that sector.
A ventilation and air-conditioning system for a room includes a cooling air supply system, a supply air duct system and at least one enclosure. The enclosure includes an inlet, an outlet, and heat storage elements. The ventilation and air-conditioning system is configured such that when the operation of the cooling air supply system fails, a natural convection airflow occurs through the enclosure from the inlet to the outlet, the natural convection airflow being cooled by transferring heat to the heat storage elements. The supply air duct system is arranged above the inlet at a distance from the inlet. A gap is defined between the supply air duct system and the inlet. The inlet of the enclosure is adapted to be in constant flow communication with the room by air flowing from the room through the gap into the inlet of the enclosure.
The invention relates to a method for automatically mapping the radiation in a portion of a building (7) and/or of a portion of a transport object using a robot vehicle (1), the portion of the building and/or of the transport object comprising a plurality of surfaces (9, 10), the method comprising: acquiring (1010) a 3D map (42) of a portion of a building (7) and/or of a portion of a transport object, wherein the 3D map (42) comprises a plurality of segments (44), each representing a surface (9, 10) of the building and/or of the transport object; applying to each segment a plurality sectors forming a grid of sectors, each sector having a border; physically marking, by the robot vehicle, at least a portion of the border of each sector (46) with paint on the corresponding surface (9, 10); and mapping the radiation for one or more sectors (46), by scanning, by the robot vehicle, with a radiation sensor (28) each sector of the one or more sectors, to measure the radioactive radiation within that sector, wherein the method further comprises: rendering at least one 3D image based on at least one portion of the 3D Map; sending the at least one rendered 3D image to at least one screen (62, 66) of a virtual reality system being arranged remotely from the robot vehicle; detecting commands from a commanding device (64) of the virtual reality system (60); transmitting the commands to the robot vehicle; and operating the robot vehicle in response to the commands.
This cargo system (12) comprises: - an envelope (16) having a bottom and delimiting an inner space (24); and - a damping apparatus (18) arranged inside the inner space (24) configured for damping vibrations of the envelope (16), the apparatus (18) comprising: + a first support (26) and a second support (28), + a first support spring (30), connecting the first support (26) to the bottom (20), and a second support spring (32), connecting the second support (28) to the bottom (20), each support spring (30, 32) being coiled along a support spring axis (S) parallel to the bottom (20), and + a damping mass (34), guided on the first support (26) along a first direction (A) and on the second support (28) along a second direction (B), the first (A) and second (B) directions being perpendicular and being both parallel to the bottom (20).
F16F 7/10 - Vibration-dampersShock-absorbers using inertia effect
F16F 15/067 - Suppression of vibrations of non-rotating, e.g. reciprocating, systemsSuppression of vibrations of rotating systems by use of members not moving with the rotating system using elastic means with metal springs using only wound springs
6.
CARNOT BATTERY HAVING A HEAT GENERATOR, AND METHOD FOR CONVERTING ENERGY BY MEANS OF THE CARNOT BATTERY
A Carnot battery (2), comprising a heat generator (8) for heating a fluid by electric current and a heat store (10) for storing heat of the fluid heated by the heat generator (8), wherein the Carnot battery (2) also comprises a converter (12) for converting the heat into electricity and/or a branch (13A) of the heat store (10) for providing the heated fluid, wherein the heat generator (8) has a plurality of tubes (18) between at least one inlet (14) and at least one outlet (16), wherein the tubes (18) are fluidically connected in parallel. At least one phase of the electric current is applied directly to the tubes (18) at an input terminal (20), and the input terminal (20) is arranged electrically between the at least one inlet (14) and the at least one outlet (16) of the heat generator (8), and an output terminal (22) for the electric current is connected to ground (G).
The present invention relates to a safety condenser (25) intended to be connected to a steam generating component (14, 7') in a water-cooled nuclear reactor (3, 120) comprising: - a heat exchanger (26) partially arranged in a pool (30) containing a cooling fluid, the heat exchanger (26) comprising a bundle of parallel heat exchanger tubes (52), the heat exchanger tubes extending in a vertical direction between a lower tube sheet (60) and a upper tube sheet (58), each heat exchanger tube (52) being intended for receiving a downward flow of steam from the steam generating component (14, 7'), the heat exchanger comprising an inlet (72), intended for receiving steam generated in the steam generating component(7', 14), the heat exchanger (26) being configured for cooling this steam through heat exchange with the cooling fluid contained in the pool (30) to produce condensate and an outlet (70), configured for returning the condensate to the steam generating component; and - a cooling capacity regulator (100), configured for controlling the cooling capacity of the safety condenser (26) by adjusting the height of the condensate in the heat exchanger tubes, wherein the heat exchanger (26) further comprises a lower end dome (56) connected to the lower tube sheet (60) and comprising the outlet (70) intended to be connected to the steam generating component (7', 14) and upper end dome (54) connected to the upper tube sheet (58) and comprising the inlet (72) intended to be connected to an outlet pipe (92) of the steam generating component (7', 14), the lower end dome (56) and the upper end dome (54) being located outside of the pool (30).
The present invention relates to a method for measuring the lithium concentration and boron acid concentration in an aqueous solution, comprising: acquiring the temperature of the solution, and applying an input voltage on a pair of electrodes within the solution, characterized in that the input voltage is an alternating voltage with at least two different frequencies, wherein the method further comprises the following steps: acquiring for each frequency at least one impedance value of the impedance between the electrodes of the pair of electrodes, and determining the lithium concentration and the boric acid concentration by comparing at least one of the acquired impedance values with a set of calibration functions of a plurality of calibration functions, wherein the calibration functions for the set of calibration functions are selected from the plurality of calibration functions depending on the acquired temperature and being at the frequency used for the acquisition of the respective impedance value.
This spot welding gun (12), comprises a frame (18) and a movable group (20), movable along a welding direction (W-W') within the frame (18) and comprising: - an outer unit (28) comprising a proximal electrode (34) and an outer actuation flange (38), - an inner unit (30) comprising a distal electrode (44) and an inner actuation flange (48), - a clamping actuator (32) being connected to the inner actuation flange (48) and to the outer actuation flange (38), and configured for displacing said flanges (38, 48) to displace the proximal electrode (34) relatively to the distal electrode (44) along the welding direction (W-W'), the gun (12) comprising a compensation actuator (21), arranged between the frame (18) and the movable group (20), the compensation actuator (21) being configured to exert a biasing force to compensate the weight of the movable group (20) depending on an orientation of the welding direction (W-W').
The invention relates to a nuclear power plant (1) comprising a containment structure (2) and a pressure vessel (4) received in the containment structure (2), the pressure vessel (4) containing the core (5) of the nuclear power plant (1) during normal operation of the nuclear power plant (1), the containment structure (2) defining a spreading compartment (6) configured for receiving molten material including molten core material from the core (5) in the event of a core meltdown, wherein the nuclear power plant (1) furthermore comprises a core catcher (8) arranged in the spreading compartment (6) and comprising a lateral wall (16) and a bottom wall (18) interiorly delimiting a reception space (20) intended for receiving the molten material. The core catcher (8) comprises a convection barrier (14), arranged within the reception space (20) delimited by the lateral wall (16) and the bottom wall (18).
A nuclear power plant comprises a system for degasification of a gaseous liquid, the system comprising a separation vessel having at least one outer wall delimiting an inner volume and configured for separating gas from the gaseous liquid, at least one inlet adapted to introduce the gaseous liquid into the inner volume, at least one gas suction line attached to the separation vessel and being adapted to discharge the separated gas from the inner volume, at least one outlet adapted to discharge a degassed liquid from the inner volume, and a sonotrode cluster configured to expose the gaseous liquid to ultrasonic waves.
G21C 19/307 - Arrangements for introducing fluent material into the reactor coreArrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products specially adapted for liquids
The present invention relates to a cutting device (3) for cutting a plurality of parallel fingers (7) of at least one core component (5) in a plane orthogonal to the longitudinal axis of the fingers (7), the fingers (7) being adapted to be introduced into the fuel assembly of a nuclear reactor core, the cutting device (3) comprising: a first bearing plate (30, 46) comprising a plurality of abutments (54, 56) respectively for a finger (7) to be cut, wherein the cutting device (3) further comprises: a rotatable cutting plate (34) comprising a corresponding cutting blade (42a, 42b, 42c) for each abutment (54, 56) in the first bearing plate, the rotatable cutting plate (34) being rotatable about a rotating axis (Y) between a starting position and a final position in a circumferential direction (C), the first bearing plate (30, 46) and the cutting plate (34) being parallel to each other, the cutting blades (42a, 42b, 42c) comprising a plurality of groups of cutting blades (42a, 42b, 42c), wherein for each group of cutting blades (42a, 42b, 42c) the angle between the cutting blades (42a, 42b, 42c) and the corresponding abutments (54, 56) is different to an angle between the cutting blades (42a, 42b, 42c) and the corresponding abutments (54, 56) of any other group of cutting blades.
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
The present invention relates to a method for controlling a pressurized water reactor (3), the pressurized water reactor (3) comprising a reactor core (5) and a primary cooling circuit (10) comprising a primary cooling medium, the method comprising: acquiring (1010) a plurality of measurable reactor process variables; obtaining (1020) a plurality of non- measurable reactor process variables; wherein the method further comprises: calculating (1030) future axial offsets (AO) at the end of a predetermined prediction time interval for a plurality of different possible boration/dilution actions based on the plurality of measurable reactor process variables and the plurality of non-measurable reactor process variables, the axial offset being a normalized difference between power of an upper half of the reactor core (5) and a lower half of the reactor core (5), wherein the calculation of the future axial offset for each of the plurality of different possible boration/dilution actions is performed in parallel; determining a boration/dilution action to be performed based on the calculated future axial offsets, AO, for the plurality of different possible boration/dilution actions and corresponding reference axial offsets, AOref; and commanding the determined boration/dilution action (1050) in the primary cooling circuit (10).
The present invention relates to a fuel assembly (1) for a nuclear power plant, the fuel assembly (1) comprising at least one hollow rod (9, 9a,9b, 9c), the hollow rod being a control rod guide tube (9) of the fuel assembly (1) for the control rod assembly or an instrumentation tube, each rod (9) is adapted to be filled with one or more containers (38) filled with material to be activated, wherein the fuel assembly further comprises a damping element (36, 36a, 36b, 36c) at the lower end (32) of the hollow rod (9, 9a,9b, 9c).
G21C 3/326 - Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different compositionComprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
G21C 7/103 - Control assemblies containing one or more absorbants as well as other elements, e.g. fuel or moderator elements
G21C 7/20 - Disposition of shock-absorbing devices
G21C 19/105 - Lifting devices or pulling devices adapted for co-operation with fuel elements or with control elements with grasping or spreading coupling 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
G21C 23/00 - Adaptations of reactors to facilitate experimentation or irradiation
G21G 1/02 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
G21C 7/117 - Clusters of control rodsSpider construction
15.
INSTALLATION AND METHOD FOR PRODUCING ACTIVATED IRRADIATION TARGETS IN AN INSTRUMENTATION TUBE SYSTEM OF A NUCLEAR REACTOR
A decay station includes a housing comprising a radiation shielding. The housing delimits a decay conduit intended for containing the irradiation targets in the predetermined linear order. The decay conduit includes a decay conduit inlet, intended to be connected to the structure of the core of the nuclear reactor for receiving the irradiation targets therefrom; and a decay conduit outlet, intended to be connected to an irradiation target discharge system for discharging the irradiation targets from the decay station. The decay station further includes an inlet distributor, located at the decay conduit inlet, and configured for releasing only a predetermined amount of irradiation targets at a time from the decay station towards the structure of the core of the nuclear reactor. The inlet distributor is configured for releasing the irradiation targets closest to the decay conduit inlet, while retaining the remaining irradiation targets in the decay conduit. The decay station further includes an inlet counter configured for counting the number of irradiation targets entering or exiting the decay conduit through the decay conduit inlet. The inlet counter is located at the decay conduit inlet. The decay station further includes an outlet radiation detector configured for measuring the radiation emitted by an irradiation target located at the decay conduit outlet.
