The invention relates to a method for identifying an acoustic source in a component (2), in particular a component of a power plant, comprising the following steps : a) determining at least one simulated structure-borne noise signature (KSi,j) of a simulated acoustic source for at least one observation point (BSk) by use of a simulation model (S) of the component, whereby the simulated structure- borne noise signature (KSi,j) is at least related to a position (ASi) of the simulated acoustic source, b) detecting at least one real structure-borne noise signature (KRi) of a real acoustic source at at least one measuring point (BRk), wherein the at least one measuring point (BRk) corresponds to at least one observation point (BSk), c) comparing the actual structure-borne noise signature (KRi) detected at measuring point (BRk) to the simulated structure-borne noise signature (KSi,j) simulated for the corresponding observation point (BSk), d) identifying at least a position (ARi) of the real acoustic source in the component (2) based on the result of the comparison between the real structure- borne noise signature (KRi) measured at measuring point (BRk) and the simulated structure-borne noise signature (KSi,j) simulated for the corresponding observation point (BSk).
G01N 29/14 - Recherche ou analyse des matériaux par l'emploi d'ondes ultrasonores, sonores ou infrasonores; Visualisation de l'intérieur d'objets par transmission d'ondes ultrasonores ou sonores à travers l'objet utilisant des techniques d'émission acoustique
2.
METHOD FOR PRODUCING A LAYER ON A SURFACE OF A COMPONENT AND METHOD FOR PRODUCING A WELDED JOINT
The invention relates to a method for producing at least one layer (2, 16, 32, 46, 70, 72) on a surface (6, 12, 14, 36, 42, 44, 66, 68) of a component (8, 38, 62), wherein the layer (2, 16, 32, 46, 70, 72) is produced by at least two or more weld layers (4a, 4b, 4c, 34a, 34b, 34c), comprising the following steps: a) a first weld layer (4a, 34a) is produced on the surface (6, 12, 14, 36, 42, 44, 66, 68) of the component (8, 38, 62); b) at least a part of the first weld layer (4a, 34a) is removed, c) a second weld layer (4b, 34b) is produced on one surface (24, 54) of the first weld layer is (4a, 34a), which results from the partial removal of the first weld layer (4a, 34a), wherein the at least one part of the first weld layer (4a, 34a) is removed mechanically, in particular in a turning or milling process, to such an extent that a hardness of the component (8, 38, 62) is reduced after the production of the layer (2, 16, 32, 46, 70, 72) to a maximum of 300 HV5. The invention further relates to a method for producing a welded joint between a first component (62), on the surface (6, 12, 14, 36, 42, 44, 66, 68) of which such a layer (2, 16, 32, 46, 70, 72) is produced, and a second component (64).
The invention relates to a method for cleaning coatings from cooling towers (10) and/or trickle stacks (11) in cooling towers (10), comprising the steps of: – emptying the cooling water from the cooling tower basin (12) of the cooling tower (10), – mechanically removing the coatings, in particular the coatings which have dried as a consequence of emptying, – refilling the cooling tower basin (12) with water up to a zero delivery height, – adding acid, in particular nitric acid, to the water in the cooling tower basin (12) so as to form a cleaning solution in order to remove any coatings remaining after mechanical removal of the coatings.
The invention relates to a static measuring device (1) for cooling towers (20), in particular cooling towers (20) of power plants, comprising at least one measuring train (2) between two opposite sides of the cooling tower (20), wherein at least one measuring gondola (3) is provided so as to be able to move on the at least one measuring train (2), wherein the measuring gondola (3) comprises at least one sensor (4) for taking measurements in the cooling tower interior (18) during operation of the cooling tower (20). The invention also relates to a method for taking measurements inside a cooling tower (20), in particular using a measuring device (1) according to the invention.
F28F 27/00 - Commandes ou dispositifs de sécurité spécialement adaptés pour les appareils d'échange ou de transfert de chaleur
F28F 25/00 - PARTIES CONSTITUTIVES OU AMÉNAGEMENTS, D'APPLICATION GÉNÉRALE, DES DISPOSITIFS ÉCHANGEURS DE CHALEUR OU DE TRANSFERT DE CHALEUR - Parties constitutives des réfrigérateurs à ruissellement
G01N 35/00 - Analyse automatique non limitée à des procédés ou à des matériaux spécifiés dans un seul des groupes ; Manipulation de matériaux à cet effet
G01M 9/00 - Tests aérodynamiques; Aménagements dans ou sur les souffleries
5.
METHOD AND SYSTEM FOR DISPOSING AND RECYCLING OF A RADIOACTIVE CONTAMINATED COMPONENT
The invention relates to a method and system for disposing and/or recycling of a radioactive contaminated component of a nuclear power plant, in particular a radioactive contaminated graphite moderator, comprising the following steps : - a thermal treatment step (II) wherein the radioactive contaminated component is thermally treated at a temperature at which a gas mixture (2a) containing carbon monoxide is formed, - at least one subsequent separation step (V) wherein the gas mixture (2a, 2b) is supplied to a separating device (16) for separating components present in the gas mixture (2a, 2b), in particular for separating radioactive carbon monoxide 14CO and non-reactive carbon monoxide 12CO, from each other.
The invention relates to a separating device (2) for separating a first and a second component of a mixture, comprising a housing (4) with a cylindrical housing part (6), an upper lid (8) and a lower lid (10) forming a separating chamber (12) there between, further comprising a rotor (14) being rotatable arranged within the housing (4), further comprising at least one inlet port (24) being provided in the housing (4) for supplying the mixture to the separating chamber (12), further comprising at least one first outlet port (26) for discharging the first component of the mixture and at least one second outlet port (28) for discharging the second component of the mixture, each being provided in the housing (4), further comprising a separation wall (30) being arranged within the housing (4), whereby at least the lower lid (10) and the cylindrical housing part (6) are integrally formed.
B04B 5/08 - Centrifugeurs pour séparer des mélanges essentiellement gazeux
B04B 5/12 - Centrifugeurs dans lesquels l'action centrifuge agissant dans un récipient stationnaire est obtenue par des organes rotatifs autres que des tambours
The invention relates to a shut-off fitting which reliably closes in a passive manner in the event of a critical temperature of the fluid flowing through the fitting and which is preferably resistant to the loads in the nuclear sector. According to the invention, this is achieved by a shut-off fitting (2) for a pipeline, comprising • a housing (4) which surrounds a flow channel (20), • a closure element (6) which is arranged in the flow channel (20) and which can be converted from an open position into a closed position and • a first spring element (32) which is arranged in the flow channel (20), consists of a shape-memory material, and is operatively connected to the closure element (6), wherein the shape of the spring element (32) changes when a switching temperature (Tc) is reached or exceeded, thus bringing the closure element (6) into the closed position.
G21C 13/036 - Raccords entre le tube et la paroi d'une enceinte, p.ex. tenant compte des contraintes thermiques le tube traversant la paroi, c. à d. s'étendant de chaque côté
G21C 13/067 - Bouchons scellés pour des tubulures, p.ex. puits de chargement; Dispositifs de verrouillage pour bouchons
F01P 7/16 - Commande du débit de l'agent de refroidissement l'agent de refroidissement étant un liquide par commande thermostatique
F16K 15/14 - Soupapes, clapets ou valves de retenue à corps de soupapes flexibles
F16L 55/128 - Moyens pour arrêter l'écoulement dans les tuyaux ou manches en introduisant dans le tuyau un élément expansible in situ introduits axialement dans le tuyau ou la manche
8.
RADIONUCLIDE GENERATION SYSTEM AND METHOD OF PRODUCING RADIONUCLIDES
A method of producing radionuclides from irradiation targets in a nuclear reactor uses at least one instrumentation tube system (12) of a commercial nuclear reactor. Irradiation targets (16) and dummy targets (18) are inserted into an instrumentation finger (14) and the irradiation targets (16) are activated by exposing them to neutron flux in the nuclear reactor core (10) to form a desired radionuclide. The dummy targets (18) hold the irradiation targets (16) at a predetermined axial position in the reactor core corresponding to a pre-calculated neutron flux density sufficient for converting the irradiation targets (16) to the radionuclide. A step of separating the dummy targets (18) from the activated irradiation targets (16) includes exposing the dummy targets (18) and/or the activated irradiation targets (16) to a magnetic field to retain either the dummy targets (18) or the activated irradiation targets (16) in the instrumentation tube system (12) and release the other one of the activated irradiation target (16) or the dummy target (18) from the instrumentation tube system (12). An apparatus adapted to the above method is also provided.
G21G 1/02 - Dispositions pour la conversion des éléments chimiques par rayonnement électromagnétique, radiations corpusculaires ou bombardement par des particules, p.ex. production d'isotopes radioactifs dans les réacteurs nucléaires
9.
INTERNAL MANIPULATOR FOR TRAVERSING PIPE SYSTEMS, IN PARTICULAR BRANCH LINES IN PIPE SYSTEMS
The invention relates to an internal manipulator (1) for traversing pipe systems (2), in particular branch lines (3) in pipe systems (2), comprising a crawling system (4) with at least two crawling elements (4a; 4b; 4c). Adjacent crawling elements (4a; 4b; 4c) are connected by at least two bellows (5a; 5b; 5c; 5d). Each of at least two crawling elements (4a; 4b; 4c) has a fixing device (6) for fixing the crawling element (4a; 4b; 4c) in the pipe (7). The invention is characterized in that the bellows (5a; 5b; 5c; 5d) are designed to be expandable and/or compressible independently of each other such that the internal manipulator (1) can bend into branch lines (3), whereby at least one of the bellows (5a; 5b; 5c; 5d) is compressed and at least another of the bellows (5a; 5b; 5c; 5d) is expanded.
The invention relates to a device (2) for checking a fuel rod (4) of a fuel element in a water-filled basin (6) of a submerged nuclear plant, comprising a testing container (8) having a first chamber (10) and a second chamber (12), a first checking device (14) arranged in the testing container (8), wherein the testing container (8) has at least one inlet opening (16a, b) and at least one outlet opening (18a, b), and wherein the testing container (8) comprises an insertion opening (20a) for inserting the fuel rod (4) into the second chamber (12), and wherein a valve (24) is arranged in a connecting channel (22) connecting the first and the second chamber (10, 12). The invention further relates to a method for checking a fuel rod (4) in a water-filled basin (6) of a submerged nuclear plant having such a device (2), wherein the fuel rod (4) is inserted into the second chamber (12) of the testing container (8) through the insertion opening (20a) while the valve (24) is closed, wherein a fluid is fed in via the at least one inlet opening (16a, b), and wherein the valve (24) is opened in order to check the fuel rod (4) with the first checking device (14).
G21C 17/06 - Dispositifs ou dispositions pour la surveillance ou le test du combustible ou des éléments combustibles en dehors du cœur du réacteur, p.ex. pour la consommation ou pour la contamination
An irradiation target processing system (22) for insertion and retrieving irradiation targets (16) into and from an instrumentation tube (14) in a nuclear reactor core (10) comprises a target retrieving system (38) comprising a target exit port (40) configured to be coupled to a target storage container (42) and an exhaust system (44); a target insertion system (46) comprising a target filling device (84), a target retention tubing (86) and a target diverter (88) coupled to the target filling device (84), the target retention tubing (86) and the target retrieving system (38), and further comprising a target supply junction (96) at the target retention tubing (86), wherein the target supply junction (96) is configured to be connected to the instrumentation tube (14); and a transport gas supply system (48) comprising a first gas supply tubing (102), a second gas supply tubing (104) and a transport gas supply junction (106) coupled to the first and second gas supply tubing (102, 104), wherein the first gas supply tubing (102) is coupled to the exit port (40) of the target retrieving system (38) and the second gas supply tubing (104) is configured to be coupled to a junction (108) for supplying gas to the instrumentation tube (14). The target retrieving system (38), the target insertion system (46) and the transport gas supply system (48) are mounted on a movable support (52).
G21G 1/02 - Dispositions pour la conversion des éléments chimiques par rayonnement électromagnétique, radiations corpusculaires ou bombardement par des particules, p.ex. production d'isotopes radioactifs dans les réacteurs nucléaires
G21C 23/00 - Dispositions dans les réacteurs pour faciliter les expériences ou l'irradiation
A radionuclide generation system comprises a tube system configured to permit insertion and removal of irradiation targets into an instrumentation finger of a nuclear reactor, and an irradiation target drive system configured to insert the irradiation targets into the instrumentation finger and to remove the irradiation targets from the instrumentation finger. The radionuclide generation system further comprises an instrumentation and control unit which is linked to an online core monitoring system and being configured to calculate an optimum irradiation time for the irradiation targets based on the actual state of the reactor as provided by the online core monitoring system.
