Abrégé

A portable internal friction measuring instrument and internal friction measurement method, the portable internal friction measuring instrument comprising: a cavity (10), a sample fixture (20), a fixing plate (30), a heating plate (40), a thermal barrier cover (50), an excitation assembly (60), and a vibration sensor (70). The excitation assembly (60) comprises a rotatable vibration impeller (61), at least one protrusion is provided on the outer wall of the vibration impeller (61), the lower edge of a sample (80) can be intermittently toggled by means of the protrusion during the rotation of the vibration impeller (61), and the vibration amplitude of the sample (80) is determined by using an angle difference between emitted light and reflected light of the sample (80), such that the technical effects of mechanical toggling to excite the vibration of the sample (80) and non-contact measurement of the vibration of the sample (80) are achieved.

Classes IPC  ?

• G01N 19/02 - Mesure du coefficient de frottement entre matériaux

Abrégé

A stress corrosion test device (1) for a grid spring (10), comprising an autoclave (2), a loader (3) and, arranged in the autoclave (2), an upper jig assembly and a lower jig assembly; the loader (3) is used for driving the upper jig assembly to move; the upper jig assembly and the lower jig assembly are respectively used for fixing a fuel cladding (9) and a grid spring (10); the lower jig assembly comprises a support plate (71) fixed to the bottom portion of the autoclave (2) and a pressing plate (72) fitting the support plate (71); the upper jig assembly comprises a clamping plate (61) and a jig plate (62), the clamping plate (61) penetrating through the fuel cladding (9) and then being fixed to the jig plate (62). The stress corrosion test device (1) for a grid spring (10) can effectively implement fixation and apply a loading condition conforming to the actual service environment of the grid spring (10) so as to simulate the actual service environment, and simulate the service state of the grid spring (10) in terms of three main stress corrosion influence factors, i.e. the material, the service environment and the stress state, thus more realistically evaluating the stress corrosion sensitivity of the grid spring (10).

Classes IPC  ?

• G01N 3/08 - Recherche des propriétés mécaniques des matériaux solides par application d'une contrainte mécanique par application d'efforts permanents de traction ou de compression
• G01N 3/18 - Exécution de tests à des températures élevées ou basses
• G01N 3/04 - Mandrins
• G01N 3/02 - Recherche des propriétés mécaniques des matériaux solides par application d'une contrainte mécanique Parties constitutives

Abrégé

A driving device for a curved top cover, a positioning checker, and a positioning and detecting method. The driving device (1) comprises: a driving mechanism (11), comprising a driving frame (111), and a driving assembly (112) mounted on the driving frame (111), wherein the bottom of the driving frame (111) is provided with a wedge assembly attached to a top surface (01); and a flexible guide mechanism (12), which is configured to move the driving mechanism (11), which is on the top surface (01), along a check channel, and comprises a winding frame (121), and a chain (122) wound on the winding frame (121), wherein a free end of the chain (122) is fixedly connected to a front end of the driving mechanism (11). By virtue of a vertical arrangement of a plane on which a motion track is located when a laser emitter (21) and the chain (122) extend out, position calibration of a probe (31) in a first channel and a second channel can be rapidly achieved, and in combination with a characteristic that a bending direction of the chain (122) is limited, a projection of a moving track of the driving mechanism (11) on a bottom surface of the top cover (0) extends along a straight line to ensure movement along the check channel, thereby ensuring that the probe (31) can be attached to the top cover (0) while moving along the check channel.

Classes IPC  ?

• G21C 17/003 - Inspection à distance des enceintes, p. ex. des cuves de pression
• G01N 33/00 - Recherche ou analyse des matériaux par des méthodes spécifiques non couvertes par les groupes

Abrégé

A vision-guided intelligent fastening bolt inspection device, comprising: a frame (11); a main buoyancy body (1), which is mounted on the frame (11) and serves as a main buoyancy source of the inspection device; propellers (3), used for controlling the movement direction of the inspection device; an ultrasonic inspection module (5); and an underwater self-stabilization moving platform (4), which comprises an upper nut sliding block (403) and a lower nut sliding block (411) which are opposite in movement direction, a balancing weight (408), and a self-stabilization driving part used for driving the upper nut sliding block (403) and the lower nut sliding block (411) to move in opposite directions, wherein the ultrasonic inspection module (5) is fixedly connected to the upper nut sliding block (403), and the balancing weight (408) is fixedly connected to the lower nut sliding block (411), or the ultrasonic inspection module (5) is fixedly connected to the lower nut sliding block (411), and the balancing weight (408) is fixedly connected to the upper nut sliding block (403).

Classes IPC  ?