G21G 1/02 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
G21C 23/00 - Adaptations of reactors to facilitate experimentation or irradiation
16.
DEVICE FOR SUBJECTING PROBES TO IRRADIATION IN THE CORE OF A HEAVY WATER REACTOR, DIVERTER, INSTALLATION FOR PRODUCING ACTIVATED PROBES IN THE CORE OF A HEAVY WATER REACTOR AND HEAVY WATER REACTOR
A device (55) for subjecting probes to irradiation in the core of a heavy water nuclear reactor, comprising: - a plurality of probe receiving fingers (60), each probe receiving finger (60) defining a longitudinal axis (L), extending into the core of the nuclear reactor, and having a double walled structure; and - a pneumatic transport system (64). The device (55) further comprises a head (62), to which the probe receiving fingers (60) are attached, comprising a body (80) defining, for each of the probe receiving fingers (60), a gas conduit (113) for receiving a flow of pressurized gas from the pneumatic transport system (64), each gas conduit (113) having a first end (115) opening into an annular space (72) between an inner tube (68) and an outer tube (70) of the respective probe receiving finger (60) and a second end (117) connected to a gas supply port (119) for connection to a supply of pressurized gas, the gas conduits (113) of the different probe receiving fingers (60) being separated from each other fluidically.
G21C 23/00 - Adaptations of reactors to facilitate experimentation or irradiation
G21G 1/02 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
17.
DEVICE FOR SUBJECTING PROBES TO IRRADIATION IN THE CORE OF A HEAVY WATER REACTOR, DIVERTER, INSTALLATION FOR PRODUCING ACTIVATED PROBES IN THE CORE OF A HEAVY WATER REACTOR AND HEAVY WATER REACTOR
A device (55) for subjecting probes to irradiation in the core of a heavy water nuclear reactor, comprising: - a plurality of probe receiving fingers (60), each probe receiving finger (60) defining a longitudinal axis (L), extending into the core of the nuclear reactor, and having a double walled structure; and - a pneumatic transport system (64). The device (55) further comprises a head (62), to which the probe receiving fingers (60) are attached, comprising a body (80) defining, for each of the probe receiving fingers (60), a gas conduit (113) for receiving a flow of pressurized gas from the pneumatic transport system (64), each gas conduit (113) having a first end (115) opening into an annular space (72) between an inner tube (68) and an outer tube (70) of the respective probe receiving finger (60) and a second end (117) connected to a gas supply port (119) for connection to a supply of pressurized gas, the gas conduits (113) of the different probe receiving fingers (60) being separated from each other fluidically.
G21C 23/00 - Adaptations of reactors to facilitate experimentation or irradiation
G21G 1/02 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
18.
METHOD FOR AUTOMATICALLY MAPPING THE RADIATION IN A PORTION OF A BUILDING AND A ROBOT VEHICLE
The invention relates to a method for automatically mapping the radiation in a portion of a building (7) using a robot vehicle (1), the portion of the building comprising a plurality of building surfaces (9, 10), the method comprising: acquiring (1010) a 3D map (42) of a portion of a building (7), wherein the 3D map (42) comprises a plurality of segments (44), each representing a substantially flat building surface; wherein the method further comprises applying (1020) to each segment (44) a plurality sectors forming a grid of sectors (46), each sector (46) having a border (48); physically marking, by the robot vehicle (1), the border (48) of each sector (46) with paint on the corresponding building surface (9, 10); and for one or more sectors (46), scanning, by the robot vehicle (1), with a radiation sensor (28) each sector (46), to measure the radioactive radiation within that sector.
The invention relates to a method for automatically mapping the radiation in a portion of a building (7) using a robot vehicle (1), the portion of the building comprising a plurality of building surfaces (9, 10), the method comprising: acquiring (1010) a 3D map (42) of a portion of a building (7), wherein the 3D map (42) comprises a plurality of segments (44), each representing a substantially flat building surface; wherein the method further comprises applying (1020) to each segment (44) a plurality sectors forming a grid of sectors (46), each sector (46) having a border (48); physically marking, by the robot vehicle (1), the border (48) of each sector (46) with paint on the corresponding building surface (9, 10); and for one or more sectors (46), scanning, by the robot vehicle (1), with a radiation sensor (28) each sector (46), to measure the radioactive radiation within that sector.
A detection device (18) for detecting the position of a moving object comprises a base (20); an arm (22) that is mounted rotatable to the base (20), wherein the arm (22) is rotatable around a first rotational axis (26) and has a free end (28) for contact with the moving object; and a sensor (24) that is configured to detect rotation of the arm (22) relative to the base (20), wherein the sensor (24) has a first part and a second part, wherein the first part moves with the arm (22), and the second part is attached to the base (20). The first part is a first component of a magnet (40) switch (42) pair, wherein the switch is an electrical switch (42) that is configured to be actuated by the magnetic field of the magnet (40), and the second part is another component of the magnet (40) switch (42) pair.
H01H 21/28 - Operating parts, e.g. handle biased to return to original position upon removal of operating force adapted for actuation at a limit or other predetermined position in the path of a body, the relative movement of switch and body being primarily for a purpose other than the actuation of the switch, e.g. door switch, limit switch, floor-levelling switch of a lift
The invention relates to a ventilation and air-conditioning system (6) for a room comprising a cooling air supply system, a supply air duct system (14) and at least one enclosure (16) comprising an inlet (18), an outlet (20), and heat storage elements (30). The ventilation and air-conditioning system (6) is configured such that when the operation of the cooling air supply system fails, a natural convection airflow occurs through the enclosure (16) from the inlet (18) to the outlet (20), the natural convection airflow being cooled by transferring heat to the heat storage elements (30).The supply air duct system (14) is arranged above the inlet (18) at a distance (A) from the latter, a gap (38) being defined between the supply air duct system (14) and the inlet (18). The inlet (18) of the enclosure (16) is adapted to be in constant flow communication with the room (2) by air flowing from the room (2) through the gap (38) into the inlet (18) of the enclosure.
The invention relates to a ventilation and air-conditioning system (6) for a space, comprising a cooling-air feed system, a supply-air duct system (14), and at least one housing (16), which comprises: - an inlet (18), - an outlet (20), and - heat storage elements (30). The ventilation and air-conditioning system (6) is configured such that, if the operation of the cooling-air feed system drops out, a natural convection air flow through the housing (16) from the inlet (18) to the outlet (20) occurs, the natural convection air flow being cooled by heat transfer to the heat storage elements (30). The supply-air duct system (14) is disposed above the inlet (18) at a distance (A) therefrom, and a gap (38) is defined between the supply-air duct system (14) and the inlet (18). The inlet (18) of the housing (16) is suitable for being permanently fluidically connected to the space (2) by virtue of the fact that the air from the space (2) flows through the gap (38) into the inlet (18) of the housing.
A method is for controlling a nuclear power plant comprising a pressurized water nuclear reactor. The method includes determining that an obtained waiting period and/or a remaining waiting period is greater than a first predetermined time allowing raising of a Xenon concentration to maximal value. The method further includes, responsive to the determination, moving one or more control rods out of the reactor core for compensating the reactivity loss due to an increase of the Xenon concentration, and moving the one or more control rods into the reactor core to a control rod setpoint for the start of power ramp up before the end of the obtained waiting period and/or remaining waiting period.
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 3/326 - Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different compositionComprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
A method for providing a neutron radiation shield includes a step (a) of providing a wall having an opening; and a step (b) of at least partially filling a space in the opening with a neutron moderator. Step (b) includes blast-injecting plastic granules into the opening with a blower device to form the neutron moderator.
A method for optimizing an aviation radiation dose comprises a) gathering flight-relevant data including at least one flight schedule; b) gathering radiation data including at least a current radiation field assigned to the at least one flight schedule, historical radiation data assigned to the flight-relevant data and a radiation dose threshold; c) calculating an expected radiation dose based on the flight-relevant data and the radiation data; and d) modifying the flight-relevant data and repeating steps a) to c) at least once in order to obtain optimized flight-relevant data with regard to the expected radiation dose. With each iteration the flight-relevant data is modified.
The invention relates to a target transport system (1) for a radionuclide generation system, comprising: - a conduit (5) for transporting irradiation targets (7) through the radionuclide generation system; - a target drive system (9) configured to drive the irradiation targets (7) through said conduit (5); - a counting system (12) configured for counting the number of irradiation targets (7) passing though the conduit (5). The counting system (12) comprises at least two distance sensors (15), each configured for measuring a radial distance (d1, d2) between the distance sensor (15) and the irradiation target (7), and arranged at a same axial position along the conduit (5) and regularly spaced along the circumference of the conduit (5) with a constant angular spacing.
G21G 1/02 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
G21F 7/06 - Structural combination with remotely-controlled apparatus, e.g. with manipulators
G21K 5/08 - Holders for targets or for objects to be irradiated
27.
TARGET TRANSPORT SYSTEM FOR A RADIONUCLIDE GENERATION SYSTEM
122) between the distance sensor (15) and the irradiation target (7), and arranged at a same axial position along the conduit (5) and regularly spaced along the circumference of the conduit (5) with a constant angular spacing.
G21G 1/02 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
G21F 7/06 - Structural combination with remotely-controlled apparatus, e.g. with manipulators
G21K 5/08 - Holders for targets or for objects to be irradiated
28.
HYDROGENATION SYSTEM FOR PRESSURIZED WATER REACTOR AND ACCORDING METHOD
A pressurized water reactor includes a primary reactor coolant circuit flown through by a primary reactor coolant during operation, and a chemical and volume control system for the primary reactor coolant. The chemical and volume control system includes, along the direction of flow of the primary reactor coolant, a letdown line, a high-pressure charging pump with a given discharge pressure, and a charging line leading to the primary reactor coolant circuit. The chemical and volume control system further includes a hydrogenation system with a hydrogen supply and a hydrogen feeding line. In order to achieve efficient and fast hydrogen injection into the primary reactor coolant, a high-pressure feeding pump is arranged in the feeding line to provide a gas pressure higher than the discharge pressure of the charging pump. The feeding line discharges into the charging line.
G21C 17/028 - Devices or arrangements for monitoring coolant or moderator for monitoring gaseous coolants
G21C 17/032 - Reactor-coolant flow measuring or monitoring
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
A method of governing a pressurized water nuclear reactor can simultaneously consider and balance a large number of control goals. The method includes iteratively considering a large number of randomly varied possible trajectories (Ta) of actuating variables for controlling reactor core reactivity for a future time interval. Each trajectory (Ta) of actuating variables is assigned a figure of merit (Σ) on the basis of a Value Table which contains weighting or penalty values for a number of events or adverse reactor core states which are characterized by preset conditions or values of the actuating variables, the process variables and/or variables derived from them. The trajectory (Ta) of actuating variables is chosen such that the figure of merit (Σ) has a local extremum, and corresponding actuators are moved accordingly.
A nuclear power plant includes a nuclear reactor and a reactor coolant circuit containing a reactor coolant. The nuclear power plant further includes a degasification system (2) for the reactor coolant. The degasification system (2) is an ultrasonic degasification system comprising a sonotrode cluster (11) with at least one sonotrode (10) arranged in a line of the reactor coolant circuit or in a line which is fluidically connected to the reactor coolant circuit.
G21C 19/307 - Arrangements for introducing fluent material into the reactor coreArrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products specially adapted for liquids
A control rod position indication system is for a nuclear reactor with a reactor core and at least one control rod which is movable along a linear path of movement for controlling reactivity of the core. The system includes a permanent magnet mounted on the control rod or a corresponding drive rod, and a number of reed switches arranged around the path of movement in order to be switched by a magnetic field generated by the permanent magnet when passing by. The permanent magnet has a north-south axis whose orientation is constant during movement, and the respective reed switch has a number of reed contacts which are aligned along a longitudinal axis. The longitudinal axis of at least one reed switch is inclined relative to the north-south axis of the permanent magnet, and the angle of inclination has an absolute value within a range from 15 to 65 degrees.
G21C 17/12 - Sensitive element forming part of control element
G01D 5/251 - Selecting one or more conductors or channels from a plurality of conductors or channels, e.g. by closing contacts one conductor or channel
G21C 17/10 - Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
32.