G21G 1/02 - Dispositions pour la conversion des éléments chimiques par rayonnement électromagnétique, radiations corpusculaires ou bombardement par des particules, p.ex. production d'isotopes radioactifs dans les réacteurs nucléaires
13.
METHOD OF DECONTAMINATING METAL SURFACES IN A COOLING SYSTEM OF A NUCLEAR REACTOR
A method of decontaminating metal surfaces in a cooling system of a nuclear reactor comprises conducting a plurality of treatment cycles, with each of the treatment cycles comprising: an oxidation step wherein metal oxides including radioisotopes on the metal surfaces are contacted with an aqueous solution of a permanganate oxidant; a decontamination step after the oxidation step wherein the metal oxides are contacted with an aqueous solution of an organic acid selected from the group consisting of oxalic acid, formic acid, citric acid, tartaric acid, picolinic acid, gluconic acid, glyoxylic acid and mixtures thereof so as to dissolve at least part of the metal oxides and the radioisotopes; and a cleaning step wherein at least the radioisotopes are immobilized on an ion exchange resin; wherein the oxidation step comprises at least one acidic oxidation step and at least one alkaline oxidation step carried out one after another in either the same or different treatment cycles; and wherein the plurality of treatment cycles comprises at least one treatment cycle including a high temperature oxidation step, wherein the permanganate oxidant solution is kept at a temperature of at least 100 °C and, wherein the at least one reactor coolant pump is used to circulate and heat the oxidation solution inside the primary loop, and the residual heat removal system is used to control the temperature of the oxidant solution during the high temperature oxidation step.
G21F 9/00 - Traitement des matériaux contaminés par la radioactivité; Dispositions à cet effet pour la décontamination
G21C 17/022 - Dispositifs ou dispositions pour la surveillance du réfrigérant ou du modérateur pour la surveillance de réfrigérants ou de modérateurs liquides
G21C 19/28 - Dispositions pour introduire un matériau fluent à l'intérieur du cœur du réacteur; Dispositions pour enlever un matériau fluent du cœur du réacteur
The invention provides a method of preparing irradiation targets for radioisotope production in instrumentation tubes of a nuclear power reactor, the method comprising the steps of: providing a powder of an oxide of a rare earth metal having a purity of greater than 99 %; consolidating the powder in a mold to form a round green body having a green density of at least 50 percent of the theoretical density; and sintering the spherical green body in solid phase at a temperature of at least 70 percent of a solidus temperature of the rare earth metal oxide powder and for a time sufficient to form a round sintered rare earth metal oxide target having a sintered density of at least 80 percent of the theoretical density.
G21G 1/02 - Dispositions pour la conversion des éléments chimiques par rayonnement électromagnétique, radiations corpusculaires ou bombardement par des particules, p.ex. production d'isotopes radioactifs dans les réacteurs nucléaires
H05H 6/00 - Cibles pour la production de réactions nucléaires
15.
METHOD OF PREPARING IRRADIATION TARGETS FOR RADIOISOTOPE PRODUCTION AND IRRADIATION TARGET
The invention provides a method of preparing irradiation targets for radioisotope production in instrumentation tubes of a nuclear power reactor, the method comprising the steps of: providing a powder consisting of an oxide of a rare earth metal having a purity of greater than 99 % and, optionally, an organic binder; pelletizing the powder and optionally the organic binder to form a substantially spherical green body having a diameter of from between 1 to 10 mm; and sintering the spherical green body in solid phase at a temperature of at least 70 percent of a solidus temperature of the rare earth metal oxide powder and for a time sufficient to form a round sintered rare earth metal oxide target having a sintered density of at least 80 percent of the theoretical density.
G21G 1/02 - Dispositions pour la conversion des éléments chimiques par rayonnement électromagnétique, radiations corpusculaires ou bombardement par des particules, p.ex. production d'isotopes radioactifs dans les réacteurs nucléaires
H05H 6/00 - Cibles pour la production de réactions nucléaires
16.
IRRADIATION TARGET FOR RADIOISOTOPE PRODUCTION, METHOD FOR PREPARING AND USE OF THE IRRADIATION TARGET
The invention provides a sintered rare earth metal oxide target for producing a radioisotope in an instrumentation tube of a nuclear power reactor, wherein the sintered target has a density of at least 90 percent of the theoretical density, and wherein the sintered target contains chromium in an amount of from 500 to 2000 µg/g, and Mg and/or Ca in an amount of from 1000 to 6000 µg/g. The sintered target is prepared by providing a rare earth metal oxide powder, blending the rare earth metal oxide powder with chromium oxide, dry granulating and consolidating the powder in a mold to form a spheroidal green body, and sintering the green body in solid phase to form a spheroidal ytterbia target.
G21G 1/02 - Dispositions pour la conversion des éléments chimiques par rayonnement électromagnétique, radiations corpusculaires ou bombardement par des particules, p.ex. production d'isotopes radioactifs dans les réacteurs nucléaires
H05H 6/00 - Cibles pour la production de réactions nucléaires
17.
VENTILATION SYSTEM AND ASSOCIATED OPERATING METHOD FOR USE DURING A SERIOUS INCIDENT IN A NUCLEAR PLANT
A ventilation system (2) for an operating room accessible to service personnel in a nuclear plant, in particular a control room (4) in a nuclear power plant (6), is intended to enable a supply of decontaminated fresh air at least for a time span of a few hours in the event of serious incidents involving the release of radioactive activity. In particular, the content of radioactive inert gases in the fresh air supplied to the operating room should be as low as possible. According to the invention, the ventilation system (2) is equipped with an air supply line (10) guided from an external inlet (14) to the operating room, with a first fan (12) and a first inert gas adsorber column (e.g. 38) being connected to said air supply line (10), an air discharge line (44) guided from the operating room to an external outlet (72), with a second fan (46) and a second inert gas adsorber column (e.g. 48) being connected to said air discharge line (44), and switchover means for interchanging the roles of the first and second inert gas adsorber columns (38, 48).
G21C 19/00 - Dispositions pour le traitement, pour la manipulation, ou pour faciliter la manipulation, du combustible ou d'autres matériaux utilisés à l'intérieur du réacteur, p.ex. à l'intérieur de l'enceinte sous pression
18.
DEVICE AND METHOD FOR PERFORMING A LEAK TEST ON FUEL ROD CAPSULES
The invention relates to a device (1) for performing a leak test on a fuel rod capsule (3), which contains at least one fuel rod (2) and test gas (P), which device (1) comprises a test container (4), which is designed to accommodate at least one fuel rod capsule (3) and can be lowered into a pool (5) of a nuclear plant flooded with water. According to the invention, a mass spectrometer (14) is fluidically connected to the interior of the test container (4) in such a way that a gas flow can be fed to the mass spectrometer (14) in order to sense the concentration of the test gas (P) that has diffused into the test container (4) from the fuel rod capsule (3).
G01M 3/20 - Examen de l'étanchéité des structures ou ouvrages vis-à-vis d'un fluide par utilisation d'un fluide ou en faisant le vide par détection de la présence du fluide à l'emplacement de la fuite en utilisant des révélateurs particuliers, p.ex. teinture, produits fluorescents, produits radioactifs
G21C 19/07 - Râteliers de stockage; Piscines de stockage
19.
SHOCK ABSORBER FOR TRANSPORT CONTAINERS AND/OR STORAGE CONTAINERS FOR FUEL ELEMENTS AND/OR FUEL-CONTAINING VESSELS, FUEL ELEMENT AND/OR FUEL-CONTAINING VESSEL, AND TRANSPORT CONTAINERS AND/OR STORAGE CONTAINERS FOR FUEL ELEMENTS AND/OR FUEL-CONTAINING VESSELS
The invention relates to a shock absorber (10) for transport containers and/or storage containers for fuel elements and/or fuel-containing vessels, wherein the shock absorber (10) has a plastically deformable elongate hollow body (11). The invention is characterized in that the hollow body (11) has at least one first region (12) provided for the plastic deformation in the event of shock loading and at least one second region (13) that remains dimensionally stable in the event of shock loading. The invention further relates to a fuel element and/or to a fuel-containing vessel (20) having at least one such shock absorber (10) and to a transport container and/or storage container (30) for fuel elements and/or for fuel-containing vessels (20) having at least one such shock absorber (10).
The invention relates to a test device for the non-destructive testing of a component of an anti-friction bearing (2) having a plurality of rolling elements (6) that roll in a rolling element receiving chamber. The device has a sensor holder (10) comprising at least one sensor (14) for testing the component, which holder can be arranged in a region between neighbouring rolling elements (6). According to the invention, a retaining device (62) for guiding a connecting cable (25) can be at least indirectly connected to the anti-friction bearing (6) in such a way that the connecting cable (25) guided in the retaining device (62) can be connected to the sensor holder (10) in order to test the component.
A process for the recovery of a radioisotope from a waste resin of a nuclear power plant comprises the steps of: a) treating a waste resin loaded with at least one radioisotope with an organic acid or alkaline compound to release the at least one radioisotope and to obtain a process solution containing the at least one radioisotope; b) separating the at least one radioisotope from the process solution through a reaction specific to the radioisotope so as to obtain a treated process solution depleted of the at least one radioisotope, wherein said depleted process solution comprises the organic acid or alkaline compound and optionally a non-reacted radioisotope; c) reacting the organic acid or alkaline compound in the depleted process solution from step b) by thermal and/or photochemical oxidation to form gaseous reaction products; and d) reloading the waste resin with the reacted process solution from step c) to bind the non-reacted radioisotope on the waste resin. Further, an apparatus is provided to carry out the above method.
An ultrasonic test head (1) for the non-destructive materials testing of a component (7) has an ultrasonic transducer arrangement (2) which is designed to be coupled to the component (7) and comprises a multiplicity of individual transducers (3) arranged at a distance from one another in a two-dimensional array (4); at least one of the individual transducers (3) in the array (4) is arranged at a predefinable acute angle (13) with respect to a supporting surface (8) of the array (4) such that the sound waves which can be emitted by the at least one individual transducer (3) can be coupled in in a preferred direction (11), which differs from a surface normal (12) running perpendicular to the coupling surface (8), when the ultrasonic test head (1) is placed onto the component (7).
G01N 29/22 - Recherche ou analyse des matériaux par l'emploi d'ondes ultrasonores, sonores ou infrasonores; Visualisation de l'intérieur d'objets par transmission d'ondes ultrasonores ou sonores à travers l'objet - Détails
G01N 29/26 - Dispositions pour l'orientation ou le balayage
23.
A METHOD FOR THE MANUFACTURE OF POWDER-FILLED SHAPED BODIES, SHAPED BODIES FOR INTRODUCTION INTO A COMMERCIAL NUCLEAR POWER REACTOR AND THE USE THEREOF
To manufacture shaped bodies (10) filled with powder (22) for introduction into the reactor core of a commercial nuclear power reactor a plate made of a metal and/or metalloid is provided with one or more blind holes (14), the blind holes (14) are filled with powder (22), the blind holes (14) filled with powder (22) are reversibly sealed and shaped bodies are cut from the plate so that each blind hole (14) filled with powder (22) is surrounded by a shell made of a metal or metalloid. The powder-filled shaped bodies (10) are used in a ball measuring system for commercial nuclear power reactors and/or for the generation of radionuclides in said reactors.
G21G 1/02 - Dispositions pour la conversion des éléments chimiques par rayonnement électromagnétique, radiations corpusculaires ou bombardement par des particules, p.ex. production d'isotopes radioactifs dans les réacteurs nucléaires
G21G 4/06 - Sources radioactives autres que les sources de neutrons caractérisées par des aspects de leur structure
24.
COOLING ELEMENT FOR COOLING THE COOLANT IN A FUEL ELEMENT POND, ASSOCIATED SYSTEM, FUEL ELEMENT POND AND NUCLEAR FACILITY
A cooling element (2) for cooling the coolant in a fuel element pond (115) in which a fuel element frame (92) is arranged for receiving fuel elements (98), wherein the cooling element (2) comprises a heat exchanger (64) which is designed for connection to a cooling circuit (120), and the cooling element should be integrated in a space-saving way in an already present fuel element pond (115). According to the invention, the cooling element (2) is dimensioned and configured in such a way that it can be arranged and/or fixed in an unoccupied position (106) for a fuel element (98) in the fuel element frame (92).