System for sterilizing sterilization units and method for operating such a system
A system for sterilizing sterilization units by radiation exposure comprises a conveyance system for transporting sterilization units through a sterilizing environment along a conveying path. The conveyance system comprises at least one lifting beam conveyor with at least one stationary supporting beam and at least one movable lifting beam, which is movable with respect to the at least one stationary supporting beam in a longitudinal and a vertical direction. The at least one stationary supporting beam has a central region between two fixed bearings, which is supported via at least one tensile-loaded tensile element, which is fastened to the central region and to at least one vertical strut, which is arranged in the region of at least one of the fixed bearings, in such a manner that the tensile element extends in a direction diagonal to the longitudinal and the vertical direction.
B65G 25/02 - Conveyors comprising a cyclically-moving, e.g. reciprocating, carrier or impeller which is disengaged from the load during the return part of its movement the carrier or impeller having different forward and return paths of movement, e.g. walking-beam conveyors
The present application relates to a recirculation method for the continuous mineralization of an organic acid in an aqueous solution used for the stripping of radionuclides from an ion exchanger, by means of an electrolyzer comprising a boron-doped diamond electrode, the apparatus for conducting said method and the method for regenerating an ion exchanger containing immobilized radionuclides involving said recirculation method.
C02F 1/469 - Treatment of water, waste water, or sewage by electrochemical methods by electrochemical separation, e.g. by electro-osmosis, electrodialysis, electrophoresis
34.
MINERALIZATION OF ORGANIC COMPOUNDS WITH BORON-DOPED-DIAMOND ELECTRODE DURING RADIONUCLIDES STRIPPING PROCESS
The present application relates to a recirculation method for the continuous mineralization of an organic acid in an aqueous solution used for the stripping of radionuclides from an ion exchanger, by means of an electrolyzer comprising a boron-doped diamond electrode, the apparatus for conducting said method and the method for regenerating an ion exchanger containing immobilized radionuclides involving said recirculation method.
C02F 1/20 - Treatment of water, waste water, or sewage by degassing, i.e. liberation of dissolved gases
C02F 1/42 - Treatment of water, waste water, or sewage by ion-exchange
C02F 1/44 - Treatment of water, waste water, or sewage by dialysis, osmosis or reverse osmosis
C02F 1/461 - Treatment of water, waste water, or sewage by electrochemical methods by electrolysis
C02F 1/467 - Treatment of water, waste water, or sewage by electrochemical methods by electrolysis by electrochemical disinfection
C02F 1/469 - Treatment of water, waste water, or sewage by electrochemical methods by electrochemical separation, e.g. by electro-osmosis, electrodialysis, electrophoresis
G21F 9/12 - Processing by absorptionProcessing by adsorptionProcessing by ion-exchange
35.
DEVICE FOR USE IN A FUEL ASSEMBLY OF NUCLEAR POWER PLANT, METHOD FOR MANUFACTURING A DEVICE AND METHOD FOR ACTIVATING A MATERIAL IN A NUCLEAR POWER PLANT
The present invention relates to device (20) for use in a fuel assembly (1) of a nuclear power plant, the device comprises at least one rod (30), each rod comprises a plurality of containers (32, 32b, 32c) having a space being filled with material to be activated, characterized in that the device further comprises a flow restrictor (24, 26) for a fuel assembly (1) of a nuclear power plant comprising a plurality of fingers (28) adapted to extend respectively into a control rod guide tube (9) of the fuel assembly (1) when the flow restrictor is inserted into the fuel assembly (1), wherein the at least one rod (30) is connected to a finger of the flow restrictor, wherein the containers (32) are arranged subsequently in a direction of the longitudinal axis of the respective rod (30).
A nuclear power plant comprises a system for degasification (1) of a gaseous liquid (2), the system (1) comprising: - a separation vessel (4) having at least one outer wall (6) delimiting an inner volume (8) and configured for separating gas (18) from the gaseous liquid (2), - at least one inlet (10) adapted to introduce the gaseous liquid (2) into the inner volume (8), - at least one gas suction line (20) attached to the separation vessel (4) and being adapted to discharge the separated gas (18) from the inner volume (8), and - at least one outlet (12) adapted to discharge a degassed liquid (14) from the inner volume (8), - a sonotrode cluster (16) configured to expose the gaseous liquid (2) to ultrasonic waves.
G21C 19/307 - Arrangements for introducing fluent material into the reactor coreArrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products specially adapted for liquids
For stabilizing a pipe connection, in which a first pipe (10) is inserted into a second pipe (12) that has an insertion funnel (20), a stabilizer element (22) has a clamping ring (24) with several tensioners (48) distributed over its circumference, which in the final assembly position engage in an intermediate space between the first pipe (10) and the insertion funnel (20), and tense the first pipe (10) and the second pipe (12) against each other. The clamping ring (24) is composed of several mutually connectable ring segments, in particular of two half shells (34).
F16L 37/133 - Couplings of the quick-acting type in which the connection between abutting or axially-overlapping ends is maintained by locking members using hooks, pawls, or other movable or insertable locking members using flexible hooks
F16L 37/12 - Couplings of the quick-acting type in which the connection between abutting or axially-overlapping ends is maintained by locking members using hooks, pawls, or other movable or insertable locking members
F16L 57/06 - Protection of pipes or objects of similar shape against external or internal damage or wear against wear
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
G21C 17/10 - Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
38.
Method for conditioning ion exchange resins and apparatus for carrying out the method
A method for conditioning of spent ion exchange resins from nuclear facilities comprises the steps of: mixing the spent ion exchange resins with water to form a reaction mixture; setting and controlling the pH of the reaction mixture in a range from 1.0 to 3.5, preferably in a range from 2.0 to 3.0; adding an oxidant to the reaction mixture, with the temperature of the reaction mixture maintained at 90°° C. or less so that the spent ion exchange resin and the oxidant react with each other to form an aqueous reaction solution comprising the organic reaction products of the spent ion exchange resin; and electrochemically oxidizing the organic reaction products, wherein carbon dioxide is produced and a carbon-depleted aqueous reaction solution having a TOC (total organic carbon) value of less than 50 ppm is obtained. Furthermore, an apparatus for the conditioning of spent ion exchange resins from nuclear facilities is described.
G21F 9/12 - Processing by absorptionProcessing by adsorptionProcessing by ion-exchange
B01J 45/00 - Ion-exchange in which a complex or a chelate is formedUse of material as complex or chelate forming ion-exchangersTreatment of material for improving the complex or chelate forming ion-exchange properties
09 - Scientific and electric apparatus and instruments
40 - Treatment of materials; recycling, air and water treatment,
Goods & Services
Waste sorting machines, remotely controlled lifting
machines, machine tools for removing waste material, waste
and trash conveying machines, waste and trash separator
machines, waste compacting machines; robotic apparatus and
machines for separating and sorting waste; control
mechanisms for robotic apparatus and machines for separating
and sorting waste; industrial robots for use in connection
with apparatus and machines for separating and sorting
waste; robot mechanisms for conveying waste. Electrical installations for the remote control of
industrial operations in waste conditioning machines; remote
control apparatus for the control of waste conditioning
machines; robotic electrical control apparatus for use in
connection with apparatus and machines for separating and
sorting waste; computer software for the remote control of
waste conditioning machines; virtual reality hardware and
virtual reality software for controlling waste conditioning
machines; detectors, sensors, and monitoring instruments and
apparatus for use with waste conditioning machines;
radiation detectors; measuring instruments and apparatus,
control instruments and apparatus, radiation measuring
instruments, digital cameras for industrial purposes and
video cameras, each as components of waste conditioning
machines. Recycling of waste and trash; treatment of waste; processing
of waste; treatment [reclamation] of material from waste;
destruction of trash; sorting of waste and recyclable
material; recycling and waste processing in connection with
metal-containing wastes; recycling of metals; metalworking;
treatment (reclamation) of materials from radioactive waste,
and treatment of radioactive waste; decontamination of
nuclear waste; treatment of hazardous waste; recycling and
waste processing in connection with nuclear waste; waste
treatment by means of radiological characterization.
According to the invention a nuclear power plant is provided comprising a containment (3) defining a hermitical zone, a reactor pressure vessel (5) being arranged in a first portion (6) of the containment (3), a first condenser (7) arranged in a second portion (8) of the containment, the first condenser being a wet condenser and in fluid communication with the first portion (6) of the containment via a corridor (10), one or more air traps (30) collecting non-condensable gases from the wet condenser (7), an external pool (40, 42) provided outside the containment (3), wherein the external pool (40, 42) is arranged above the containment (3) and is adapted to contain a cooling fluid, wherein the nuclear power plant further comprises: a second condenser (50) forming a heat exchanger and being arranged in the corridor (10), the second condenser (50) having an feed pipe (60) for providing a cooling fluid to the second condenser (50) and a return pipe (62) for providing a cooling fluid from the second condenser (50), the feed pipe (60) and the return pipe (62) being respectively in fluid communication with the external pool (40, 42), wherein an opening (67) of the feed pipe (60) and an at least one opening (66) of the return pipe (62) are provided within the external pool (40, 42) and are arranged above the second condenser (50), wherein the opening (67) of the feed pipe (60) is arranged below the opening (66) of the return tube (62).
Decay station (30) comprising a housing (50) comprising a radiation shielding (54), the housing (50) delimiting a decay conduit (52) intended for containing the irradiation targets (16) in the predetermined linear order, the decay conduit (52) comprising: - a decay conduit inlet (56), intended to be connected to the structure (12) of the core (10) of the nuclear reactor for receiving the irradiation targets (16) therefrom; - a decay conduit outlet (58), intended to be connected to an irradiation target discharge system (27) for discharging the irradiation targets (16) from the decay station (30), the decay station (30) further comprising: - an inlet distributor (68), located at the decay conduit inlet (56), and configured for releasing only a predetermined amount of irradiation targets (16) at a time from the decay station (30) towards the structure (12) of the core (10) of the nuclear reactor, the inlet distributor (68) being configured for releasing the irradiation targets (16) closest to the decay conduit inlet (56), while retaining the remaining irradiation targets (16) in the decay conduit (52); - an inlet counter (96), configured for counting the number of irradiation targets (16) entering or exiting the decay conduit (52) through the decay conduit inlet (56), the inlet counter (96) being located at the decay conduit inlet (56), and - an outlet radiation detector (102), configured for measuring the radiation emitted by an irradiation target (16) located at the decay conduit outlet (58).
G21G 1/02 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
42.
INSTALLATION AND METHOD FOR PRODUCING ACTIVATED IRRADIATION TARGETS IN AN INSTRUMENTATION TUBE SYSTEM OF A NUCLEAR REACTOR
Decay station (30) comprising a housing (50) comprising a radiation shielding (54), the housing (50) delimiting a decay conduit (52) intended for containing the irradiation targets (16) in the predetermined linear order, the decay conduit (52) comprising: - a decay conduit inlet (56), intended to be connected to the structure (12) of the core (10) of the nuclear reactor for receiving the irradiation targets (16) therefrom; - a decay conduit outlet (58), intended to be connected to an irradiation target discharge system (27) for discharging the irradiation targets (16) from the decay station (30), the decay station (30) further comprising: - an inlet distributor (68), located at the decay conduit inlet (56), and configured for releasing only a predetermined amount of irradiation targets (16) at a time from the decay station (30) towards the structure (12) of the core (10) of the nuclear reactor, the inlet distributor (68) being configured for releasing the irradiation targets (16) closest to the decay conduit inlet (56), while retaining the remaining irradiation targets (16) in the decay conduit (52); - an inlet counter (96), configured for counting the number of irradiation targets (16) entering or exiting the decay conduit (52) through the decay conduit inlet (56), the inlet counter (96) being located at the decay conduit inlet (56), and - an outlet radiation detector (102), configured for measuring the radiation emitted by an irradiation target (16) located at the decay conduit outlet (58).
43.