The invention relates to a passive two-phase cooling circuit (2) with an evaporator (6) and a condenser (18) for a coolant which is conducted in the cooling circuit (2). An evaporator supply line (4) and an evaporator discharge line (10) are connected to the evaporator (6), and a condenser supply line (16) and a condenser discharge line (22) are connected to the condenser (18). Such a cooling circuit is to be developed such that pressure peaks are reduced or even completely prevented during operation while keeping the system design simple and inexpensive. According to the invention, this is achieved in that the evaporator supply line (4), the evaporator discharge line (10), the condenser supply line (16), and the condenser discharge line (22) are connected to a common damping container (24). A liquid column (52) is formed in the condenser discharge line (22) during the operation of the cooling circuit (2), said liquid column assuming the function of a liquid seal (50) and the function of a fluid-dynamic vibration damper.
F25B 23/00 - Machines, installations ou systèmes ayant un seul principe de fonctionnement non compris dans les groupes , p.ex. utilisant l'effet de radiation sélective
The invention relates to a method for testing a workpiece (10) using ultrasound, wherein an ultrasonic probe (2, 12) generates an ultrasound signal (4) which has a central beam (Z) and which is coupled into the workpiece (10) under test, and the central beam (Z) is guided along a predefined path (18) on the surface (20) of the workpiece (10), the central beam (Z) and the workpiece (10) being moved in opposite directions at least along a portion of the path (18).
G01N 29/27 - Dispositions pour l'orientation ou le balayage en déplaçant le matériau par rapport à un capteur fixe
G01N 29/275 - Dispositions pour l'orientation ou le balayage en déplaçant à la fois le capteur et le matériau
G01N 29/28 - Recherche ou analyse des matériaux par l'emploi d'ondes ultrasonores, sonores ou infrasonores; Visualisation de l'intérieur d'objets par transmission d'ondes ultrasonores ou sonores à travers l'objet - Détails pour établir le couplage acoustique
27.
METHOD FOR OXIDATIVE BREAKDOWN OF NITROGENOUS COMPOUNDS IN WASTE WATER
The invention relates to a method for oxidative breakdown of nitrogenous compounds in waste water by means of an electrochemical treatment using a diamond electrode as an anode (A) and a cathode (K) as a counter-electrode, wherein the destruction of the nitrogenous compounds and a reduction of the total nitrogen content can be achieved in a common method in that, in a first method step, a first current density is adjusted on the anode (A) in order to oxidize the nitrogenous compounds and subsequently, by means of a second current density which is smaller than the first current density, the dissolved total nitrogen content is reduced by releasing molecular nitrogen.
C02F 1/461 - Traitement de l'eau, des eaux résiduaires ou des eaux d'égout par des procédés électrochimiques par électrolyse
C02F 1/467 - Traitement de l'eau, des eaux résiduaires ou des eaux d'égout par des procédés électrochimiques par électrolyse par désinfection électrochimique
C02F 101/38 - Composés organiques contenant de l'azote
C02F 103/34 - Nature de l'eau, des eaux résiduaires ou des eaux ou boues d'égout à traiter provenant de l'industrie chimique non prévue dans les groupes
The invention relates to a method for testing a workpiece (2) using ultrasound in a curved region (6) of the surface (4) of said workpiece, having the following steps: (a) a plurality of ultrasonic signals (14a, b) are emitted from a plurality of transmitting positions (Pa-f) at different pivot angles (Sa, b) in a pivoting range (16a, b) with the aid of at least one ultrasonic transducer (10a-f) and are injected into the workpiece (2), (b) a corresponding ultrasonic echo signal (18a, b) is received for each ultrasonic signal (14a, b), and the amplitude of the ultrasonic echo (E) produced upon entering the workpiece (2) or on the rear wall of the workpiece (2) is determined, (c) the ultrasonic echoes (E) having amplitudes representing local maxima are determined for each transmitting position (Pa-f), (d1) if an individual ultrasonic echo (E) having an amplitude representing a local maximum was determined for a transmitting position (Pa-f) in step (c), the associated ultrasonic echo signal (18a, b) of said echo is selected, (d2) if a plurality of ultrasonic echoes (E) having an amplitude representing a local maximum were determined for a transmitting position (Pa-f) in step (c) or if this is predefined for a transmitting position (Pa-f), ultrasonic echo signals (18a, b) are selected if only an individual ultrasonic echo (E) having an amplitude representing a local maximum was determined for an adjacent transmitting position (Pa-f) in step (c) by selecting those ultrasonic echo signals (18a, b) which are in a particular angle range (24) around the corresponding pivot angle (Sa,b) of the ultrasonic echo signal (18a, b) having the maximum amplitude of the ultrasonic echo (E) of the adjacent transmitting position (Pa-f) and which have an ultrasonic echo (E) having a maximum amplitude, (e) at least the selected ultrasonic echo signals (18a, b) are evaluated.
The invention relates to a leak-monitoring system (2) for space-enclosing objects such as pipes (4), hoses or containers that have a surrounding wall (6), and comprising at least one electrically-conductive element that acts as a leak sensor (8) and is mounted on or integrated into said surrounding wall (6). According to the invention, in order to allow simple and reliable monitoring of imminent or existing leaks even for large wall areas, and as universally as possible for different types of medium, said electrically-conductive element is a component of a measurement bridge (12) that comprises an evaluation device for (20) for the bridge voltage (VMess) and that is supplied, by a voltage source (18), with an operating voltage (UG) having both alternating voltage components and direct voltage components.
G01M 3/18 - Examen de l'étanchéité des structures ou ouvrages vis-à-vis d'un fluide par utilisation d'un fluide ou en faisant le vide par détection de la présence du fluide à l'emplacement de la fuite en utilisant des moyens de détection électrique pour soupapes
G01M 5/00 - Examen de l'élasticité des structures ou ouvrages, p.ex. fléchissement de ponts ou d'ailes d'avions
30.
TRANSMISSION SYSTEM FOR A NUCLEAR POWER PLANT AND ASSOCIATED METHOD
Signal transmission system for a technical installation having a region exposed to radiation, in particular for a nuclear power plant (2) having a containment (6), wherein • a modulator (26) for converting an analogue measured value (K), which is provided by an associated sensor (8), into a PWM signal (D) is arranged inside the region exposed to radiation, • a demodulator (38) for reconstructing the measured value (K) from the PWM signal (D) is arranged outside the region exposed to radiation, • the modulator (26) is implemented using radiation-hardened circuit technology, preferably analogue circuit technology, and comprises an adaptable measured value normalization means (18), a sawtooth generator (14) and a comparator (16), and • the demodulator (38) is connected to the modulator (26) via a signal transmission line (34) DC-isolated from the output of the comparator (16).
H04Q 9/00 - Dispositions dans les systèmes de commande à distance ou de télémétrie pour appeler sélectivement une sous-station à partir d'une station principale, sous-station dans laquelle un appareil recherché est choisi pour appliquer un signal de commande ou
G08C 15/00 - Dispositions caractérisées par l'utilisation du multiplexage pour la transmission de plusieurs signaux par une voie commune
G08C 15/06 - Dispositions caractérisées par l'utilisation du multiplexage pour la transmission de plusieurs signaux par une voie commune successivement, c. à d. utilisant la division de temps
G01D 21/02 - Mesure de plusieurs variables par des moyens non couverts par une seule autre sous-classe
Main claim: reactor pressure vessel (2) comprising a vessel pot (6) and a cover (4), wherein • the cover (4) includes at least one drive housing (12) for a control element drive (10), • the vessel pot (6) has a core frame (8) for accommodating control elements, • a position indicator (16), which, in the final mounted state, is inserted into a drive rod (14) of an associated control element, is mounted inside the drive housing (12), and • a centering device (20), which helps insert the position indicator (16) into the drive rod (14) when the cover (4) is mounted on the vessel pot (6), is fastened to the core frame (8).
G21C 7/12 - Moyens pour amener les éléments de commande dans la position désirée
G21C 17/12 - Combinaison structurelle de l'élément combustible, de la barre de commande, du cœur du réacteur, ou de la structure du modérateur avec des instruments sensibles, p.ex. pour la mesure de la radioactivité, des contraintes l'élément sensible faisant partie de l'élément de commande
G21C 19/20 - Dispositions pour introduire des objets à l'intérieur de l'enceinte sous pression; Dispositions pour manipuler des objets à l'intérieur de l'enceinte sous pression; Dispositions pour extraire des objets de l'enceinte sous pression
G21C 13/073 - Obturateurs pour enceintes de réacteurs, p.ex. rotatifs
G21C 19/10 - Dispositifs de relèvement ou d'enlèvement adaptés pour coopérer avec les éléments combustibles ou avec l'élément de commande
32.
DEVICE FOR REPAIRING DAMAGE TO THE BOTTOM OF A CONTAINER FILLED WITH WATER
The invention relates to a device (16) for repairing damage to a bottom (8) of a container (2) filled with water (10), which bottom is formed by a plurality of bottom elements (12), said device comprising a guiding device (22), which can be placed on the bottom (8) of the container (2) and which has a centering device (26) for centering the guiding device (22) between wall sections (14) of the bottom elements (12) and a fixing device (38) for fixing the guiding device (22) on the bottom (8) of the container (2), a carrier (40), which can be guided along the guiding device (22) and on which at least one pivot arm (42) is arranged in such a way that the at least one pivot arm can be pivoted between a transport position oriented perpendicularly to the plane of the bottom (8) and a working position extending parallel to the plane of the bottom (8), an accommodating element (48) arranged at a free end (44) of the pivot arm (42), for accommodating adhesive (50), with which part of a wall section (14) of the bottom elements (12) can be covered.
The invention relates to a hose (2) or tube for transporting a gas specimen, having • · an inner envelope (4), forming a diffusion barrier and comprising a plurality of perforation holes (6), and • · an outer envelope (8), forming a diffusion layer and resting on the inner envelope (4). The object of the invention is to develop a hose (2) or tube of this type so as to ensure transport of a gas specimen over as great a distance as possible without substantial weakening of the concentration, and at the same time without impairing the ability of the gas to be detected to diffuse into the hose (2) or tube. For this purpose, it is provided according to the invention that the outer envelope (8) comprises diffusion-inhibiting sealing zones (20) on its inner surface (18), which zones overlap the perforation holes (6) in the inner envelope (4). When there is a sufficiently high concentration in the surroundings, gas molecules diffuse into the diffusion layer from the outside and thereby cause the outer envelope to swell. This causes the outer envelope, which usually rests on the inner envelope, to lift off the inner envelope, even in the region of the sealing zones. The gas molecules can flow through the diffusion layer of the outer envelope, the temporary gap formed between the outer envelope and the inner envelope and through the perforation holes, thus bypassing the sealing zones.
F17D 5/02 - Prévention, interception ou localisation des pertes
G01M 3/04 - Examen de l'étanchéité des structures ou ouvrages vis-à-vis d'un fluide par utilisation d'un fluide ou en faisant le vide par détection de la présence du fluide à l'emplacement de la fuite
G01M 3/22 - Examen de l'étanchéité des structures ou ouvrages vis-à-vis d'un fluide par utilisation d'un fluide ou en faisant le vide par détection de la présence du fluide à l'emplacement de la fuite en utilisant des révélateurs particuliers, p.ex. teinture, produits fluorescents, produits radioactifs pour soupapes
G01N 1/10 - Dispositifs pour prélever des échantillons à l'état liquide ou fluide
34.
CONNECTING ASSEMBLY OF A CENTERING PIN ON A CORE GRATE AND METHOD FOR CONNECTING A CENTERING PIN TO A CORE GRATE
The invention relates to a connecting assembly of a centering pin (10) on a core grate (3) of the reactor pressure vessel (1) of a pressurized-water reactor, which centering pin is used to center a fuel element (2), wherein the centering pin (10) is retained in an accommodating bore (16) of a plate (4) present on the core grate (3), with an expanded projection (19) protruding from the accommodating bore (16), in such a way that a form closure is formed. In a pre-assembly state, in which said form closure does not yet exist, the fixing segment (18) is a hollow cylinder, which has, over the entire length of the hollow cylinder, an outer circumferential surface (27) that extends on the lateral surface of a circular cylinder having uniform outside diameter (26). In a final assembly state, the projection (19) is expanded as a consequence of an expansion by means of an expanding tool in such a way that said form closure is formed.
B21D 39/06 - Utilisation de procédés permettant d'assembler des objets ou des parties d'objets, p.ex. revêtement par des tôles, autrement que par placage; Dispositifs de mandrinage des tubes des tubes dans des ouvertures
F16B 19/10 - Rivets creux; Rivets en plusieurs morceaux fixés par action mécanique
G21C 5/06 - Moyens pour placer ou pour supporter les éléments combustibles
G21C 19/19 - Parties de réacteurs spécifiquement adaptées pour faciliter la manipulation, p.ex. pour faciliter le chargement ou le déchargement des éléments combustibles
35.
METHOD FOR QUANTITATIVE ANALYSIS OF THE COMPOSITION OF A GAS MIXTURE AND ASSOCIATED MEASURING DEVICE
The invention relates to a method for quantitative analysis of the composition of a gas mixture, in particular of the atmosphere of a containment (4) of a nuclear plant. The method is intended to make it possible to easily and reliably determine, in as direct a manner as possible, even under difficult conditions, physical parameters which characterize the ignition field and the combustion behaviour of the gas mixture. For this purpose, a measuring device (2) is provided according to the invention which comprises • a thermal conductivity detector (16) having a first measuring bridge, • a reaction heat detector (14) having a second measuring bridge, and • a common evaluation unit (26), wherein the hydrogen (H2) content and at the same time the oxygen (O2) content are determined in the evaluation unit (26) based on the bridge voltages present at the two measuring bridges.
G01N 25/18 - Recherche ou analyse des matériaux par l'utilisation de moyens thermiques en recherchant la conductivité thermique
G01N 27/16 - Recherche ou analyse des matériaux par l'emploi de moyens électriques, électrochimiques ou magnétiques en recherchant l'impédance en recherchant la résistance d'un corps chauffé électriquement dépendant de variations de température produite par l'oxydation par combustion ou catalyse d'un matériau de l'espace environnant à tester, p.ex. d'un gaz
G01N 33/00 - Recherche ou analyse des matériaux par des méthodes spécifiques non couvertes par les groupes
36.
METHOD FOR REDUCING THE RADIOACTIVE CONTAMINATION OF THE SURFACE OF A COMPONENT USED IN A NUCLEAR REACTOR
The invention relates to a method for reducing the radioactive contamination of the surface of a component used in a nuclear reactor, which component is in contact with radioactively contaminated water, in which method a hydrophobic film is produced on the surface of a component by virtue of the surface being wetted with an aqueous solution which contains a film-forming amphiphilic substance.
G21F 9/00 - Traitement des matériaux contaminés par la radioactivité; Dispositions à cet effet pour la décontamination
G21C 17/022 - Dispositifs ou dispositions pour la surveillance du réfrigérant ou du modérateur pour la surveillance de réfrigérants ou de modérateurs liquides
G21C 19/28 - Dispositions pour introduire un matériau fluent à l'intérieur du cœur du réacteur; Dispositions pour enlever un matériau fluent du cœur du réacteur
The invention relates to a method and a device for repairing damage to a container wall located under water. A repair device (2) for repairing the damage to a container wall (4) located under water has a carrier (6) and the following design: - the carrier (6) has means for fastening the carrier to the container wall (4), - a repair die (10) is arranged on the carrier (6), which repair die has at least one injection opening (12) and at least one outlet opening (13) and can be pressed against the container wall (4) in a remotely controlled manner in order to cover the damage to the container wall (4) and to seal off a chamber (14) formed by the repair die (10) and the container wall (4), - a reservoir (17) for an adhesive (18) is arranged on the carrier (6), - a remotely controllable injection device (20) is arranged on the carrier (6), which remotely controllable injection device is provided in order to inject adhesive (18) from the reservoir (17) into the injection opening (12) of the repair die (10) so that the chamber (14) formed by the repair die (10) and the container wall (4) is filled by means of the adhesive (18).
G21C 19/20 - Dispositions pour introduire des objets à l'intérieur de l'enceinte sous pression; Dispositions pour manipuler des objets à l'intérieur de l'enceinte sous pression; Dispositions pour extraire des objets de l'enceinte sous pression
38.
VENTILATION SYSTEM AND ASSOCIATED OPERATING METHOD FOR USE DURING A SERIOUS INCIDENT IN A NUCLEAR PLANT
A ventilation system (2) for an operating room accessible to service personnel in a nuclear plant, in particular a control room (4) in a nuclear power plant (6), is intended to enable a supply of decontaminated fresh air at least for a time span of a few hours in the event of serious incidents involving the release of radioactive activity. In particular, the content of radioactive inert gases in the fresh air supplied to the operating room should be as low as possible. For this purpose, in accordance with the invention the ventilation system (2) is equipped with • an air supply line (10) passed from an external inlet (14) to the operating room, with a first fan (12) and a first inert gas adsorber column (e.g. 38) being connected into said air supply line (10), • an air discharge line (44) passed from the operating room to an external outlet (72), with a second fan (46) and a second inert gas adsorber column (e.g. 48) being connected into said air discharge line (44), and • switchover means for interchanging the roles of the first and second inert gas adsorber columns (38, 48).
G21C 9/00 - Dispositions pour la protection d'urgence structurellement associées avec le réacteur
G21C 9/06 - Moyens de prévention de l'accumulation de gaz explosifs, p.ex. recombinateurs
G21C 13/02 - Enceintes sous pression; Enceintes d'enveloppe; Enveloppes en général - Détails
G21C 19/30 - Dispositions pour introduire un matériau fluent à l'intérieur du cœur du réacteur; Dispositions pour enlever un matériau fluent du cœur du réacteur avec purification continue du matériau fluent en circulation, p.ex. par extraction des produits de fission
G21D 3/06 - Dispositions de sécurité réagissant à des défaillances à l'intérieur de l'installation
G21F 7/015 - Dispositifs de commande de l'atmosphère dans la chambre, de la température ou de la pression
39.
INSPECTING DEVICE FOR NONDESTRUCTIVELY INSPECTING A COMPONENT OF A ROLLING-ELEMENT BEARING, ROLLING-ELEMENT BEARING, AND WIND TURBINE
The invention relates to an inspecting device for nondestructively inspecting a component of a rolling-element bearing (2) having a plurality of rolling elements (6), comprising a sensor retainer (10), which comprises at least one sensor (14) for inspecting the component and which can be inserted into a region (8) between adjacent rolling elements (6) and which is carried along in the inserted state during a rolling motion of one of the rolling elements (6), wherein the at least one sensor (14) can be coupled to the component in order to inspect the component. The invention further relates to a rolling-element bearing having such an inspecting device and to a wind turbine, comprising a rotor supported in a rolling-element bearing and comprising such an inspecting device.
The invention relates to a device and a method for the non-destructive testing of a component of a rolling bearing (2), said bearing comprising a plurality of rolling elements (6). According to the invention, the component is laterally accessible in the assembled state of the rolling bearing (2) in an area (10) located between two adjacent rolling elements (6) and the device comprises a testing device (14) which can be guided laterally into the rolling bearing (2) and seated against the component, said testing device comprising at least one sensor (16) for testing the component.
The present invention is based on the object of specifying a sensor carrier (2) and an associated apparatus for measuring the filling level (4) which, with a structure which is kept simple and cost-effective, have high radiation resistance and low sensitivity to vibrations in the form of earthquake shocks and the like. For this purpose, the invention provides a sensor carrier (2) which is designed to be mounted, at the upper end thereof, in a manner suspended from an associated carrier (66) or suspension point in a vertical orientation and has a plurality of carrier elements (14) which each carry at least one sensor (10) and are flexibly connected to one another via connecting elements (22) in such a manner that each carrier element (14) can be deflected from the position of rest in at least one spatial direction in the event of vibrations in the form of earthquake shocks or the like.
G01F 23/24 - Indication ou mesure du niveau des liquides ou des matériaux solides fluents, p.ex. indication en fonction du volume ou indication au moyen d'un signal d'alarme en mesurant des variables physiques autres que les dimensions linéaires, la pression ou le poids, selon le niveau à mesurer, p.ex. par la différence de transfert de chaleur de vapeur ou d'eau en mesurant les variations de résistance de résistances électriques produites par contact avec des fluides conducteurs
G01F 23/26 - Indication ou mesure du niveau des liquides ou des matériaux solides fluents, p.ex. indication en fonction du volume ou indication au moyen d'un signal d'alarme en mesurant des variables physiques autres que les dimensions linéaires, la pression ou le poids, selon le niveau à mesurer, p.ex. par la différence de transfert de chaleur de vapeur ou d'eau en mesurant les variations de capacité ou l'inductance de condensateurs ou de bobines produites par la présence d'un liquide ou d'un matériau solide fluent dans des champs électriques ou électromagnétiques
G01F 23/00 - Indication ou mesure du niveau des liquides ou des matériaux solides fluents, p.ex. indication en fonction du volume ou indication au moyen d'un signal d'alarme
42.
PRESSURE-RELIEF AND ACTIVITY-RESTRAINT SYSTEM FOR A NUCLEAR PLANT
The invention relates to a pressure-relief and activity-restraint system (2) for a nuclear plant (6), particularly a nuclear power plant, having a containment (4) enclosed by a containment shell (8), to which containment a pressure-relief line (10) for relieving pressure in the event of malfunctions or accidents is connected. The following components are connected in series in the pressure-relief line (10), as viewed in the flow direction of the pressure-relief flow: a catalytic recombiner (14) for reacting hydrogen contained in the pressure-relief flow with oxygen in order to produce water vapour; a wet scrubber (24), or alternatively a dry filter (100, for separating out aerosols from the pressure relief flow; and a line section having at least two parallel line portions, each comprising an adsorber column (44) for retaining noble gases contained in the pressure-relief flow. In addition, a flushing and feedback system (56) is connected to the adsorber columns (44), and at least one of the adsorber columns (44) can be decoupled from the pressure-relief flow by means of associated valves (46, 48, 84, 86) and shifted to a flushing operation mode, in which noble gases collected in said absorber column (44) are flushed back into the containment (4) with the assistance of a flushing agent. The flushing and feedback system (56) is designed as a passive system, which is driven by the heat of decay contained in the containment (4) or the pressure-relief flow.
The invention relates to an emission monitoring system (2) for a venting system (16) of a nuclear power plant (4), which is configured for a particularly low consumption of electrical energy while having high reliability, availability and quality of the measurement results. For this purpose, the emission monitoring system (2) is, according to the invention, equipped with a pressure relief line (8), which is connected to a containment (6) of the nuclear power plant (4) and comprises a high-pressure section (74) and a low-pressure section (76), a sampling line (22), which, on the inlet side, opens into the low-pressure section (76) of the pressure relief line (8) and is guided from there to a functional path (20, 46) through which a sample flow can flow, an ejector (78) comprising a pump fluid connector (82), a suction connector (86) and an outlet connector (88), a pump fluid feed line (80) which, on the inlet side, opens into the high-pressure section (74) of the pressure relief line (8) and is guided from there to the ejector (78) and connected to the pump fluid connector (82), and a sample return line (56), which is guided from the functional path (20, 46) to the ejector (78) and connected to the suction connector (86).
G21C 17/10 - Combinaison structurelle de l'élément combustible, de la barre de commande, du cœur du réacteur, ou de la structure du modérateur avec des instruments sensibles, p.ex. pour la mesure de la radioactivité, des contraintes
G21C 19/303 - Dispositions pour introduire un matériau fluent à l'intérieur du cœur du réacteur; Dispositions pour enlever un matériau fluent du cœur du réacteur avec purification continue du matériau fluent en circulation, p.ex. par extraction des produits de fission spécialement adaptés pour des gaz
44.
VENTING SYSTEM FOR THE CONTAINMENT STRUCTURE OF A NUCLEAR INSTALLATION
It is sought to provide a pressure release system (30) for the containment structure (4) of a nuclear installation (2), which pressure release system permits effective and reliable operation of a wet scrubber (36) for the pressure release flow with a simultaneously compact design, in particular with regard to the amounts of washing fluid (52) that must be kept available. This is achieved according to the invention by means of a pressure release system (30) having • a pressure release line (28) which is guided through the containment structure (4) and which can be closed off by means of a shut-off fitting (26), • a wet scrubber (36), which is connected into a section of the pressure release line (28) situated within the containment structure (4), for the pressure release flow generated during pressure release operation with the shut-off fitting (26) open, • a reservoir (100) which is situated within the containment structure (4) and which is connected in terms of flow to the rest of the interior of the containment structure (4) such that a positive pressure prevailing there in relation to the environment outside the containment structure (4) is at least partially, preferably predominantly or entirely, transmitted to the reservoir (100), and • a feed line (72) which leads from the reservoir (100) to the wet scrubber (36) and which serves for the feed of liquid (14), which acts as washing fluid (52), from the reservoir (100) to the wet scrubber (36), wherein the wet scrubber (36) has a washing fluid vessel (38) which is sealed off with respect to the rest of the interior of the containment structure (4), and wherein a throttle section (102) is formed in a section of the pressure release line (28) upstream of the passage (44) into the washing fluid vessel (38).