INSTALLATION AND METHOD FOR PRODUCING ACTIVATED IRRADIATION TARGETS IN AN INSTRUMENTATION TUBE SYSTEM OF A NUCLEAR REACTOR
Decay station (30) comprising a housing (50) comprising a radiation shielding (54), the housing (50) delimiting a decay conduit (52) intended for containing the irradiation targets (16) in the predetermined linear order, the decay conduit (52) comprising: - a decay conduit inlet (56), intended to be connected to the structure (12) of the core (10) of the nuclear reactor for receiving the irradiation targets (16) therefrom; - a decay conduit outlet (58), intended to be connected to an irradiation target discharge system (27) for discharging the irradiation targets (16) from the decay station (30), the decay station (30) further comprising: - an inlet distributor (68), located at the decay conduit inlet (56), and configured for releasing only a predetermined amount of irradiation targets (16) at a time from the decay station (30) towards the structure (12) of the core (10) of the nuclear reactor, the inlet distributor (68) being configured for releasing the irradiation targets (16) closest to the decay conduit inlet (56), while retaining the remaining irradiation targets (16) in the decay conduit (52); - an inlet counter (96), configured for counting the number of irradiation targets (16) entering or exiting the decay conduit (52) through the decay conduit inlet (56), the inlet counter (96) being located at the decay conduit inlet (56), and - an outlet radiation detector (102), configured for measuring the radiation emitted by an irradiation target (16) located at the decay conduit outlet (58).
G21G 1/02 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
09 - Scientific and electric apparatus and instruments
40 - Treatment of materials; recycling, air and water treatment,
Goods & Services
(1) Waste sorting machines, remotely controlled lifting machines for lifting and removing radioactive waste material, machine tools for removing waste material, waste and trash conveying machines, waste and trash separator machines, waste compacting machines; robotic apparatus and machines for separating and sorting waste; control mechanisms for robotic apparatus and machines for separating and sorting waste; industrial robots for use in connection with apparatus and machines for separating and sorting waste; robot mechanisms for conveying waste
(2) Electrical industrial controls for the remote control of nuclear waste treatment machines; radio remote controls for nuclear waste treatment machines; robotic arms for removing nuclear waste contaminated materials for use in separating and sorting nuclear waste; computer software for the remote control of nuclear waste treatment machines for use in decommissioning of nuclear facilities; virtual reality hardware and virtual reality software for controlling waste conditioning machines; radioactivity detectors, radioactivity sensors and radioactivity monitoring instruments and apparatus for use with nuclear waste treatment machines; radiation detectors; radioactivity measuring instruments and apparatus, radiation measuring instruments, digital cameras for industrial purposes and video cameras, each as components of waste conditioning machines (1) Recycling of waste and trash; nuclear waste treatment; decontamination of nuclear waste; recycling and reclamation of usable materials from residue of waste produced in industry for others; destruction of trash; sorting of waste and recyclable material; recycling of metals; metalworking; treatment (reclamation) of materials from radioactive waste, and treatment of radioactive waste; decontamination of nuclear waste; waste treatment by means of radiological characterization namely determining the nature, location and concentration of radionuclides at a nuclear installation in the decommissioning of nuclear facilities
09 - Scientific and electric apparatus and instruments
Goods & Services
Scientific, surveying, measuring, signalling, checking (supervision) apparatus and instruments; Electrotechnical and electronic apparatus being installations for the detection and location of leaks in containers holding solid, liquid and gaseous media; Electrotechnical and electronic apparatus being installations for the detection and location of leaks in containers and pipelines holding solid, liquid and gaseous media, consisting of sensors, detectors, electric transmission apparatus and data processing programs relating thereto (included in class 9), alarm equipment and an information memory.
40 - Treatment of materials; recycling, air and water treatment,
07 - Machines and machine tools
09 - Scientific and electric apparatus and instruments
Goods & Services
Recycling of waste and trash; treatment of waste; processing of waste; treatment and reclamation of material from waste, namely, upcycling in the nature of waste recycling; destruction of trash; sorting of waste and recyclable material; recycling and waste processing in connection with metal-containing wastes; recycling of metals; metalworking; treatment and reclamation of materials from radioactive waste, namely, sorting of waste and recyclable material, processing of radioactive waste, and treatment of radioactive waste; decontamination of nuclear waste; treatment of hazardous waste; recycling and waste processing in connection with nuclear waste; waste treatment by means of radiological characterization Waste sorting machines, remotely controlled lifting machines for containers and barrels containing waste, machine tools for removing waste material, waste and trash conveying machines, waste and trash separator machines, waste compacting machines; robotic apparatus and machines for separating and sorting waste; industrial robots for use in connection with apparatus and machines for separating and sorting waste; robotic mechanisms for conveying waste Electrical installations for the remote control of industrial operations in waste conditioning machines; remote control apparatus for the control of waste conditioning machines; robotic electrical control apparatus for use in connection with apparatus and machines for separating and sorting waste; control mechanisms being electronic motor controllers for robotic apparatus and machines for separating and sorting waste; downloadable computer software for the remote control of waste conditioning machines; recorded computer software for the remote control of waste conditioning machines; virtual reality hardware in the nature of virtual reality headsets, virtual reality glasses, virtual reality controllers being video graphics controller; downloadable virtual reality software for controlling waste conditioning machines; recorded virtual reality software for controlling waste conditioning machines; gamma radiation detectors; weight, pressure and temperature sensors; monitoring instruments and apparatus in the nature of hot spot identification and localization monitoring systems for use with waste conditioning machines; radiation detectors; pressure, temperature and radiation measuring instruments and apparatus, control instruments and apparatus in the nature of remote controls and electronic controllers for monitoring and controlling industrial processes; radiation measuring instruments, digital cameras for industrial purposes and video cameras, each sold as components of waste conditioning machines
47.
Lance unit, nuclide activation and nuclear monitoring system as well as method of producing radionuclides
A lance unit (32) for usage in a nuclear reactor core (15) includes a nuclide activation system (22), a nuclear monitoring system (14), a tube system (28) and a yoke (34) holding the tube system (28). The nuclear monitoring system (14) has at least one nuclear monitoring tube (16) for accommodating monitoring members (18) that monitor the nuclear reactor core (15). The nuclide activation system (22) has a nuclide activation tube (24) for accommodating at least one irradiation target (26) to be exposed to neutron flux in the nuclear reactor (12) to form a radionuclide. The at least one nuclear monitoring tube (16) and the nuclide activation tube (24) are part of the tube system (28). The nuclide activation tube (24) has an internal stop (40) configured to stop the at least one irradiation target (26). The internal stop (40) of the nuclide activation tube (24) is located at a different height with regard to the lower end of the nuclear monitoring tube (16).
G21G 1/02 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
48.
SENSING DEVICE FOR SENSING THE POSITION OF A MOVABLE OBJECT
A detection device for detecting the position of a moving object comprises: - a base; - an arm that is mounted rotatable to the base, wherein the arm is rotatable around a first rotational axis and has a free end for contact with the moving object; and - a sensor that is configured to detect rotation of the arm relative to the base, wherein the sensor has a first part and a second part, wherein the first part moves with the arm, and the second part is attached to the base. The first part is a first component of a magnet switch pair, wherein the switch is an electrical switch that is configured to be actuated by the magnetic field of the magnet, and the second part is another component of the magnet switch pair.
H01H 21/28 - Operating parts, e.g. handle biased to return to original position upon removal of operating force adapted for actuation at a limit or other predetermined position in the path of a body, the relative movement of switch and body being primarily for a purpose other than the actuation of the switch, e.g. door switch, limit switch, floor-levelling switch of a lift
B25J 9/10 - Programme-controlled manipulators characterised by positioning means for manipulator elements
H01H 36/00 - Switches actuated by change of magnetic field or of electric field, e.g. by change of relative position of magnet and switch, by shielding
H01H 21/08 - Dustproof, splashproof, drip-proof, waterproof, or flameproof casings
49.
SENSING DEVICE FOR SENSING THE POSITION OF A MOVABLE OBJECT
The invention relates to a sensing device (18) for sensing the position of a movable object comprising: a base (20); an arm (22), which is mounted for rotation relative to the base (20), the arm (22) being rotatable about a first axis of rotation (26) and having a free end (28) for contacting the movable object; and a sensor (24), which is designed to sense rotation of the arm (22) relative to the base (20), the sensor (24) having a first part and a second part. The first part rotates with the arm (22), and the second part is fastened to the base (20). The first part is a first element of a magnet(40)-switch(42) pair, the switch being an electrical switch (42) designed to be actuated by means of the magnetic field of the magnet (40), and the second part is the other element of the magnet(40)-switch(42) pair.
H01H 21/28 - Operating parts, e.g. handle biased to return to original position upon removal of operating force adapted for actuation at a limit or other predetermined position in the path of a body, the relative movement of switch and body being primarily for a purpose other than the actuation of the switch, e.g. door switch, limit switch, floor-levelling switch of a lift
B25J 9/10 - Programme-controlled manipulators characterised by positioning means for manipulator elements
H01H 21/08 - Dustproof, splashproof, drip-proof, waterproof, or flameproof casings
H01H 36/00 - Switches actuated by change of magnetic field or of electric field, e.g. by change of relative position of magnet and switch, by shielding
50.
Welding torch, welding system, method of producing a welding torch as well as computer- readable medium
A welding torch (18) for a welding system (10) includes a substantially spherical main body (20) that has an integrated coolant chamber (60) which is in fluid communication with at least one coolant port (62). The substantially spherical main body (20) is a joint head (22) of a ball joint (24) of the welding system (10). A welding system (10) includes a torch bracket (16) and the welding torch (18). The torch bracket (16) has a socket (26, 28) of a ball joint (24), and the socket (26, 28) receives the substantially spherical main body (20) of the welding torch (18) in a spherically orientable manner thereby forming the ball joint (24).
B23K 9/29 - Supporting devices adapted for making use of shielding means
B33Y 80/00 - Products made by additive manufacturing
51.
FIXING DEVICE FOR FIXING AT LEAST ONE SUPPLY COMPONENT TO A CONCRETE MEMBER OF A NUCLEAR POWER PLANT, RELATED METHOD AND SET FORMING SUCH FIXING DEVICE
A fixing device (4) for fixing at least one supply component to a concrete member (2) of a nuclear power plant, the fixing device (4) comprising a metal plate (10) adapted to extend in parallel to the concrete member (2), the metal plate (10) being configured to be fixed to the supply component and having a rear side (14) adapted to face the concrete member (2), and a square section profile (12) having a rectangular hollow cross section. The square section profile (12) is welded on a rear side (14) of the metal plate (10) and to be embedded in the concrete member (2), such that the square section profile (12) is filled with concrete and/or mortar, the square section profile (12) being configured for transmitting at least one torsional moment applied on the metal plate (10) and forces applied on the metal plate (10).
A method for decontaminating a metal surface exposed to radioactive liquid or gas during operation of a nuclear facility comprises an oxidation step wherein a metal oxide layer on the metal surface is contacted with an aqueous oxidation solution comprising a permanganate oxidant for converting chromium into a Cr(VI) compound and dissolving the Cr(VI) compound in the oxidation solution; and a first cleaning step wherein the oxidation solution containing the Cr(VI) compound is directly passed over an anion exchange material and the Cr(VI) compound is immobilized on the anion exchange material. The method provides for substantial savings of radioactive waste and produces chelate-free waste.
A method of decontaminating a metal surface located on a component within a nuclear plant, in particular within the cooling system of a nuclear power plant, which is covered with a metal oxide layer containing radioactive substances, the method including a decontamination step in which a metal oxide layer pretreated in an oxidation step is contacted with an aqueous solution of an organic acid to dissolve the metal oxide layer, forming a decontamination solution containing the organic acid, metal ions and the radioactive substances, and passing the decontamination solution over an ion exchanger to immobilize metal ions and radioactive substances. An oxidant selected from oxygen, air, hydrogen peroxide and ozone is dosed into the decontamination solution to control the dissolution rate of the metal oxide layer. The method is particularly suitable for large-scale system decontamination and ensures high process stability.