G21C 19/303 - Dispositions pour introduire un matériau fluent à l'intérieur du cœur du réacteur; Dispositions pour enlever un matériau fluent du cœur du réacteur avec purification continue du matériau fluent en circulation, p.ex. par extraction des produits de fission spécialement adaptés pour des gaz
The invention relates to a pressure release system (18) for a containment structure (4) of a nuclear installation (2), having a pressure release line (16) which is guided through the containment structure (4) and which can be closed off by means of a shut-off fitting (30, 32), wherein a wet scrubber (36) for the pressure release gas flow generated during pressure release operation with the shut-off fitting (30, 32) open is connected into a section of the pressure release line (16) situated outside the containment structure (4). Based on this, it is the intention to permit effective and reliable operation of the wet scrubber (36) with a simultaneously compact design, in particular with regard to the amounts of washing fluid (52) that must be kept available. This is achieved according to the invention by means of • a reservoir (67) which is arranged in the containment structure (4) or connected in terms of flow thereto such that a positive pressure prevailing in the containment structure (4) in relation to the outside environment is at least partially, preferably predominantly or entirely, transmitted to the reservoir (67), and • a feed line (68), which leads from the reservoir (67) to the wet scrubber (36) and which can be closed off by means of a shut-off fitting (72), for the feed of liquid (14), which acts as washing fluid (52), from the reservoir (67) to the wet scrubber (36).
G21C 19/303 - Dispositions pour introduire un matériau fluent à l'intérieur du cœur du réacteur; Dispositions pour enlever un matériau fluent du cœur du réacteur avec purification continue du matériau fluent en circulation, p.ex. par extraction des produits de fission spécialement adaptés pour des gaz
FRAUNHOFER-GESELLSCHAFT ZUR FÖRDERUNG DER ANGEWANDTEN FORSCHUNG E.V. (Allemagne)
AREVA GMBH (Allemagne)
Inventeur(s)
Altpeter, Iris
Tschunky, Ralf
Herrmann, Hans-Georg
Kurz, Jochen
Dobmann, Gerd
Hübschen, Gerhard
Bergholz, Steffen
Rudolph, Jürgen
Abrégé
The present invention relates to a method for detecting temporally varying thermomechanical stresses and/or stress gradients over the wall thickness of metal bodies (1), in particular pipelines. In the method, the temperature on the outer surface of the body (1) is measured in order to determine a temperature progression and stress progression therefrom. In addition, electromagnetic ultrasonic transducers (3-6) are used at at least one measuring point on the outer surface in order to determine the progression of the stresses and/or stress gradients over time over the wall thickness of the body (1) in conjunction with the result of the temperature measurement. The method allows the fatigue monitoring of pipelines even in the event of rapid stress changes.
The invention relates to a lance for removing deposits (8) adhering to the tube sheet (4) of a steam generator (1), comprising a flexible strip (14) which is introducing into intermediate tube areas (12) of the steam generator (1), which has a cleaning head (15) at the free end of the strip, and which comprises at least one water hose (18) that is used to supply a flow of water to the cleaning head. In a use situation, the cleaning head comprises a working face (33) which faces the tube sheet or deposits present thereon, an outlet opening (54) which is fluidically connected to the water hose and opens into the working face, and a mechanical tool (21a, 21b) which acts on the deposits and removes material.
The invention relates to a device (70) for detecting unauthorised manipulations of the system state of an open-loop and closed-loop control unit (8), in particular of a programmable logic controller (10), of a nuclear plant (2), which device should be able to reliably detect unauthorised manipulations. For this purpose, a monitoring module (82) is provided, which monitors the operating state and/or hardware expansion state and/or program state of the open-loop and closed-loop control unit (8) and generates an indication when said state changes.
G06F 21/56 - Détection ou gestion de programmes malveillants, p.ex. dispositions anti-virus
G06F 21/57 - Certification ou préservation de plates-formes informatiques fiables, p.ex. démarrages ou arrêts sécurisés, suivis de version, contrôles de logiciel système, mises à jour sécurisées ou évaluation de vulnérabilité
49.
METHOD FOR THE SURFACE DECONTAMINATION OF COMPONENT PARTS OF THE COOLANT CYCLE OF A NUCLEAR REACTOR
The invention relates to a method for the chemical decontamination of a surface, having an oxide layer, of a metallic component part of the coolant system of a nuclear power plant, said method comprising at least one oxidation step, in which the oxide layer is treated with an aqueous solution containing an oxidant, and a subsequent decontamination step, in which the oxide layer is treated with an aqueous solution of a decontamination acid, which has the property of forming, with metal ions, in particular with nickel ions, a poorly soluble precipitate. Prior to implementing the decontamination step, metal ions which have dissolved during the oxidation step are removed from the aqueous solution with the aid of a cation exchanger.
PIPE SHUT-OFF ARRANGEMENT, AND A DEVICE FOR THE EMERGENCY SUPPLY OF COOLANT LIQUID TO THE FUEL RODS IN A NUCLEAR POWER PLANT REACTOR CONTAINER, COMPRISING SUCH A PIPE SHUT-OFF ARRANGEMENT
The invention relates to a pipe shut-off arrangement (10) comprising a pipe section (10a) that is arranged in a pipeline (3) and has a shut-off element (19) which, when in a closed position, may be destroyed by an arrangement (22) located in the region of the pipe section (10a), said arrangement (10) being able to be actuated from outside in order to destroy the shut-off element (19).
G21C 9/008 - Suppression de la pression par des disques ou des diaphragmes de rupture
F16K 17/38 - Soupapes ou clapets de sûreté; Soupapes ou clapets d'équilibrage fonctionnant sous l'action de circonstances extérieures, p.ex. un choc, un changement de position d'une température excessive
G21C 9/02 - Moyens pour effectuer une réduction très rapide du facteur de réactivité dans des conditions défectueuses, p.ex. fusible pour réacteur
G21C 9/033 - Moyens pour effectuer une réduction très rapide du facteur de réactivité dans des conditions défectueuses, p.ex. fusible pour réacteur par un fluide absorbant
G21C 15/18 - Dispositions pour le refroidissement d'urgence; Mise hors circuit de la chaleur
51.
JET PUMP AND BOILING WATER REACTOR HAVING SUCH A JET PUMP
The invention relates to a jet pump (18) comprising a mixing chamber pipe (26) and a diffuser pipe (28), wherein the end of the mixing chamber pipe (26) is inserted into the diffuser pipe (28) in the manner of a nested arrangement and is mounted slidingly therein such that in an overlapping region (44) the diffuser pipe (28) surrounds the mixing chamber pipe (26) to form a substantially annular leakage gap (42). Measures shall be taken to avoid leakage-induced vibrations and shocks in such a jet pump (18) which measures do not require additional mechanical components and as far as possible eliminate the cause of the problem. According to the invention inside the overlapping region (44) at least in a partial section of the circumference at the outer face of the mixing chamber pipe (26) there is a plurality of axially aligned grooves (64) separated from one another by ridges or webs (66), the depth of which grooves decreases towards the leakage flow (48) that occurs during operation of the jet pump (18).
The invention relates to a jet pump (18) having a mixing chamber tube (26) and having a diffuser tube (28), wherein the mixing chamber tube (26) is plugged into the diffuser tube (28) on the end side in the manner of a nested arrangement and is mounted slidingly therein, with the result that, in an overlapping region (44), the diffuser tube (28) encloses the mixing chamber tube (26) with the formation of a substantially annular leakage gap (42). Measures are to be realized for avoiding leakage-induced vibrations and jolts in a jet pump (18) of this type, which measures manage without additional mechanical components, are easy to retrofit and eliminate the cause of the problem as far as possible. To this end, it is provided according to the invention that a number of passage openings (54) and/or edge recesses (64) are made in the tube wall (56) of the diffuser tube (28) within the overlapping region (44) and/or in the immediate vicinity thereof, the shape and position of which passage openings (54) and/or edge recesses (64) are selected in such a way that the leakage flow (48) which is produced during operation of the jet pump (18) generates a resulting force which deflects the mixing chamber tube (26) relative to the diffuser tube (28) in a temporally constant direction with regard to the circumference.
In a pipe system (2) having a pipeline (4) through which a fluid can flow, from which pipeline a cavity branches off (14), the excitation of standing acoustic waves in the cavity (14) by a fluid flowing through the pipeline (4) is reduced such that damage and extraordinary wear of components located downstream of or branching off to the side of the pipe system (2) such as valves, steam dryers and the like is prevented. To this end, according to the invention, a turbulator (24) is arranged in the pipeline (4) upstream of the cavity (14) seen in the direction of flow (8) or in the region of the cavity (14), which turbulator is designed such that eddies break up on the turbulator (24) when the fluid flows through the pipeline (4) under rated operating conditions, the breakaway frequency of which eddies being greater than the acoustic resonance frequency of the cavity (14) and therefore excitation of resonant pressure oscillations in the cavity (14) is at least partially, preferably completely, suppressed.
The invention relates to the production of a modular, prefabricated, solid, reinforced concrete construction made of reinforced concrete plates and joint connection elements, which, after connecting the individual elements as a monolithic unit, bears the high load level under various load cases as are typical in nuclear power plant construction. Said aim is achieved by a wall element (2), designed as a prefabricated concrete component, for erecting a structure having a wall body having a substantially rectangular base area and four edges, which wall body has an inner shell (4), an outer shell (6) and a core filling (8) there between, in the manner of a sandwich design.
E04C 2/04 - Eléments de construction de relativement faible épaisseur pour la construction de parties de bâtiments, p.ex. matériaux en feuilles, dalles ou panneaux caractérisés par des matériaux spécifiés en béton ou autre matériau analogue à la pierre; en ciment d'amiante
E04C 2/06 - Eléments de construction de relativement faible épaisseur pour la construction de parties de bâtiments, p.ex. matériaux en feuilles, dalles ou panneaux caractérisés par des matériaux spécifiés en béton ou autre matériau analogue à la pierre; en ciment d'amiante renforcé
55.
SYSTEM AND METHOD FOR EXAMINING THE MICROSTRUCTURE OF A METAL COMPONENT
The invention relates to a system (2) for examining the microstructure of a metal component (32) which should enable microstructure examinations under adverse conditions and significantly reduce the risks and disturbances to persons involved. For this purpose, a controllable manipulator arm (8) is provided, which has an accommodating device (20) for machining tools at an accommodating end (16), and having a tool group of machining tools, which comprises a grinding and polishing tool (14), an etching tool (160), and a sample-taking tool (90).
G01N 1/28 - Préparation d'échantillons pour l'analyse
B25J 15/04 - Têtes de préhension avec possibilité pour l'enlèvement ou l'échange à distance de la tête ou de parties de celle-ci
G01N 1/08 - Dispositifs pour prélever des échantillons à l'état solide, p.ex. par coupe à l'outil impliquant un outil d'extraction, p.ex. mèche cylindrique creuse ou trépan
The invention relates to a device for closing a pipe opening (7), opening upwards, of a drive casing pipe (1) accommodating the control rod drive of a boiling water reactor, said device comprising a closure plug (8) with a plug housing (10), opening downwards, a sealing element (13) guided axially so as to be movable within the plug housing, which element has a sealing face (15) providing a sealing contact with an annular counter face (16) defining the pipe opening (7), a locking element (14) provided to fix the plug housing (10) on the drive casing pipe (1), and a spring (26), which is supported by the upper end thereof on the plug housing and by the lower end thereof on the sealing element and holds said element in a lower end position.
The invention relates to a device (14) for the automated application of a lubricant (16) inside a pipeline (18). According to the invention, the device (14) comprises to this end: a supply line (22) for a transport gas (24) connected to the pipeline (18), into which supply line a connecting piece (31) is connected as a T-junction or 4-way junction (32); a transverse line (34) connected to this connecting piece (31), which transverse line encloses a lubricant plunger (36) which can be moved along the line longitudinally; and a lubricant reservoir (56) connected to the transverse line (34), wherein the lubricant plunger (36) is sealed at the outer circumference thereof against the transverse line (34). The lubricant plunger has a depression (50) to accept a portion of lubricant (16). The plunger can be moved from a load position (58) into a delivery position (60). In the load position (58), the depression (50) communicates with the lubricant reservoir (56) and, in the delivery position (60), the depression is arranged inside the connecting piece (31) where the transport gas (24) flowing into the pipeline (18) can flow over it.
F16N 7/30 - Installations à huile ou autre lubrifiant non spécifié, à réservoir ou autre source portés par la machine ou l'organe machine à lubrifier l'huile étant entraînée par un autre fluide
58.