A repairing system (2) is used for applying an adhesive to a location to be repaired underwater in a container. The repairing system (2) comprises a movable and remotely controlled repairing robot (10) that is configured to be driven underwater. The repairing robot (10) comprises a repairing module (12) that is configured to be coupled with an adhesive applying module (34). The adhesive applying module (34) is configured to dispense an adhesive on the location to be repaired. Further, a repairing method is described.
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
B29C 65/48 - Joining of preformed partsApparatus therefor using adhesives
55.
METHOD FOR CONTROLLING A NUCLEAR POWER PLANT AND CONTROLLER
The present invention relates to a method for controlling a nuclear power plant comprising pressurized water nuclear reactor (3) having a reactor core producing power, a primary circuit (5) connecting the reactor core to a steam generator (9), one or more of control rods (16), which can be moved into the reactor core for controlling the power of the reactor core, an injecting device (22, 23, 24, 26, 28, 30) for injecting boric acid and/or deionized water into the primary circuit (5) for controlling the reactivity of the reactor core.
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
G21C 7/04 - Control of nuclear reaction by using self-regulating properties of reactor materials of burnable poisons
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
The invention relates to a method for providing a neutron radiation shield, the method comprising: (a) providing a wall (2) having an opening (6); and (b) at least partially filling a space in the opening (6) with a neutron moderator (10). The according neutron radiation shield shall be easy to establish in little time and the method shall be flexible to adapt to various installation locations. To this end, according to the invention, step (b) comprises: blast-injecting plastic granules (36) into the opening (6) with a blower device (46) to form the neutron moderator (10).
An analysis device for detecting fission products by measurement of a radioactivity includes a first line for carrying a liquid sample, a first detector connected to the first line and designed for measuring the radioactivity of fission products contained in the liquid sample, a second line for carrying a gas sample and a second detector connected to the second line and designed for measuring the radioactivity of fission products contained in the gas sample. The analysis device includes a separation device for separating gas from the first line carrying the liquid sample, which line has an outlet opening into the second line for gas separated from the liquid sample. The outlet opening fluidly connected to the second lines in such a manner that the gas separated from the liquid sample is suppliable as a gas sample to the second detector for measuring the radioactivity of fission products contained therein.
G01M 3/22 - Investigating fluid tightness of structures by using fluid or vacuum by detecting the presence of fluid at the leakage point using special tracer materials, e.g. dye, fluorescent material, radioactive material for pipes, cables, or tubesInvestigating fluid tightness of structures by using fluid or vacuum by detecting the presence of fluid at the leakage point using special tracer materials, e.g. dye, fluorescent material, radioactive material for pipe joints or sealsInvestigating fluid tightness of structures by using fluid or vacuum by detecting the presence of fluid at the leakage point using special tracer materials, e.g. dye, fluorescent material, radioactive material for valves
The invention relates to a system (2) for stabilizing a meltdown in a nuclear power plant (1), comprising: - a reactor pressure vessel (4), which contains a reactor core (12), - a safety vessel (6), which defines a chamber (16) arranged underneath the reactor pressure vessel (4), - a coolant supply device (8), which is designed to introduce a coolant into the chamber (16) in the event that a meltdown is detected, - an absorbent material (10), which is suitable for absorbing the coolant introduced into the chamber (16), characterized in that the absorbing material (10) is suitable for expanding when absorbing the coolant.
09 - Scientific and electric apparatus and instruments
42 - Scientific, technological and industrial services, research and design
Goods & Services
Apparatus, instruments and devices for monitoring and
surveillance of industrial installations in the fields of
power generation; alarms for monitoring and surveillance of
industrial installations; computer programs, software and
software packages, recorded or downloadable, for monitoring
and surveillance of constructions and industrial
installations, including material aging and plant life
monitoring; modular computer software platforms, recorded or
downloadable, for monitoring and surveillance of
constructions and industrial installations, including
material aging and plant life monitoring; modular computer
software platforms, recorded or downloadable, for monitoring
and surveillance of constructions and industrial
installations, including material aging and plant life
monitoring, featuring functions for plant modeling and
parameter management, engineering tools and input data
validation, material library data and standard management,
commodity grouping, management of plant program activities,
validation of inspection and maintenance activities and
intervals, technical documentation management, operational
experience feedback management, and aging management review
reporting; modular computer software platforms, recorded or
downloadable, for monitoring and surveillance of mechanical
components, featuring functions for material aging and
degradation prediction, material degradation sensitivity
assessment, prioritization of inspection and maintenance
activities, examination data management, material data
management, and active components reliability assessment, in
particular for use in constructions and industrial
installations; modular computer software platforms, recorded
or downloadable, for monitoring and surveillance of
electrical and i&c components, featuring functions for life
time analysis and qualification, function chains modeling,
managing and evaluation, management of cable materials and
environmental conditions history, management and trending of
inspections on components, cables or function chains to
calibrate and validate prediction results, prioritization of
inspection activities, and examination data management, in
particular for use in constructions and industrial
installations; modular computer software platforms, recorded
or downloadable, for monitoring and surveillance of civil
structures, featuring functions for degradation assessment
of civil structures considering material, design, and
history of environmental conditions, lifetime assessment,
inspection management and inspection feedback evaluation,
defect trend analysis and remaining life analysis, integrity
assessment and reporting; prioritization of inspection and
maintenance activities, and examination data management;
modular computer software platforms, recorded or
downloadable, for monitoring and surveillance of
constructions and industrial installations, featuring data
import from connected systems, plant structure mapping,
trend analysis, data analysis according to equipment
operating condition, automatic diagnosis and prognosis
proposal with indication of event severity, and event
standard reports. Research and development services in the field of
engineering; services of engineers, namely, simulation and
monitoring services in the fields of energy and power
generation; services of engineers, namely, monitoring of
nuclear materials, and monitoring of nuclear and non-nuclear
installations and equipment; design, programming, updating,
maintenance and rental of software used for monitoring and
surveillance of constructions and industrial installations,
including material aging and plant life monitoring, in
particular for use in the field of energy and power
generation; software development and implementation services
for software used for monitoring and surveillance of
installations, including material aging and plant life
monitoring, in particular for use in the field of energy and
power generation; hosting services; software as a service in
relation to software used for monitoring and surveillance of
constructions and industrial installations, including
material aging and plant life monitoring, in particular for
use in the field of energy and power generation.
60.
METHOD FOR OPTIMIZING AVIATION RADIATION AND DOSE MONITORING SYSTEM
A method for optimizing an aviation radiation dose comprises the following steps: a) Gathering flight-relevant data including at least one flight schedule; b) Gathering radiation data including at least a current radiation field assigned to the at least one flight schedule, historical radiation data assigned to the flight-relevant data and a radiation dose threshold; c) Calculating an expected radiation dose based on the flight-relevant data and the radiation data; and d) Modifying the flight-relevant data and repeating steps a) to c) at least once in order to obtain optimized flight-relevant data with regard to the expected radiation dose, wherein with each iteration the flight-relevant data is modified. Further, a dose monitoring system is shown.
A method for optimizing an aviation radiation dose comprises the following steps: a) Gathering flight-relevant data including at least one flight schedule; b) Gathering radiation data including at least a current radiation field assigned to the at least one flight schedule, historical radiation data assigned to the flight-relevant data and a radiation dose threshold; c) Calculating an expected radiation dose based on the flight-relevant data and the radiation data; and d) Modifying the flight-relevant data and repeating steps a) to c) at least once in order to obtain optimized flight-relevant data with regard to the expected radiation dose, wherein with each iteration the flight-relevant data is modified. Further, a dose monitoring system is shown.
G06Q 10/04 - Forecasting or optimisation specially adapted for administrative or management purposes, e.g. linear programming or "cutting stock problem"
G01C 21/20 - Instruments for performing navigational calculations
62.
LUBRICATING DEVICE, INSTRUMENTATION TUBE SYSTEM OF A NUCLEAR POWER REACTOR AND METHOD FOR LUBRICATING THE INSTRUMENTATION TUBE SYSTEM
A lubricating device (28) for introducing a lubricant into a pipeline (20) by means of a gaseous transport medium comprises a feed pipe (30), which can be connected to the pipeline (20) and on which a pressure can be applied by means of the gaseous transport medium. The lubricating device (28) further comprises a check valve (38), arranged in the feed pipe (30), and a filling device (36) for the lubricant, which is in fluid connection with the feed pipe (30). The check valve (38) is mounted downstream of the filling device (36) towards the pipeline (20), and the filling device (36) is set up to introduce a predetermined amount of lubricant into the feed pipe (30), which can be introduced from the feed pipe (30) through the check valve (38) into the pipeline (20) by means of said gaseous transport medium. Further, an instrumentation tube system (14) comprising said lubricating device (28) and a method for lubricating at least one pipeline (20) of an instrumentation tube system (14) is shown.
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
G21G 1/02 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
B05B 13/06 - Machines or plants for applying liquids or other fluent materials to surfaces of objects or other work by spraying, not covered by groups specially designed for treating the inside of hollow bodies
63.
Method and device for the determination of film forming amines in a liquid
A photometric method for determination of a concentration of a film forming amine in a liquid, including providing a buffer solution of a weak acid having a pKa≥4.5 and a strong acid having a pKa≤1; diluting an aliquot of the buffer solution with water, and determining the pH of the diluted buffer solution; adding reagent to the diluted buffer solution and measuring an initial absorbance of the diluted buffer/reagent solution; preparing a sample solution by adding liquid containing the film forming amine to an aliquot of the buffer solution and measuring the pH of the sample solution; adjusting the pH of the sample solution to match the pH of the diluted buffer solution by adding strong acid; and adding the reagent to the pH adjusted sample solution to form a colored complex, and measuring the absorbance of the resulting solution in a photometer.
G01N 31/22 - Investigating or analysing non-biological materials by the use of the chemical methods specified in the subgroupsApparatus specially adapted for such methods using chemical indicators
G01N 21/78 - Systems in which material is subjected to a chemical reaction, the progress or the result of the reaction being investigated by observing the effect on a chemical indicator producing a change of colour
The invention relates to a pressurized water reactor (2), comprising a primary reactor coolant circuit (4) flown through by a primary reactor coolant during operation, and comprising a chemical and volume control system (14) for the primary reactor coolant, the chemical and volume control system (14) comprising, along the direction of flow of the primary reactor coolant, a letdown line (18), a high-pressure charging pump (32) with a given discharge pressure, and a charging line (34) leading to the primary reactor coolant circuit (4), the chemical and volume control system (14) further comprising a hydrogenation system (16) with a hydrogen supply (16) and a hydrogen feeding line (38). In order to achieve efficient and fast hydrogen injection into the primary reactor coolant, a high-pressure feeding pump (40) is arranged in the feeding line (38) to provide a gas pressure higher than the discharge pressure of the charging pump (32), wherein the feeding line (38) discharges into the charging line (34).
A monitoring method for monitoring at least one plant component of a power plant comprises the steps: - Receiving asset data associated with the plant component of the power plant; and - Processing the asset data received with at least one analyzing module (36) that applies machine learning and/or statistical methods, thereby generating analysis results (50), wherein the analysis results (50) comprise information on a condition of the plant component of the power plant. Further, a predicting method, a monitoring system (10) and a computer program are described.
The invention relates to a control rod position indication system (2) for a nuclear reactor (4) with a reactor core (8) and at least one control rod (6) which is movable along a linear path of movement for controlling the reactivity of the reactor core (8), the control rod position indication system (2) comprising • a permanent magnet (16) mounted on the control rod (6) or a corresponding drive rod (12), • a number of reed switches (20) arranged around the path of movement in order to be switched by a magnetic field generated by the permanent magnet (16) when passing by, wherein • the permanent magnet (16) has a north-south axis (18) whose orientation is constant during movement, and • the respective reed switch (20) has a number of reed contacts (22) which are aligned along a longitudinal axis (24). To improve reliability and/or detection accuracy for such a control rod position indication system (2), the invention suggests that the longitudinal axis (24) of at least one of the reed switches (20) is inclined relative to the north-south axis (18) of the permanent magnet (16), wherein the angle of inclination (W) has an absolute value within a range from 15 to 65 degrees.
G21C 17/10 - Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
G21C 17/12 - Sensitive element forming part of control element
G01D 5/251 - Selecting one or more conductors or channels from a plurality of conductors or channels, e.g. by closing contacts one conductor or channel
67.
SYSTEM FOR STERILIZING STERILIZATION UNITS AND METHOD FOR OPERATING SUCH A SYSTEM
The invention relates to a system (1) for sterilising sterilisation units (100) by means of exposure to radiation, more particularly for sterilising sterilisation units (100) containing medical objects by means of exposure to radiation, comprises a conveying system (8) for transporting the sterilisation units (100) through a sterilising environment along a conveying line. The sterilising environment is exposed to radioactive radiation from a radiation source (2). At least one conveying section (F3, F4, F5, F6, F7, F8, F9, F10) of the conveying line extends along the periphery of the radiation source (2). The radiation source (2), for example a Co60 source, emits gamma radiation. According to the invention, the conveying system (8) comprises at least one lifting beam conveyor (12) with at least one stationary support beam (32) and at least one moveable lifting beam (34), which can be moved in a longitudinal and vertical direction with respect to the at least one stationary support beam (32). The at least one stationary support beam (32) has a central region between two fixed bearings (46), which is supported via at least one tensile element (42) under tensile stress that is fastened on the central region and on at least one vertical strut (48) that is arranged in the region of at least one fixed bearing (46), the tensile element (42) being fastened such that it extends in a direction diagonal to the longitudinal and vertical direction.
B65G 25/02 - Conveyors comprising a cyclically-moving, e.g. reciprocating, carrier or impeller which is disengaged from the load during the return part of its movement the carrier or impeller having different forward and return paths of movement, e.g. walking-beam conveyors
68.
SYSTEM FOR STERILISING STERILISATION UNITS AND METHOD FOR OPERATING SUCH A SYSTEM
The invention relates to a system (1) for sterilising sterilisation units (100) by means of exposure to radiation, more particularly for sterilising sterilisation units (100) containing medical objects by means of exposure to radiation, comprises a conveying system (8) for transporting the sterilisation units (100) through a sterilising environment along a conveying line. The sterilising environment is exposed to radioactive radiation from a radiation source (2). At least one conveying section (F3, F4, F5, F6, F7, F8, F9, F10) of the conveying line extends along the periphery of the radiation source (2). The radiation source (2), for example a Co60 source, emits gamma radiation. According to the invention, the conveying system (8) comprises at least one lifting beam conveyor (12) with at least one stationary support beam (32) and at least one moveable lifting beam (34), which can be moved in a longitudinal and vertical direction with respect to the at least one stationary support beam (32). The at least one stationary support beam (32) has a central region between two fixed bearings (46), which is supported via at least one tensile element (42) under tensile stress that is fastened on the central region and on at least one vertical strut (48) that is arranged in the region of at least one fixed bearing (46), the tensile element (42) being fastened such that it extends in a direction diagonal to the longitudinal and vertical direction.
B65G 25/02 - Conveyors comprising a cyclically-moving, e.g. reciprocating, carrier or impeller which is disengaged from the load during the return part of its movement the carrier or impeller having different forward and return paths of movement, e.g. walking-beam conveyors
69.
PROBE SUPPORT APPARATUS FOR AN ULTRASONIC FLAW DETECTOR, ULTRASONIC FLAW DETECTOR AND METHOD FOR INSPECTING A WHEELSET AXLE
A probe support apparatus (12) for an ultrasonic flaw detector (10) is described. It comprises a probe holder (20) having at least two receptacles (42, 44) for ultrasonic probes (14, 16), and at least two magnetic rollers (22). The receptacles (42, 44) are inclined towards each other such that a middle axis (46) of a first receptacle (42) and a middle axis (48) of a second receptacle (44) are perpendicular to the axes (24) of rotation of the rollers (22). Additionally, an ultrasonic flaw detector (10) comprising such a probe support apparatus (12) is presented. Furthermore, a method for inspecting a wheelset axle using an ultrasonic flaw detector (10) is provided.
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
The invention relates to a nuclear power plant comprising a nuclear reactor and a reactor coolant circuit containing a reactor coolant, and further comprising a degasification system (2) for the reactor coolant. An objective underlying the pre- sent invention is to provide a nuclear power plant with a degasification system (2) which can be easily integrated into the surrounding systems with low space- demand, which in the case of existing plants can be adapted to various needs, and which works reliably and efficiently. To this end, the degasification system (2) is an ultrasonic degasification system comprising a sonotrode cluster (11) with at least one sonotrode (10) arranged in a line of the reactor coolant circuit or in a line which is fluidically connected to the reactor coolant circuit.
G21C 19/307 - Arrangements for introducing fluent material into the reactor coreArrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products specially adapted for liquids
A ventilation and air conditioning system (6) is for a room (2) containing a heat source and the ventilation and air conditioning system (6) comprising a cooled air supply (12) and a ventilation duct (10). The ventilation duct (10) includes a primary inlet (24) connected to the cooled air supply (12) and an outlet (14) leading into the room (2). A number of heat storage elements (30) is arranged inside the ventilation duct (10) between the primary inlet (24) and the outlet (14), such that during operation of the cooled air supply (12) there is a forced stream of cooled air through the ventilation duct (10), thereby cooling and preferably freezing the heat storage elements (30). A secondary inlet (36) into the ventilation duct (10) is in flow communication with the room (2) and during operation of the cooled air supply (12) is closed by a damper (40). The damper (40) is designed to automatically open in a passive manner when the forced stream of cooled air from the cooled air supply (12) stops, such that a natural convection airflow through the ventilation duct (10) is supported, and the natural convection airflow is cooled by transferring heat to the heat storage elements (30).
An irradiation target removal system comprises at least one storage container (34) for receiving activated irradiation targets (16) from an instrumentation tube system (12) of a nuclear reactor; a discharge tube (30) comprising a first discharge tube section (38), a second discharge tube section (40) and a conjunction of the first and second discharge tube sections (38, 40); and a supply (52) of pressurized gas connected to the first discharge tube section (38) for pressurizing the discharge tube (30). The second discharge tube section (40) is coupled to the instrumentation tube system (12), wherein the first discharge tube section (38) comprises an exit port (32) assigned to the storage container (34); a first lock element (36) for blocking movement of the activated irradiation targets (16) to the storage container (34), wherein the first lock element (36) is located between the exit port (32) and the conjunction; and at least one opening (46) located between the first lock element (36) and the conjunction, wherein the supply (52) of pressurized gas is connected to the at least one opening (46). Further, a radioisotope generation system, a discharge tube and a method for removing activated irradiation targets from an instrumentation tube system of a nuclear reactor are shown.
G21G 1/02 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
73.
SYSTEM AND METHOD FOR REMOVING IRRADIATION TARGETS FROM A NUCLEAR REACTOR AND RADIONUCLIDE GENERATION SYSTEM
An irradiation target removal system comprises at least one storage container (34) for receiving activated irradiation targets (16) from an instrumentation tube system (12) of a nuclear reactor; a discharge tube (30) comprising a first discharge tube section (38), a second discharge tube section (40) and a conjunction of the first and second discharge tube sections (38, 40); and a supply (52) of pressurized gas connected to the first discharge tube section (38) for pressurizing the discharge tube (30). The second discharge tube section (40) is coupled to the instrumentation tube system (12), wherein the first discharge tube section (38) comprises an exit port (32) assigned to the storage container (34); a first lock element (36) for blocking movement of the activated irradiation targets (16) to the storage container (34), wherein the first lock element (36) is located between the exit port (32) and the conjunction; and at least one opening (46) located between the first lock element (36) and the conjunction, wherein the supply (52) of pressurized gas is connected to the at least one opening (46). Further, a radioisotope generation system, a discharge tube and a method for removing activated irradiation targets from an instrumentation tube system of a nuclear reactor are shown.
G21G 1/02 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
G21C 23/00 - Adaptations of reactors to facilitate experimentation or irradiation
09 - Scientific and electric apparatus and instruments
42 - Scientific, technological and industrial services, research and design
Goods & Services
(1) Computer programs, software and software packages, recorded and downloadable, for monitoring and surveillance of constructions and industrial installations, namely material aging and plant life monitoring; modular computer software platforms, recorded and downloadable, for monitoring and surveillance of constructions and industrial installations, namely material aging and plant life monitoring; modular computer software platforms, recorded and downloadable, for monitoring and surveillance of constructions and industrial installations, namely material aging and plant life monitoring, featuring functions for plant modeling and parameter management, engineering tools and input data validation, material library data and standard management, commodity grouping, management of plant program activities, validation of inspection and maintenance activities and intervals, technical documentation management, operational experience feedback management, and aging management review reporting; modular computer software platforms, recorded and downloadable, for monitoring and surveillance of mechanical components, featuring functions for material aging and degradation prediction, material degradation sensitivity assessment, prioritization of inspection and maintenance activities, examination data management, material data management, and active components reliability assessment, in particular for use in constructions and industrial installations; modular computer software platforms, recorded or downloadable, for monitoring and surveillance of electrical and instrumentation and control system components, featuring functions for life time analysis and qualification, function chains modeling, managing and evaluation, management of cable materials and environmental conditions history, management and trending of inspections on components, cables or function chains to calibrate and validate prediction results, prioritization of inspection activities, and examination data management, in particular for use in constructions and industrial installations; modular computer software platforms, recorded or downloadable, for monitoring and surveillance of civil structures, featuring functions for degradation assessment of civil structures considering material, design, and history of environmental conditions, lifetime assessment, inspection management and inspection feedback evaluation, defect trend analysis and remaining life analysis, integrity assessment and reporting; prioritization of inspection and maintenance activities, and examination data management; modular computer software platforms, recorded or downloadable, for monitoring and surveillance of constructions and industrial installations, featuring data import from connected systems, plant structure mapping, trend analysis, data analysis according to equipment operating condition, automatic diagnosis and prognosis proposal with indication of event severity, and event standard reports; all afore-mentioned goods for use in the field of aging management of constructions and in the field of aging management of industrial installations; Monitoring system comprising meters and sensors to collect operational data and environmental conditions to determine material aging and calculating plant life, and including alarm and reporting functions; alarm monitoring systems for industrial installations in the fields of power generation (1) Research and development services in the field of engineering; services of engineers, namely, simulation and monitoring services in the fields of energy and power generation; services of engineers, namely, monitoring of nuclear materials, and monitoring of nuclear and non-nuclear installations and equipment; design, programming, updating, maintenance and rental of software used for monitoring and surveillance of constructions and industrial installations, including material aging and plant life monitoring, in particular for use in the field of energy and power generation; software development and implementation services for software used for monitoring and surveillance of installations, including material aging and plant life monitoring, in particular for use in the field of energy and power generation; hosting services; software as a service in relation to software used for monitoring and surveillance of constructions and industrial installations, including material aging and plant life monitoring, in particular for use in the field of energy and power generation; all afore-mentioned services for use in the field of aging management of constructions and in the field of aging management of industrial installations.