BOILING WATER REACTOR HAVING DRIVE HOUSING OF A CONTROL ROD DRIVE
The invention relates to a boiling water reactor (8), comprising a reactor pressure vessel (14) provided with an base wall (12) having a recess (6), through which a drive housing (10) of a control rod drive (6) is guided, wherein in the final assembly position, the drive housing (4) is welded to the base wall (12), or to a connection piece (80) connected to the base wall (12). In connection therewith, a securing device (2) is to be disclosed, by way of which with simple installation and good access for maintenance purposes, the drive housing (4) is held by the base wall (12) of the reactor pressure vessel (14) during dismantling, to be specific, without additional stress peaks and increased operational material fatigue of the reactor pressure vessel (14). For this purpose, the invention provides that below the welding point (16), a retaining device (2) for the drive housing (4) is formed, in the event of a failure of the welding point (16), or of dismantling, provided with a retaining ring (24) surrounding the drive housing (4), having a lower end face (40) and an upper end face (44). The lower end face (40) of the retaining ring (24) faces an annular step (30) of the recess (10) engaging below said end face. The upper end face (44) of the retaining ring (24) faces an annular step (50) of the drive housing (4) engaging above said end face. During normal operation, the retaining ring (24) is not within the power flow of the drive housing (4).
G21C 7/08 - Commande de la réaction nucléaire par application de matériau absorbant les neutrons, c. à d. matériau avec section efficace d'absorption excédant largement la section efficace de réflexion par déplacement des éléments de commande solides, p.ex. barres de commandes
G21C 13/032 - Raccords entre le tube et la paroi d'une enceinte, p.ex. tenant compte des contraintes thermiques
G21C 13/036 - Raccords entre le tube et la paroi d'une enceinte, p.ex. tenant compte des contraintes thermiques le tube traversant la paroi, c. à d. s'étendant de chaque côté
59.
DEVICE AND METHOD FOR REMOVING A SEALING ELEMENT FROM A CONNECTING PIECE OF A COAXIAL CABLE
The invention relates to a device and a method for removing a sealing element (8) from a connecting piece (2) of a coaxial cable, having: - a first sleeve (12) having a longitudinal axis (L), said first sleeve (12) having a first internal thread (14) and a second internal thread (18), wherein the first sleeve is screwable onto one end (20) of the connecting piece (2) by way of the first internal thread and the diameter of the first internal thread is greater than the diameter of the second internal thread, - a second sleeve (24) having a first end (26) and a second end (28), said second sleeve (24) being screwable into the first sleeve in the direction of the longitudinal axis and having, between the two ends, a section (30) with an external thread (32) opposed to the first internal thread of the first sleeve, wherein the external thread interacts with the second internal thread of the first sleeve, the first end has a rotary actuation element (33) and the second end has at least one engaging element (34) which is configured such that, when the second sleeve is screwed into the first sleeve, it engages into the sealing element in an inclined manner with respect to the direction of the longitudinal axis, and - a fixing element (36) for fixing the first sleeve to the second sleeve.
B25B 27/00 - Outils à main ou outillage d'établi, spécialement conçus pour assembler ou séparer des pièces ou des objets, que cela entraîne ou non une certaine déformation, non prévus ailleurs
H01R 43/00 - Appareils ou procédés spécialement adaptés à la fabrication, l'assemblage, l'entretien ou la réparation de connecteurs de lignes ou de collecteurs de courant ou pour relier les conducteurs électriques
H01R 24/40 - Dispositifs de couplage en deux pièces, ou l'une des pièces qui coopèrent dans ces dispositifs, caractérisés par leur structure générale ayant des contacts disposés concentriquement ou coaxialement spécialement adaptés à la haute fréquence
The invention relates to a beam assembly, comprising a substantially straight beam (2), which is arranged between two bearings (4, 6) and extends in a longitudinal direction (8) and comprises at least three segments (10, 2, 14), which are arranged one behind the other in the longitudinal direction (8) and which are connected to each other by means of two head plate joints (22), namely a middle segment (10) and two outer segments (12, 14), wherein the bearings (4, 6) are prevented from moving in the longitudinal direction (8), should permit controlled relief of thermal constraining forces while the load-transferring function is simultaneously maintained and while external dynamic forces are evenly distributed within the construction. According to the invention this is achieved in that the middle segment (10) has a middle segment head plate (18) at each of the two ends of the middle segment and each of the two outer segments (12, 14) has an outer segment head plate (20) at the end of the outer segment directed toward the middle segment (10), each outer segment head plate (20) is oriented complementarily to the middle segment head plate (18) facing the outer segment head plate in such a way that the outer segment head plate and the middle segment head plate together form a head plate joint (22), the two head plates (18, 20) of each head plate joint (22) are connected to each other by means of connecting bolts (28), which are inserted through openings (26) in the head plates (18, 20), the openings (26) in at least one of the head plates (18) of each head plate joint (22) are designed as elongated holes (34), and both head plate joints (22) are angled in opposite directions with respect to a plane normal to the longitudinal direction (8) in such a way and the elongated holes (34) are arranged and oriented in such a way that lateral displacement of the middle segment (10) in relation to the two outer segments (12, 14) is possible in the event of thermal expansion or contraction of the segments (10, 12, 14).
The invention relates to a method for measuring the deflection of a fuel element can (10) for a fuel element (8) of a boiling water reactor. According to said method an image of the fuel element can (10) is taken with a camera (2) and evaluated by photogrammetry. By means of the method according to the invention, it is possible to determine the deflection of a fuel element can by taking a single image, even in the absence of external structural features recognisable in the image, and without knowledge of the relative position between the camera (2) and the fuel element can (10).
G01B 11/245 - Dispositions pour la mesure caractérisées par l'utilisation de techniques optiques pour mesurer des contours ou des courbes en utilisant plusieurs transducteurs fixes fonctionnant simultanément
62.
CONTAINMENT PROTECTION SYSTEM FOR A NUCLEAR FACILITY AND ASSOCIATED OPERATING METHOD
A containment protection system (2) for treating the atmosphere present in the containment (4) of a nuclear facility (6), particularly a nuclear power plant, in case of critical incidents involving extensive release of hydrogen (H2) and steam is to be able to effectively and quickly relieve such conditions in a largely passive manner and where possible without contaminating the environment. According to the invention, the containment protection system (2) has for this purpose a circuit, which comprises a conduction system (10, 72, 120, 128) and which is provided for connecting to the containment (4), out of the containment (4) and back again for a fluid flow, more particularly having the following components fluidically connected in series: a recombination device (20) for recombining hydrogen (H2) contained in the fluid flow with oxygen (O2) to form steam (H2O); a condensation device (74) connected downstream of the recombination device (20) for condensing steam fractions contained in the fluid flow with means for diverting the condensate (94) out of the fluid flow; drive means (18, 180) for the fluid flow, a heat exchanger (96) being provided for an at least partial re-cooling of the condensation device (74) and being connected on the inlet side via a feed line (144) to a storage tank (140) for liquid nitrogen (N2).
G21C 9/06 - Moyens de prévention de l'accumulation de gaz explosifs, p.ex. recombinateurs
G21C 13/02 - Enceintes sous pression; Enceintes d'enveloppe; Enveloppes en général - Détails
G21C 19/30 - Dispositions pour introduire un matériau fluent à l'intérieur du cœur du réacteur; Dispositions pour enlever un matériau fluent du cœur du réacteur avec purification continue du matériau fluent en circulation, p.ex. par extraction des produits de fission
The invention relates to a heat removal system (2) for a nuclear system, in particular a nuclear reactor system (30) or a fuel reservoir (84), with a heat source (4), in particular in the form of residual heat which is generated during the radioactive decay of irradiated nuclear fuel. A circuit (8) for a working medium (6) comprises an evaporator (10) which is thermally coupled to the heat source (4) in order to evaporate the working medium (6), a heat engine (12) in order to produce mechanical work from the expanding working medium (6), a condenser (14) which is thermally coupled to a heat sink (16) in order to condense the expanded working medium (6), and a working medium pump (18) which is driven by the heat engine (12) in order to pump the working medium (6) in the circuit (8). Said type of heat removal system (2) is to be developed so as to have a high degree of efficiency and be functional even at a relatively low temperature of the heat source (4) and/or with a comparably poor thermal coupling to the heat source (4) while maintaining high operational safety standards. According to the invention, the circuit (8) is designed as a low-temperature circuit (9) for this purpose, wherein the working medium (6) contains a component with a lower boiling point than water.
The invention addresses the problem of reinforcing a nuclear plant (2), comprising a containment shell (4) and at least one pressure relief line (10) which is lead out from the containment shell (4) and which can be shut by means of a shut-off valve (14) and through which a pressure relief flow can flow in relief mode when the shut-off valve (14) is open, such that the nuclear plant is designed to cope in a particularly reliable manner with critical scenarios in which a significant increase in pressure occurs inside the containment shell (4) simultaneously with the release of hydrogen (H2) and/or carbon monoxide (CO). To this end, a gas flow treatment device (24) is located inside the containment shell (4) on the inlet side, arranged upstream of the respective pressure relief line (10) and comprises a chimney-like flow channel (26) which is enclosed by a lateral shell surface (28) and which has a lower inflow opening (30) and an upper inflow and outflow opening (32), a first group of catalytic elements (34) being arranged above the lower inflow opening (32) in order to reduce hydrogen (H2) and/or carbon monoxide (CO) in the flow channel (26), and the pressure relief line (10) having an inlet opening (22) which is arranged above the first group of catalytic elements (34) and below the upper inflow and outflow opening (32) in the shell surface (28), such that, in the event of a critical disruption in which hydrogen (H2) and/or carbon monoxide (CO) are released in the containment shell (4), a gas mixture which is present in the containment shell (4) flows through the flow channel (26) from the bottom to the top according to the principle of natural convection in a convection mode which precedes the relief mode and in which the shut-off valve (14) is closed, and, in the relief mode, the gas mixture flows into the flow channel (26) from the bottom and preferably also from the top according to the principle of forced overflow and flows out as a pressure relief flow via the pressure relief line (10).
The invention relates to a digital sensing circuit (100) for a secondary clock signal (204) to be monitored for clock failure with the aid of a primary clock signal (202), comprising a flip-flop (102) which has a clock input (108), a data input (106), a Q output (110) and a reset input (112), and further comprising an n-bit counter (104) which has a clock input (114), a reset input (128) and a counter reading output (116). The digital sensing circuit according to the invention should avoid meta-stable states being reached and also detect multiple state changes of the secondary clock signal (204) within a cycle time and thus be suitable for operating safety-relevant assemblies, which can also be used in nuclear power plants. For this purpose, the flip-flop (102) and the n-bit counter (104) are wired electrically to each other, wherein n ≥ 2, the primary clock signal (202) is present on the clock input (114) of the n-bit counter (104), the secondary clock signal (204) is present on the clock input (108) of the flip-flop (102), a constant signal is present on the data input (106) of the flip-flop (102), the Q output (110) of the flip-flop (102) is connected to the reset input (128) of the n-bit counter (104), and the counter reading output (116) of the n-bit counter (104) is connected to the reset input (112) of the flip-flop (102) via an interposed logic gate (122).
The invention relates to a gripper for raising and lowering loads and having the following configuration: - it comprises a coupling part (3) and a connecting part (4), - the connecting part is guided on the coupling part for movement along a movement axis (5) between a first end position (E1) and a second end position (E2), wherein those ends of the aforementioned parts which are oriented away from one another are further apart from one another in the first end position than in the second end position, - at least two catch elements (7) are present on the coupling part (3) and can be moved between a gripping position (G), in which they use a rear-engagement surface (8) to engage behind a mating element (9) of the load (2), and a release position (F), in which they release the mating element, - the connecting part (3) is connected to the at least two catch elements (7) via at least one gear mechanism (10) such that, in the first end position (E1), the catch elements are located in their gripping position (G) and, in the second end position (E2), the catch elements are located in their release position (F), - the at least two catch elements (7) are spaced apart from one another in the circumferential direction of an imaginary circle (13) which concentrically comprises a centre longitudinal axis (6) of the gripper (1), said axis running parallel to the movement axis (5), - the catch elements (7) are spaced apart from the centre longitudinal axis (5) by a greater distance (14) in the gripping position (G) than in the release position (F).
The invention relates to a method for operating a steam generator (1) of a power plant, in particular of a nuclear power plant, wherein the steam generator comprises a secondary chamber (4) and, arranged therein, a multiplicity of pipes (7) which are in the form of U-shaped pipes and which have two parallel-running legs (8) and a pipe bend (9) connecting said legs to one another. Bending oscillations of a pipe caused by a medium flowing through the secondary chamber and/or through the pipes are detected by virtue of a parameter which characterizes the intensity of the bending oscillation being detected by means of a sensor and, if a threshold range of the vibration intensity which is critical with regard to damage to the pipes is approached or reached, the operating conditions of the steam generator being set such that bending oscillations occur with an intensity that lies outside the threshold range.