09 - Scientific and electric apparatus and instruments
42 - Scientific, technological and industrial services, research and design
Goods & Services
Apparatus, instruments and devices for monitoring and surveillance of industrial installations in the fields of power generation, namely, monitoring system comprising meters and sensors to collect operational data and environmental conditions to determine material aging and calculating plant life, and including alarm and reporting functions; alarm monitoring systems for industrial installations; Recorded and downloadable computer programs for monitoring and surveillance of constructions and industrial installations, namely, material aging and plant life monitoring; Recorded and downloadable software for monitoring and surveillance of constructions and industrial installations, namely, material aging and plant life monitoring; software packages featuring recorded and downloadable software for monitoring and surveillance of constructions and industrial installations, namely, material aging and plant life monitoring; modular computer software platforms, recorded and downloadable, for monitoring and surveillance of constructions and industrial installations, namely, material aging and plant life monitoring; Modular computer software platforms, recorded and downloadable, for monitoring and surveillance of constructions and industrial installations, namely, material aging and plant life monitoring, featuring functions for plant modeling and parameter management, engineering tools and input data validation, material library data and standard management, commodity grouping, management of plant program activities, validation of inspection and maintenance activities and intervals, technical documentation management, operational experience feedback management, and aging management review reporting; modular computer software platforms, recorded and downloadable, for monitoring and surveillance of mechanical components, featuring functions for material aging and degradation prediction, material degradation sensitivity assessment, prioritization of inspection and maintenance activities, examination data management, material data management, and active components reliability assessment, for use in constructions and industrial installations; modular computer software platforms, recorded and downloadable, for monitoring and surveillance of electrical and instrumentation and control system components, featuring functions for life time analysis and qualification, function chains modeling, managing and evaluation, management of cable materials and environmental conditions history, management and trending of inspections on components, cables or function chains to calibrate and validate prediction results, prioritization of inspection activities, and examination data management, for use in constructions and industrial installations; modular computer software platforms, recorded and downloadable, for monitoring and surveillance of civil structures, featuring functions for degradation assessment of civil structures considering material, design, and history of environmental conditions, lifetime assessment, inspection management and inspection feedback evaluation, defect trend analysis and remaining life analysis, integrity assessment and reporting, prioritization of inspection and maintenance activities, and examination data management; modular computer software platforms, recorded and downloadable, for monitoring and surveillance of constructions and industrial installations, featuring data import from connected systems, plant structure mapping, trend analysis, data analysis according to equipment operating condition, automatic diagnosis and prognosis proposal with indication of event severity, and event standard reports * ; all afore-mentioned goods for use in the field of aging management of constructions and in the field of aging management of industrial installations * Research and development services in the field of engineering; services of engineers, namely, simulation and monitoring of energy and power generation installations in relation to material aging and plant life; services of engineers, namely, monitoring of nuclear materials, and monitoring of nuclear and non-nuclear installations and equipment to ensure proper functioning and to control material aging and plant life; Design, programming, updating, maintenance and rental of software used for monitoring and surveillance of constructions and industrial installations, namely, material aging and plant life monitoring for use in the field of energy and power generation; software development and implementation services for software used for monitoring and surveillance of installations, namely, material aging and plant life monitoring for use in the field of energy and power generation; website hosting services; server hosting; software as a service featuring software used for monitoring and surveillance of constructions and industrial installations, namely, material aging and plant life monitoring for use in the field of energy and power generation * ; all afore-mentioned services for use in the field of aging management of constructions and in the field of aging management of industrial installations *
76.
METHOD OF GOVERNING A PRESSURIZED WATER NUCLEAR REACTOR AND ACCORDING GOVERNANCE SYSTEM
The present invention aims to provide a method of governing a pressurized water nuclear reactor which can simultaneously consider and balance a large number of control goals. According to the invention this is achieved by a method for governing a pressurized water nuclear reactor (2), the pressurized water nuclear reactor (2) comprising a reactor core (6) and a cooling circuit (10) for the reactor core (6) holding a reactor coolant, the reactor state being characterized by a number of measurable state variables, and the reactor core reactivity being controlled by a number of actuating variables and impacted by reactor poisoning, wherein for a given time-dependent trajectory (Ta) of actuating variables according trajectories (Ts) for the state variables are predicted on the basis of measured current values of the state variables, calculated poisoning values and a reactivity balance equation, the method comprising iteratively considering a large number of randomly varied possible trajectories (Ta) of the actuating variables for a future time interval, wherein each trajectory (Ta) of actuating variables is assigned a figure of merit (?) on the basis of a Value Table which contains weighting or penalty values for a number of events or adverse reactor core states which are characterized by preset conditions or values of the actuating variables, the process variables and/or variables derived from them, wherein the trajectory (Ta) of actuating variables is chosen such that the figure of merit (?) has a local extremum, and wherein corresponding actuators are moved accordingly.
G21D 3/08 - Regulation of any parameters in the plant
G21C 5/12 - Moderator or core structureSelection of materials for use as moderator characterised by composition, e.g. the moderator containing additional substances which ensure improved heat resistance of the moderator
G21C 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
77.
METHOD OF GOVERNING A PRESSURIZED WATER NUCLEAR REACTOR AND ACCORDING GOVERNANCE SYSTEM
The present invention aims to provide a method of governing a pressurized water nuclear reactor which can simultaneously consider and balance a large number of control goals. According to the invention this is achieved by a method for governing a pressurized water nuclear reactor (2), the pressurized water nuclear reactor (2) comprising a reactor core (6) and a cooling circuit (10) for the reactor core (6) holding a reactor coolant, the reactor state being characterized by a number of measurable state variables, and the reactor core reactivity being controlled by a number of actuating variables and impacted by reactor poisoning, wherein for a given time-dependent trajectory (Ta) of actuating variables according trajectories (Ts) for the state variables are predicted on the basis of measured current values of the state variables, calculated poisoning values and a reactivity balance equation, the method comprising iteratively considering a large number of randomly varied possible trajectories (Ta) of the actuating variables for a future time interval, wherein each trajectory (Ta) of actuating variables is assigned a figure of merit (Σ) on the basis of a Value Table which contains weighting or penalty values for a number of events or adverse reactor core states which are characterized by preset conditions or values of the actuating variables, the process variables and/or variables derived from them, wherein the trajectory (Ta) of actuating variables is chosen such that the figure of merit (Σ) has a local extremum, and wherein corresponding actuators are moved accordingly.
The invention relates to a steam generator (6) for a pressurized water reactor, comprising a tube sheet (34), a steam space (36) adjoining the tube sheet (34), and a number of steam generator tubes (4) being designed to carry a primary re- actor coolant during normal operation, wherein each steam generator tube (4) comprises a first tube section being fixed in the tube sheet (34) and a second tube section protruding into the steam space (36), and wherein at least one of the steam generator tubes (4) is closed by a sealing plug (40) inserted into the first tube section. In order to minimize the risk of rupture of the such-closed steam generator tube (4) in a manner which is easy to produce, to install, and to maintain, the invention suggest a separate stabilizer (2) inserted into said closed steam generator tube (4) adjacent to or above the sealing plug (40), the stabilizer (2) comprising a lengthy body (8) with a clamping section (30) fixed inside the first tube section and a sup- porting section (26) resting against the second tube section, wherein the stabilizer (2) is designed to permit a fluid flow through and/or around its body (8).
F22B 1/16 - Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being hot liquid or hot vapour, e.g. waste liquid, waste vapour
F22B 37/00 - Component parts or details of steam boilers
79.
Oscillation damper, in particular for a switch cabinet
A passive oscillation damper (8), in particular for a switch cabinet (2), includes a supporting structure (12) having a longitudinal direction (y) and a transverse direction (x) and with a central oscillating mass (14) mounted by means of spring elements (20, 22, 24, 26) so as to be able to oscillate in the longitudinal direction (y) and in the transverse direction (x). At least one peripheral oscillating mass (40, 42) is mounted on the central oscillating mass (14) so as to be slidable in the longitudinal direction (y) and to be movable relative to the central oscillating mass (14). At least one peripheral oscillating mass (44, 46) is mounted on the central oscillating mass (14) so as to be slidable in the transverse direction (x) and to be movable relative to central oscillating mass (14).
F16F 7/116 - Vibration-dampersShock-absorbers using inertia effect the inertia member being resiliently mounted on metal springs
F16F 15/14 - Suppression of vibrations in rotating systems by making use of members moving with the system using freely-swinging masses rotating with the system
F16F 7/14 - Vibration-dampersShock-absorbers of cable-support type, i.e. frictionally-engaged loop-forming cables
F16F 15/06 - Suppression of vibrations of non-rotating, e.g. reciprocating, systemsSuppression of vibrations of rotating systems by use of members not moving with the rotating system using elastic means with metal springs
For the purposes of stabilizing a pipe connection in which a first pipe (10) is plugged into a second pipe (12) which has an insertion funnel (20), there is provision according to invention of a stabilizer element (22) which has a clamping ring (24) with a plurality of clamping bodies (48) which are distributed over its circumference and which, in the assembly end position, engage in an interspace between the first pipe (10) and the insertion funnel (20) and brace the first pipe (10) and the second pipe (12) against one another, and wherein the clamping ring (24) is composed of a plurality of ring segments which can be connected to one another, in particular of two half-shells (34).
A method for conditioning of spent ion exchange resins from nuclear facilities comprises the steps of: mixing the spent ion exchange resins with water to form a reaction mixture; setting and controlling the pH of the reaction mixture in a range from 1.0 to 3.5; adding an oxidant to the reaction mixture, with the temperature of the reaction mixture maintained at 90 C or less so that the spent ion exchange resin and the oxidant react with each other to form an aqueous reaction solution comprising the organic reaction products of the spent ion exchange resin; and electrochemically oxidizing the organic reaction products, wherein carbon dioxide is produced and a carbon-depleted aqueous reaction solution having a TOC (total organic carbon) value of less than 50 ppm is obtained. Furthermore, an apparatus for the conditioning of spent ion exchange resins from nuclear facilities is described.
The invention relates to a method for conditioning consumed ion exchange resins from nuclear plants, comprising the following steps: mixing the consumed ion exchange resins with water to form a reaction mixture; adjusting and monitoring the pH of the reaction mixture in a range of from 1.0 to 3.5, preferably in a range of from 2.0 to 3.0; adding an oxidant to the reaction mixture, wherein the temperature of the reaction mixture is kept at 90°C or less, such that the consumed ion exchange resin and the oxidant react with each other in order to form an aqueous reaction solution, which comprises organic reaction products of the consumed ion exchange resin; and electrochemically oxidizing the organic reaction products, wherein carbon dioxide is formed and a carbon-depleted, aqueous reaction solution having a TOC value (total organic carbon) of less than 50 ppm is obtained. The invention further relates to an apparatus for conditioning consumed ion exchange resins from nuclear plants.
The invention relates to a device, an arrangement and a method for characterizing the torsion, rotation, and/or positioning of a shaft by generating a periodic magnetic field of a magnetic field generator disposed between at least two magnetic field detectors by applying a periodic exciter signal. The field is modified by the shaft and induces an output signal at each of the magnetic field detectors. The difference with respect to amplitude or phase between the exciter signal and the first output signal is detected as a first measured variable and between the exciter signal and the second output signal is detected as a second measured variable. The total of and/or the difference between the first and the second measured variables is calculated, and the torsion, rotation, and/or positioning of the shaft is characterized based thereon.
G01D 5/22 - Mechanical means for transferring the output of a sensing memberMeans for converting the output of a sensing member to another variable where the form or nature of the sensing member does not constrain the means for convertingTransducers not specially adapted for a specific variable using electric or magnetic means influencing the magnitude of a current or voltage by varying inductance, e.g. by a movable armature differentially influencing two coils
G01D 5/14 - Mechanical means for transferring the output of a sensing memberMeans for converting the output of a sensing member to another variable where the form or nature of the sensing member does not constrain the means for convertingTransducers not specially adapted for a specific variable using electric or magnetic means influencing the magnitude of a current or voltage
G01L 3/10 - Rotary-transmission dynamometers wherein the torque-transmitting element comprises a torsionally-flexible shaft involving electric or magnetic means for indicating
84.
Method and device for multielement analysis on the basis of neutron activation, and use
A method for a multielement analysis via neutron activation. The method includes generating fast neutrons with an energy in the range of 10 keV to 20 MeV and moderating the neutrons, irradiating the sample with the neutrons, and measuring the gamma radiation emitted by the irradiated sample using a detector to determine at least one element of the sample. The sample continuously irradiated in a non-pulsed fashion. The measurement is implemented during the irradiation. The determination of the at least one element includes an evaluation of the measured gamma radiation. The sample is subdivided into individual partitions and the measurement is implemented using a collimator. The evaluation includes a spatially resolved and energy-resolved determination of the neutron flux within the respective partition of the sample and calculation of energy-dependent photopeak efficiencies and neutron flux and neutron spectrum within a single partition of the sample by an approximation method.
G01N 23/22 - Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups , or by measuring secondary emission from the material
G01N 23/223 - Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups , or by measuring secondary emission from the material by irradiating the sample with X-rays or gamma-rays and by measuring X-ray fluorescence
A welding torch (18) for a welding system (10) is described, which comprises a substantially spherical main body (20) that has an integrated coolant chamber (60) which is in fluid communication with at least one coolant port (62). The substantially spherical main body (20) is a joint head (22) of a ball joint (24) of the welding system (10). Further, a welding system (10), a method of producing a welding torch (18) as well as a computer-readable medium are described.
The invention provides a cartridge for use as an irradiation target (10), wherein the cartridge comprises a housing (12) and a sealed ampoule (14) included in said housing, wherein the ampoule (14) contains a parent material (16) which on activation by neutron flux converts into a radioisotope, and wherein the ampoule (14) is kept within said housing (12) by means of a shock absorbing material (24). The cartridge is used as an irradiation target (10) in a method of producing radioisotopes in a moderator (104) of a heavy water nuclear reactor.
G21G 1/02 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
H05H 6/00 - Targets for producing nuclear reactions
87.
CARTRIDGE AND USE OF THE CARTRIDGE IN A METHOD OF PRODUCING RADIOISOTOPES
The invention provides a cartridge for use as an irradiation target (10), wherein the cartridge comprises a housing (12) and a sealed ampoule (14) included in said housing, wherein the ampoule (14) contains a parent material (16) which on activation by neutron flux converts into a radioisotope, and wherein the ampoule (14) is kept within said housing (12) by means of a shock absorbing material (24). The cartridge is used as an irradiation target (10) in a method of producing radioisotopes in a moderator (104) of a heavy water nuclear reactor.
G21G 1/02 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
H05H 6/00 - Targets for producing nuclear reactions
A lance unit (32) for usage in a nuclear reactor core (15) is described., comprising a nuclide activation system (22), a nuclear monitoring system (14), a tube system (28) and a yoke (34) holding the tube system (28), wherein the nuclear monitoring system (14) has at least one nuclear monitoring tube (16) for accommodating monitoring members (18) that monitor the nuclear reactor core (15), wherein the nuclide activation system (22) has a nuclide activation tube (24) for accommodating at least one irradiation target (26) to be exposed to neutron flux in the nuclear reactor (12) to form a radionuclide, wherein the at least one nuclear monitoring tube (16) and the nuclide activation tube (24) are part of the tube system (28), wherein the nuclide activation tube (24) has an internal stop(40) configured to stop the at least one irradiation target (26), and wherein the internal stop (40) of the nuclide activation tube (24)is located at a different height with regard to the lower end of the nuclear monitoring tube (16). Further, a nuclide activation and nuclear monitoring system(10) and a method of producing radionuclides are described.
G21G 1/02 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
A process for recovering uranium from components contaminated with uranium oxide includes providing a cleaning apparatus with a cleaning solution for dissolving the uranium oxide of the components, carrying out a cleaning process by introducing a batch of components into the cleaning apparatus, and carrying out a measurement for determining the uranium content of the components. The cleaning and the measuring are repeated if a limit value for the uranium content is exceeded. The components are discharged from the process if the uranium content falls below a limit value. The cleaning is carried out on a plurality of successive batches of components until a control measurement indicates an unsatisfactory cleaning action of the cleaning solution. The uranium oxide dissolved in the cleaning solution is recovered after indication of the unsatisfactory cleaning action.
A nuclear facility has a fuel pool containing a liquid and an associated cooling circuit for a circulating cooling agent. The cooling circuit contains a cooling module with a first heat exchanger which immerges into the liquid, a second heat exchanger which is located outside the fuel pool, and connecting lines between the first exchanger and the second heat exchanger. In order to provide for reliable cooling even if a filling level drops, the cooling module contains a lifting body and floats in the liquid such that its altitude varies with the filling level of the liquid in the fuel pool.
G21C 19/40 - Arrangements for preventing occurrence of critical conditions, e.g. during storage
F28D 1/02 - Heat-exchange apparatus having stationary conduit assemblies for one heat-exchange medium only, the media being in contact with different sides of the conduit wall, in which the other heat-exchange medium is a large body of fluid, e.g. domestic or motor car radiators with the heat-exchange conduits immersed in the body of fluid
F28D 20/00 - Heat storage plants or apparatus in generalRegenerative heat-exchange apparatus not covered by groups or
A repairing system (2) is described that is used for applying an adhesive to a location to be repaired underwater in a container. The repairing system (2) comprises a movable and remotely controlled repairing robot (10) that is configured to be driven underwater. The repairing robot (10) comprises a repairing module (12) that is configured to be coupled with an adhesive applying module (34). The adhesive applying module (34) is configured to dispense an adhesive on the location to be repaired. Further, a repairing method is described.
G21C 17/01 - Inspection of the inner surfaces of 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
The invention relates to a disposal apparatus (2) for reliable and reproducible disposal of nuclear fuel (62) in the form of fuel slurry and/or particles contained in a liquid (60), without substantially contaminating a tool required for this, said disposal apparatus comprising • a filter (4) having a filter cartridge (14), which can be brought into fluidic connection with the liquid (60), • a tool (6) for sucking in the liquid (60), having a piston (10) which can move preferably in a linear manner, wherein the tool (6) can be fastened to the filter (4) such that pressure changes are caused in the filter (4) by a movement of the piston (10), and therefore, when used as intended, the sucked-in liquid (60) flows through the filter cartridge (14) and the fuel (62) is deposited in the filter cartridge (14).
A catalytic recombiner and filter apparatus is especially suited for placement in a containment of a nuclear reactor. The apparatus has a natural convection flow duct with a number of catalytic elements for recombining hydrogen and oxygen contained in a gas flow through the flow duct. The catalytic recombiner and filter apparatus provides for reliable hydrogen reduction and iodine filtering for a gas flow even for a comparatively long period of operation. The catalytic recombiner and filter apparatus includes a number of adsorber elements with iodine adsorbing surfaces and with macroscopic flow channels in between. The iodine adsorbing surfaces are flown over by the gas flow, and the adsorber elements are arranged, when in use, downstream of the catalytic elements in a direction of the gas flow.
B01D 53/04 - Separation of gases or vapoursRecovering vapours of volatile solvents from gasesChemical or biological purification of waste gases, e.g. engine exhaust gases, smoke, fumes, flue gases or aerosols by adsorption, e.g. preparative gas chromatography with stationary adsorbents
94.
METHOD AND DEVICE FOR THE DETERMINATION OF FILM FORMING AMINES IN A LIQUID
A photometric method for the determination of a film forming amine in a liquid, comprises the steps of a) providing a buffer solution of a weak acid having a pKa ≥ 4.5 and a strong acid having a pKa ≤ 1; b) diluting an aliquot of the buffer solution with a given volume of water, and determining a pH value of said diluted buffer solution; c) adding a given amount of a reagent to said diluted buffer solution and measuring an initial absorbance of said diluted buffer solution containing the reagent; d) preparing a sample solution by adding a given volume of the liquid containing the film forming amine to an aliquot of the buffer solution and measuring a pH value of the sample solution; e) adjusting the pH value of the sample solution to match with the pH value of the diluted buffer solution by adding a calculated amount of the strong acid; and f) adding a given amount of said reagent to the pH adjusted sample solution to form a colored complex, and measuring the absorbance of the pH adjusted sample solution containing the reagent and the colored complex in a photometer.
G01N 31/22 - Investigating or analysing non-biological materials by the use of the chemical methods specified in the subgroupsApparatus specially adapted for such methods using chemical indicators
G01N 21/25 - ColourSpectral properties, i.e. comparison of effect of material on the light at two or more different wavelengths or wavelength bands
95.
METHOD AND DEVICE FOR THE DETERMINATION OF FILM FORMING AMINES IN A LIQUID
A photometric method for the determination of a film forming amine in a liquid, comprises the steps of a) providing a buffer solution of a weak acid having a pKa >= 4.5 and a strong acid having a pKa <=1; b) diluting an aliquot of the buffer solution with a given volume of water, and determining a pH value of said diluted buffer solution; c) adding a given amount of a reagent to said diluted buffer solution and measuring an initial absorbance of said diluted buffer solution containing the reagent; d) preparing a sample solution by adding a given volume of the liquid containing the film forming amine to an aliquot of the buffer solution and measuring a pH value of the sample solution; e) adjusting the pH value of the sample solution to match with the pH value of the diluted buffer solution by adding a calculated amount of the strong acid; and f) adding a given amount of said reagent to the pH adjusted sample solution to form a colored complex, and measuring the absorbance of the pH adjusted sample solution containing the reagent and the colored complex in a photometer.
G01N 31/22 - Investigating or analysing non-biological materials by the use of the chemical methods specified in the subgroupsApparatus specially adapted for such methods using chemical indicators
G01N 21/25 - ColourSpectral properties, i.e. comparison of effect of material on the light at two or more different wavelengths or wavelength bands
96.
MODULARLY CONSTRUCTED PUSH-IN TRANSDUCER UNIT AND INSTRUMENTATION AND CONTROL POWER SUPPLY SYSTEM FOR A NUCLEAR POWER PLANT
A modularly constructed push-in transducer (20) for a switchgear cabinet (12) of an instrumentation and control power supply system (10) of a nuclear power plant is described, comprising a frame (28), at least one busbar (42), a group of fuses (38) and a group of load clamps (22). An instrumentation and control power supply system (10) for a nuclear power plant is also described.
A gripper a fuel element, comprises a housing, an inner part arranged inside the housing, the inner part and the housing being displaceable relative to one another in an axial direction, with the inner part movable between a first end position and a second end position, a catch member movable between a gripping position and a release position, a gripper spring between the housing inner part counteracting movement of the inner part from the second end position, or an intermediate position (Z) between the first and second end position, to the first end position, and a damping system comprising a first and second connecting member for connecting the damping system to the housing, inner part and/or the fuel element loading machine, and a spring member arranged on the first and/or the second connecting member counteracting movement of the inner part from an intermediate position (Z) to the second end position.
B66C 1/66 - Load-engaging elements or devices attached to lifting, lowering, or hauling gear of cranes, or adapted for connection therewith for transmitting forces to articles or groups of articles by mechanical means comprising article-engaging members of a shape complementary to that of the articles to be handled for engaging holes, recesses, or abutments on articles specially provided for facilitating handling thereof
G21C 19/105 - Lifting devices or pulling devices adapted for co-operation with fuel elements or with control elements with grasping or spreading coupling elements
The invention relates to a nuclear system, in particular a nuclear power plant (2), comprising a containment (4) and an associated venting system (6), which has a venting line (8) connected to the containment (4), wherein an emission monitoring system (16) is provided for the venting system (6). The object of the invention is to provide a device and an associated method for obtaining a representative measuring sample, which is taken from the clean gas line of the venting system, and which can be tested for aerosol-type decomposition products online in a subsequent analysis system. In addition, according to the invention, the emission monitoring system comprises a sampling line (44) for a sample flow branching off from the venting line (8) and leading into a sample container (32), and a recirculation line (54) leading from the sample container (32) to the venting line (8), wherein the sample container (32) contains a wet scrubber (34) for the sample flow, as well as an ionisation separator (64) downstream of the wet scrubber (34) in relation to the sample flow, and wherein a liquid removal line (78) leads from the sample container (32) to an analysis unit (20).
The invention relates to a target platform (10) for the processing of irradiated targets from a nuclear reactor, comprising at least one target tube (12), which extends along the target platform (10) and is designed to hold targets, a detector assembly (14) having one or more radiation detectors (16), which are arranged above the target tube (12), and a calibration device for calibrating the radiation detectors (16) in the detector assembly (14), characterized in that the calibration device comprises a guide element (28), which is arranged in the measurement table (10) near the at least one target tube (12) and also comprises at least one radiation source (32) mounted on a positioning element (32), the radiation source (32) being designed in such a way that the radiation source can be moved along the guide element (28) by means of the positioning element (36) in order to position the radiation source (32) below each of the radiation detectors (16). The invention relates to a method for calibrating the radiation detectors (16) using the target platform (10) and to the use of the target platform (10) for an aeroball measurement system or a nuclide activation system in a nuclear reactor.
G01N 23/00 - Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups , or
G01T 7/00 - Details of radiation-measuring instruments
G21G 1/02 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