F22B 1/02 - Méthodes de production de vapeur caractérisées par le genre de chauffage par exploitation de l'énergie thermique contenue dans une source chaude
F22B 35/00 - Systèmes de commande pour chaudières à vapeur
F22B 35/18 - Utilisation des machines à calculer pour la commande des chaudières à vapeur
F22B 37/00 - MÉTHODES DE PRODUCTION DE VAPEUR; CHAUDIÈRES À VAPEUR - Détails ou parties constitutives des chaudières à vapeur
F22B 37/38 - Détermination ou signalisation des conditions de marche dans les chaudières à vapeur, p.ex. enregistrant la direction ou le débit du courant d'eau dans les tubes
F22B 37/42 - Utilisation, agencement ou disposition des dispositifs d'alarme ou des dispositifs automatiques de sécurité
G21C 17/017 - Inspection ou maintenance de tuyaux ou de tubes dans des installations nucléaires
The invention relates to a method and a device (10) for destroying whiskers (4a, 4b) on electronic components (1) by applying a sound signal (S) to the component (1).
B08B 7/02 - Nettoyage par des procédés non prévus dans une seule autre sous-classe ou un seul groupe de la présente sous-classe par distorsion, battage ou vibration de la surface à nettoyer
The invention relates to a nuclear power plant in which the sluice (10) between a fuel pool (4) and a reactor cavity (2) is provided with a contactor (36), with which the sluice (10) is automatically locked when the water level (h) in the fuel pool (4) falls under a predetermined threshold value (hG).
G21C 13/10 - Moyens pour prévenir la contamination dans le cas d'une fuite
G21C 17/02 - Dispositifs ou dispositions pour la surveillance du réfrigérant ou du modérateur
G21C 19/07 - Râteliers de stockage; Piscines de stockage
G21C 19/32 - Appareils pour enlever des objets ou matériaux radioactifs de l'aire de décharge du réacteur, p.ex. pour les porter à un emplacement de stockage; Appareils pour manipuler des objets ou matériaux radioactifs à l'intérieur d'un emplacement de stockage ou les extraire de celui-ci
G21C 19/40 - Dispositions pour prévenir l'apparition de conditions critiques, p.ex. pendant le stockage
G21C 19/18 - Appareils pour porter les éléments combustibles à l'aire de charge du réacteur, p.ex. depuis un emplacement de stockage
G21C 19/08 - Moyens pour le chauffage des éléments combustibles avant leur introduction dans le cœur; Moyens pour le chauffage ou le refroidissement des éléments combustibles après leur extraction du cœur
70.
FEED WATER DISTRIBUTING SYSTEM FOR A NUCLEAR POWER PLANT, AND METHOD FOR OPERATING A NUCLEAR POWER PLANT
The invention relates to a feed water distributing system (12) for a nuclear power plant, consisting of at least two feed water distributers (20) which are arranged within a reactor pressure vessel (1). The feed water distributing system is to be designed so as to have a consistent feed water distribution when starting up and during a partial load operation with low mechanical loads and to have a redundancy of the individual components while maintaining the customary level of reliability in nuclear power plants. For this purpose, the feed water distributing system (12) according to the invention is designed such that each feed water distributer (20) has exactly one annular main body (17) with an inner channel (30), at least one fill socket (24) which is fluidically connected to the inner channel (30) via at least one fill opening (26), and a plurality of outlet nozzles (22) which are fluidically connected to the inner channel (30). Each of the fill sockets (24) of one feed water distributer (20) is fluidically connected to each outlet nozzle (22) of said feed water distributer (20). In a method which is particularly suitable for operating a nuclear power plant using such a feed water distributing system (12), exactly one feed water distributer (20) is used in a start-up operation, and more than one feed water distributer (20) is used in a full-load operation.
G21C 15/02 - Aménagement ou disposition de passages dans lesquels la chaleur est transférée au réfrigérant, p.ex. pour la circulation du réfrigérant à travers les supports des éléments combustibles
71.
PROCESS FOR REMOVAL OF RADIOACTIVE CONTAMINATION FROM WASTEWATER
The invention relates to a process for removal of radioactive contamination from wastewater obtained in the decontamination of the cooling circuit of nuclear reactors or of parts thereof or in the course of operation of a nuclear reactor, in which exclusively an MnO2 precipitate is produced in the wastewater with the aid of permanganate ions added thereto as an oxidizing agent and of one or more organic reducing agents present in and/or metered into the wastewater, and this MnO2 precipitate is separated from the wastewater.
The invention relates to a method for purifying and conditioning the circulatory system (1) of a power plant, especially of a nuclear power plant. According to said method, an amine as the film-forming agent is metered to the working medium circulating in the circulatory system, said film-forming agent forming a hydrophobic film on the surfaces of the circulatory system. During the process, the concentration of the film-forming agent is monitored in at least one measuring point by way of measurement, and metering of the film-forming agent is stopped once its concentration in the working medium has reached a value of 1 ppm to 2 ppm in at least one measuring point M1.
C23F 11/00 - Inhibition de la corrosion de matériaux métalliques par application d'inhibiteurs sur la surface menacée par la corrosion ou par addition d'inhibiteurs à l'agent corrosif
F01D 25/00 - "MACHINES" OU MACHINES MOTRICES À DÉPLACEMENT NON POSITIF, p.ex. TURBINES À VAPEUR - Parties constitutives, détails ou accessoires non couverts dans les autres groupes ou d'un intérêt non traité dans ces groupes
G21C 17/022 - Dispositifs ou dispositions pour la surveillance du réfrigérant ou du modérateur pour la surveillance de réfrigérants ou de modérateurs liquides
The invention relates to a method for encapsulating a fuel rod (20) or fuel rod section in a container (2), comprising the following steps: a) inserting the fuel rod (20) or fuel rod section into the container (2); b) connecting one of the ends of the container (2) to a purging-gas line; c) dehydrating and purging the container (2) by means of purging gas (G); d) connecting the ends of the container (2) to a bypass line (118) in such a way that a closed gas circuit is produced and circulating a hot gas (H) in said gas circuit until the absolute moisture content reaches an end value (Xmax) at which the absolute moisture content no longer rises; e) disconnecting the container (2) from the gas circuit; and f) subsequently closing the container (2) in a fluid-tight manner at both ends.
G21C 19/26 - Dispositions pour enlever les éléments combustibles ou les éléments de commande grippés ou endommagés; Dispositions pour déplacer les parties cassées de ceux-ci
G21F 5/008 - Récipients pour éléments combustibles
G21F 5/12 - Dispositifs obturateurs pour récipients; Dispositions pour leur étanchéité
F26B 21/00 - Dispositions pour l'alimentation ou le réglage de l'air ou des gaz pour le séchage d'un matériau solide ou d'objets
G21C 19/32 - Appareils pour enlever des objets ou matériaux radioactifs de l'aire de décharge du réacteur, p.ex. pour les porter à un emplacement de stockage; Appareils pour manipuler des objets ou matériaux radioactifs à l'intérieur d'un emplacement de stockage ou les extraire de celui-ci
74.
METHOD FOR PURIFYING AND CONDITIONING THE WATER-STEAM CIRCUIT OF A POWER PLANT, ESPECIALLY OF A NUCLEAR POWER PLANT
The invention relates to a method for purifying and conditioning the water-steam circuit (1) of a power plant, especially of a nuclear power plant. According to said method, an amine as the film-forming agent is metered to the working medium circulating in the water-steam circuit (1), said film-forming agent forming a hydrophobic film on the surfaces of the circuit (1). During the process, the concentration of at least one impurity contained and the concentration of the film-forming agent at least in the feed water of the steam generator are monitored by way of measurement, and the concentration of the film-forming agent is varied subject to the concentration of the impurity.
C23F 11/00 - Inhibition de la corrosion de matériaux métalliques par application d'inhibiteurs sur la surface menacée par la corrosion ou par addition d'inhibiteurs à l'agent corrosif
F01D 25/00 - "MACHINES" OU MACHINES MOTRICES À DÉPLACEMENT NON POSITIF, p.ex. TURBINES À VAPEUR - Parties constitutives, détails ou accessoires non couverts dans les autres groupes ou d'un intérêt non traité dans ces groupes
G21C 17/022 - Dispositifs ou dispositions pour la surveillance du réfrigérant ou du modérateur pour la surveillance de réfrigérants ou de modérateurs liquides
G21D 1/00 - ENSEMBLES DE PRODUCTION D'ÉNERGIE NUCLÉAIRE - Détails des installations à énergie nucléaire
The invention relates to a device (1) for separating a fluid mass flow (M0) in a nuclear plant, comprising a primary end piece (3) for conducting the fluid mass flow (M0) and a plurality of secondary end pieces (4, 6) for conducting a plurality of separate partial flows (M1, M2, M3) of the fluid mass flow (M0), wherein a number of separating elements (2, 8) is provided in the area within the primary end piece (3), and each of the partial areas (V1; V2, V3) defined by the separating element (2, 8) or the separating elements (2, 8) opens in a secondary end piece (4, 6) clearly assigned to the partial area (V1; V2, V3).
The invention relates to an apparatus (0) for measuring the position of a displaceable control rod, having a plurality of secondary coils (S'1-S'47) which are arranged behind one another along a displacement path and are inductively excited by at least one primary coil (1), wherein one or more secondary coils (S'1-S'47) are respectively combined to form at least two coil groups in such a manner that a position signal (P'1-P'3) generated with the aid of the respective coil group is increased or reduced in a step-like manner if the control rod is pushed past the secondary coils (S'1-S'47). Such an apparatus (0), on the one hand, is intended to require the smallest possible number of measuring lines (M0, M1-M'3) and, on the other hand, is intended to determine the control rod position with a high resolution with high operational safety and reliability. For this purpose, the arrangement and connection of the secondary coils (S'1-S'47) are selected according to the invention in such a manner that all of the position signals (P'1-P'3) from all coil groups can be used to unambiguously determine the instantaneous position of the control rod, and at least one of the coil groups has at least two secondary coils (S'1-S'47) which are connected to one another in such a manner that the associated position signal (P'1-P'3) assumes at least three discrete signal levels (N'0-N'3) as the control rod is pushed forwards. The invention also relates to a corresponding method.
G01D 5/20 - Moyens mécaniques pour le transfert de la grandeur de sortie d'un organe sensible; Moyens pour convertir la grandeur de sortie d'un organe sensible en une autre variable, lorsque la forme ou la nature de l'organe sensible n'imposent pas un moyen de conversion déterminé; Transducteurs non spécialement adaptés à une variable particulière utilisant des moyens électriques ou magnétiques influençant la valeur d'un courant ou d'une tension en faisant varier l'inductance, p.ex. une armature mobile
77.
CONTAINER, DEVICE, AND METHOD FOR ENCAPSULATING A FUEL ROD OR A FUEL ROD PORTION IN A GAS-TIGHT MANNER
The invention relates to a container (2), a device, and a method for encapsulating a fuel rod (20) or a fuel rod portion in a gas-tight manner. The container (2) has a hollow cylindrical container part (8) which is closed at the free ends of the container part in a fluid-tight manner by a respective single-piece closure stopper (10). The closure stopper (10) is provided with a channel (14) that fluidically connects the flushing chamber (15) of the container part (8) to the exterior (16) exclusively in an intermediate position, which is assumed prior to reaching an end position during the assembly process and in which the closure stopper (10) additionally projects out of the container part by an axial length (s) compared to the end position of the closure stopper.
G21C 19/26 - Dispositions pour enlever les éléments combustibles ou les éléments de commande grippés ou endommagés; Dispositions pour déplacer les parties cassées de ceux-ci
G21F 5/008 - Récipients pour éléments combustibles
G21F 5/12 - Dispositifs obturateurs pour récipients; Dispositions pour leur étanchéité
The invention relates to a passive return flow delimiter (20) for a flow medium designed in such a manner that said delimiter sufficiently delimits the return flow in the reverse direction in two-phase fluids and only insignificantly delimits the flow in the passage direction. According to the invention, said flow medium is further suitable for the use in safety-relevant areas, in particular in nuclear power plants. For this purpose, the passive return flow delimiter (20) is equipped with at least one inlet opening, one outlet opening and an intermediate supply network, a first group of flow diodes (22) switched into the supply network, which flow diodes are designed as Venturi nozzles, a second group of flow diodes (24) switched into the supply network, wherein the supply network is configured in such a manner that the flow medium in the return flow operation is first led from the outlet opening first via a flow diode of the second group (24) oriented towards the reverse direction and then via a flow diode of the first group (22) oriented towards the same direction.
The invention relates to a measuring device for measuring the position of a movable control rod (1) in a nuclear reactor, comprising at least one secondary coil unit (32) which is arranged along a movement path of the control rod (1) and which is inductively excited by at least one primary coil unit (10). The measuring device is to be designed so as to have an accuracy similar to conventional systems and so as to compensate for the failure of individual components associated with the primary coil (11-14) or the secondary coil (33-36) while simultaneously being implementable into existing and established components of nuclear power plants. This is achieved in that at least one primary coil unit (10) consists of at least two primary coils (11-14), each of which has substantially the same coil start and the same coil end in the direction of the movement path, and/or at least one secondary coil unit (32) consists of at least two secondary coils (33-36), each of which substantially has the same coil start and the same coil end in the direction of the movement path.
G21C 7/12 - Moyens pour amener les éléments de commande dans la position désirée
G21C 17/10 - Combinaison structurelle de l'élément combustible, de la barre de commande, du cœur du réacteur, ou de la structure du modérateur avec des instruments sensibles, p.ex. pour la mesure de la radioactivité, des contraintes
80.
DEVICE AND METHOD FOR REPAIRING A DAMAGED SPOT IN A WALL AREA OF A CONTAINER OR A BASIN SUBMERGED IN WATER
The invention relates to a device for repairing a damaged spot in a wall area of a container or a basin submerged in water, in particular in the wall area of the basin of a nuclear reactor plant, comprising a guiding system (6) that can be mounted to and fixed to a side wall (12), along said side wall and spaced apart therefrom. At least one first sliding carriage (20) is mounted on tracks of the guiding system (6), which sliding carriage (20) is guided on the guiding system (6) and can be moved in a longitudinal direction (5) thereof. A slidably mounted accommodation (30) for a repair support (22), which can be attached to the wall area having the damaged area (21) by way of an adhesive surface, is arranged on said sliding carriage, wherein at least one suction cup that can be set against the side wall (12) and is connected to a suction hose is arranged on the first sliding carriage (20).
G21C 19/02 - Dispositions pour le traitement, pour la manipulation, ou pour faciliter la manipulation, du combustible ou d'autres matériaux utilisés à l'intérieur du réacteur, p.ex. à l'intérieur de l'enceinte sous pression - Détails des dispositions pour la manipulation
G21C 19/20 - Dispositions pour introduire des objets à l'intérieur de l'enceinte sous pression; Dispositions pour manipuler des objets à l'intérieur de l'enceinte sous pression; Dispositions pour extraire des objets de l'enceinte sous pression
81.
METHOD FOR PRODUCING A CATALYST CONTAINING URANIUM OXIDE AS ACTIVE COMPONENT
The invention relates to a method for producing a uranium oxide catalyst body having the following steps: a) UO2+x powder (2) (where x ≤ 0.7) having a purity of at least 50% is sintered in a first sintering process to give a UO2+y intermediate (14) (where y ≤ 0.25), b) the UO2+y intermediate (14) is oxidized with oxygen and converted in the process into a U3O8-z powder (11) (where z ≤ 1), c) the U3O8-z powder (11) is pressed to form a blank (15) having a shape corresponding to the later catalyst body (1), and d) the blank (15) is sintered in a second sintering process at at least 900°C in an oxygen-containing sintering atmosphere.
B01J 35/10 - Catalyseurs caractérisés par leur forme ou leurs propriétés physiques, en général solides caractérisés par leurs propriétés de surface ou leur porosité
C04B 35/51 - Produits céramiques mis en forme, caractérisés par leur composition; Compositions céramiques; Traitement de poudres de composés inorganiques préalablement à la fabrication de produits céramiques à base de composés des actinides
82.
CONNECTION BETWEEN A CONTROL ROD GUIDE TUBE AND DRIVE HOUSING PIPE OF A NUCLEAR REACTOR
The bayonet plate of the bayonet plate closure between control rod guide tube (1) and drive housing pipe (2) of a boiling water reactor is designed in two parts. It comprises a central bayonet ring (6) mounted rotatably about its longitudinal axis (3) with an outer ring (7) completely surrounding said bayonet ring. The outer ring (7) is mounted on the circumference of the bayonet ring (6) and reaches inwards under the bayonet ring circumference. Said ring is furthermore permanently supported in the axial direction on the drive housing pipe (2) by the spring pressure acting on the control rod guide tube (1), in order to produce a frictional connection. This spring pressure can be released unhindered from the reactor side by tools.
The invention relates to a closure apparatus (2) for closing and sealing off a gas or oil well provided with a defective blowout preventer (4). To this end, according to the invention the closure apparatus (2) has a main body (8), in which a closure bell (12) is formed for enveloping the connection piece (6) of the blowout preventer (4) which protrudes out of the gas or oil well, and also a central bore (10), in which a closure element (16) which can be lowered into the connection piece (6) is mounted in a longitudinally displaceable manner.
E21B 43/01 - Procédés ou dispositifs pour l'extraction de pétrole, de gaz, d'eau ou de matériaux solubles ou fusibles ou d'une suspension de matières minérales à partir de puits spécialement adaptés à l'extraction à partir d'installations sous l'eau
The invention relates to an anchoring system for forming a non-releaseable connection between a concrete component (1), which has reinforcement comprising at least one steel bar mesh, and a steel component (3), wherein at least one anchoring element formed of an anchor strip (2) is cast into the concrete component (1) in such a way that at least one connecting surface projects at least partially from the concrete component (1). The object of the invention is to improve the loadability of the anchoring. For this purpose, according to the invention, the anchor strip (2) has a number of recesses which extend at least partially into the concrete component (1) and which are each traversed by at least one steel bar (10) of the steel bar mesh.
E04B 5/29 - Structures de planchers partiellement formées sur place avec des nervures de renforcement ou autres conformations semblables à des poutres totalement ou partiellement préfabriquées les parties préfabriquées des poutres étant entièrement constituées par du métal
E04C 3/294 - Poutrelles; Solives, fermes ou structures analogues à des fermes, p.ex. préfabriquées; Linteaux; Traverses formés d'éléments de différents matériaux les matériaux étant de l'acier et du béton du béton combiné avec une structure en treillis débordant latéralement hors de l'élément
E04C 5/065 - Treillages légers, p.ex. avec éléments précoulés
85.
WALL MODULE FOR BUILDING A STRUCTURE AND ASSOCIATED STRUCTURE
A wall module (2) which is designed as a concrete prefabricated building element for building a structure and which can easily be assembled and connected to further such wall modules (2) to form a structure should be designed not only for usual operating loads but additionally also to withstand improbable extreme loads. To that end, the wall module (2) has a wall body (8) having a regular base area and multiple edges, with a plurality of reinforcement rods (10) which all together form a regular reinforcement grid, and which preferably each extend parallel to the edges, and which are cast into the wall body (8), the reinforcement rods (10) each penetrating the wall body (8) substantially from edge to edge, and being provided at their ends with connecting elements (6) which are designed to establish a connection with complementary connecting elements (6) of an immediately adjacent wall element (2), and each connecting element (6) being connected with clearance to the associated reinforcement rod (10) such that it can be moved in a plane which is perpendicular to the longitudinal direction of the reinforcement rod (10) on all sides by at least 2 mm with respect to a provided central position.
E04B 1/04 - Structures constituées principalement d'éléments porteurs en forme de blocs ou de dalles les éléments étant en béton, p.ex. en béton armé, ou en un autre matériau pierreux
E04B 1/61 - Assemblages pour les constructions du bâtiment en général d'éléments de construction en forme de plaques en contact mutuel
E04C 2/06 - Eléments de construction de relativement faible épaisseur pour la construction de parties de bâtiments, p.ex. matériaux en feuilles, dalles ou panneaux caractérisés par des matériaux spécifiés en béton ou autre matériau analogue à la pierre; en ciment d'amiante renforcé
86.
APPARATUS FOR DETECTING A MAGNETICALLY CONDUCTIVE OBJECT AND POSITION MEASURING SYSTEM FOR MEASURING THE POSITION OF A GUIDE ROD AND ASSOCIATED POSITION MEASURING METHOD
The invention relates to an apparatus (1) for detecting a magnetically conductive object (11) in a detection area (2), having an electrical coil (3) and having at least one sensor element (4). Such an apparatus is intended to be as free of degradation processes as possible and is thus intended to require little maintenance and is also intended to be designed and set up with the highest possible degree of redundancy and measurement reliability. For this purpose, the invention provides for the coil (3) to be set up to form a magnetic field (H) in the detection area (2) and for the sensor element (4) to be designed to detect a magnetic field (H) with a field strength, the magnitude of which is greater than a predefined threshold value, and for the threshold value to be set to be higher than the field strength present in the detection area (2) when the magnetically conductive object (11) is absent and lower than the field strength present therein when said object (11) is present. The invention also relates to a position measuring system (12) for measuring a position (x1) or for measuring a plurality of positions (x1,... xN) of a guide rod (14) which is extended along a rectilinear path (x) with respect to a guide system (13), can be moved along the rectilinear path (x), is substantially formed from a magnetically conductive material and in which the above-mentioned apparatus (1) is used, and to a corresponding measuring method.
G01D 5/251 - Moyens mécaniques pour le transfert de la grandeur de sortie d'un organe sensible; Moyens pour convertir la grandeur de sortie d'un organe sensible en une autre variable, lorsque la forme ou la nature de l'organe sensible n'imposent pas un moyen de conversion déterminé; Transducteurs non spécialement adaptés à une variable particulière utilisant des moyens électriques ou magnétiques sélectionnant un ou plusieurs conducteurs ou circuits parmi un certain nombre de conducteurs ou circuits, p.ex. en fermant des contacts un conducteur ou circuit
G01D 5/56 - Moyens mécaniques pour le transfert de la grandeur de sortie d'un organe sensible; Moyens pour convertir la grandeur de sortie d'un organe sensible en une autre variable, lorsque la forme ou la nature de l'organe sensible n'imposent pas un moyen de conversion déterminé; Transducteurs non spécialement adaptés à une variable particulière utilisant des moyens spécifiés dans plusieurs des groupes , , , et utilisant des moyens électriques ou magnétiques
G21C 17/10 - Combinaison structurelle de l'élément combustible, de la barre de commande, du cœur du réacteur, ou de la structure du modérateur avec des instruments sensibles, p.ex. pour la mesure de la radioactivité, des contraintes
87.
SECURING DEVICE FOR A CONTROL ROD IN A NUCLEAR PLANT
The invention relates to a securing device (1) for a control rod (14) in a nuclear plant (16), comprising a control rod drive (5) and a drive housing (4), which encloses the control rod drive (5) and which is designed to be fed through a reactor pressure wall (3). The aim of the securing device (1) is to prevent, in the most reliable manner possible, the control rod (14) from being extended in an uncontrolled manner. Furthermore, the securing device (1) should be as inexpensive as possible and should pose the slightest obstacle possible to installation work. For this purpose, the drive housing (4) has, according to the invention, at least one coupling element (9) for forming a force-locked and/or form-fit connection of the drive housing (4) to the reactor pressure wall (3).
G21C 7/12 - Moyens pour amener les éléments de commande dans la position désirée
G21C 13/036 - Raccords entre le tube et la paroi d'une enceinte, p.ex. tenant compte des contraintes thermiques le tube traversant la paroi, c. à d. s'étendant de chaque côté
F16B 7/20 - Assemblages de barres ou assemblages de tubes, p.ex. de section non circulaire, y compris les assemblages élastiques utilisant des assemblages à baïonnette
88.
PROTECTIVE SYSTEM FOR WALLS OF BUILDINGS OR CONTAINERS
The invention relates to a protective system for protecting a wall of a building or container from impact loads, having a buffer layer (3) which is arranged on the impact side of the wall of the building or container and absorbs the impact energy of the impact load predominantly by plastic deformation, wherein the buffer layer (3) comprises a deformation lattice which is formed by a substantially regular arrangement of unit cells (5) and has a number of lattice layers (6) and the intermediate spaces in which are filled with a deformable damping material (9), and wherein each unit cell (5) is composed of a plurality of lattice struts (4) which form the edges of a pyramid.
E04H 9/10 - Abris indépendants; Aménagements des murs pare-éclats indépendants
E04C 5/06 - Eléments d'armature en métal, p.ex. avec des revêtements rapportés de haute résistance à la flexion, c. à d. s'étendant essentiellement dans trois dimensions, p.ex. poutres en treillis
F41H 5/04 - Structure des plaques composées de plus d'une couche
brevets