• B63C 11/52 - Outillage spécialement adapté au travail sous l'eau, non prévu ailleurs
• B63G 8/16 - Commande de l'assiette ou de la profondeur par emploi direct des hélices ou d'un système à réaction
• B63G 8/26 - Dispositifs de réglage de l'assiette
• B63G 8/39 - Disposition des instruments de veille sonique, p. ex. basse fréquence, sonar

Abrégé

A flexible robot (1) with a flexible arm (2). The flexible robot comprises the flexible arm (2) and a turning structure (4) configured to drive the flexible arm (2) to turn, wherein the flexible arm (2) comprises an inner retraction portion (21) located on an inner side, and an outer extending portion (22) located on an outer side of the inner retraction portion (21); a cavity (12) is formed between the inner retraction portion (21) and the outer extending portion (22); after a medium is filled into the cavity (12), an end portion of the inner retraction portion (21) extends outwards to form the outer extending portion (22); and the turning mechanism (4) is provided at the end portion, which changes to the outer extending portion (22), of the inner retraction portion (21). With regard to the flexible robot (1), after the medium is filled into the cavity between the inner retraction portion (21) and the outer extending portion (22), the end portion of the inner retraction portion (21) extends outwards to form the outer extending portion (22), so that the flexible arm (2) continuously extends forwards, and the flexible arm (2) is driven by means of the turning mechanism (4) to turn, so that the flexible robot is applicable to the fields of endoscopy, etc., in tubes.

Classes IPC  ?

• B25J 9/14 - Manipulateurs à commande programmée caractérisés par des moyens pour régler la position des éléments manipulateurs à fluide
• B25J 9/00 - Manipulateurs à commande programmée
• A61B 1/00 - Instruments pour procéder à l'examen médical de l'intérieur des cavités ou des conduits du corps par inspection visuelle ou photographique, p. ex. endoscopesDispositions pour l'éclairage dans ces instruments

Abrégé

A method for evaluating the outdoor service life of a coating. The method comprises the following steps: calculating an ultraviolet irradiation equivalent of a coating during ultraviolet aging and a temperature and humidity aging equivalent of the coating during hygrothermal accelerated aging in each month of twelve months of one year; setting a condition for an accelerated aging test on the basis of the ultraviolet irradiation equivalent and the temperature and humidity aging equivalent in each month, taking one year as a cycle unit, and taking each month as one stage, wherein each cycle unit, i.e. one year, comprises twelve stages; and after the aging in each cycle unit ends, measuring an adhesive force of the coating, performing data fitting on a test result of the adhesive force, and thereby obtaining a service life time when the outdoor coating fails. A method for evaluating the service life of an outdoor coating is established, the theoretical basis and means for coating evaluation are improved, the data is accurately obtained, and a result is accurate.

Classes IPC  ?

• G01N 17/00 - Recherche de la résistance des matériaux aux intempéries, à la corrosion ou à la lumière

Abrégé

A portable internal friction measuring apparatus, comprising: a cavity (10), a sample fixture (20), a fixing plate (30), a heating plate (40), a thermal barrier cover (50), an excitation assembly (60), and a vibration sensor (70). The excitation assembly (60) comprises a rotatable vibration impeller (61), at least one protrusion is provided on the outer wall of the vibration impeller (61), the lower edge of a sample (80) can be intermittently toggled by means of the protrusion during the rotation of the vibration impeller (61), a light sensor is used as the vibration sensor (70), and the vibration amplitude of the sample (80) is determined by using an angle difference between emitted light and reflected light of the sample (80), such that the technical effects of mechanical toggling to excite the vibration of the sample (80) and non-contact measurement of the vibration of the sample (80) are achieved, and the internal friction measuring apparatus can be integrated in a small cavity (10) and is easy to carry. Also disclosed is an internal friction measurement method, comprising: using mechanical toggling to excite vibration, and non-contact measurement. The structure is simple, the reliability is good, the application range is wide, the measurement accuracy is high, and the working frequency is wide, and therefore, the internal friction measuring apparatus is suitable for on-site measurement of radiation defect representation.

Classes IPC  ?

• G01N 3/38 - Recherche des propriétés mécaniques des matériaux solides par application d'une contrainte mécanique en appliquant des efforts répétés ou pulsatoires engendrés par des moyens électromagnétiques
• G01N 3/317 - Recherche des propriétés mécaniques des matériaux solides par application d'une contrainte mécanique en appliquant une force unique et brève engendrée par des moyens électromagnétiques
• G01N 3/06 - Adaptations particulières des moyens d'indication ou d'enregistrement

Abrégé

Disclosed is a monitoring method for a corrosion state of a drum-type filter screen of a nuclear power plant. The method comprises the following steps: electrically connecting the positive electrode of a monitoring module to the drum-type filter screen, and electrically connecting the negative electrode of the monitoring module to a potential sensor; controlling the potential sensor to move to measurement points at different positions, so as to measure the potentials between the drum-type filter screen and the measurement points at different positions; and/or, controlling the position of the measurement point of the potential sensor to be fixed, so as to measure the potentials between different positions of the drum-type filter screen and the measurement point; and according to the measured potentials, determining the corrosion state of the drum-type filter screen. According to the monitoring method for a corrosion state of a drum-type filter screen of a nuclear power plant, the issues of safety and detection time of corrosion state detection of the drum-type filter screen of the nuclear power plant can be solved, and the detection and evaluation efficiency is improved, and meanwhile, accurate monitoring and evaluation of areas are carried out, and on-site detection and evaluation can be quickly, efficiently and safely completed.

Classes IPC  ?

• G01N 17/02 - Systèmes de mesure électro-chimique de l'action due aux intempéries, de la corrosion ou de la protection contre la corrosion
• H02J 50/10 - Circuits ou systèmes pour l'alimentation ou la distribution sans fil d'énergie électrique utilisant un couplage inductif
• H02J 7/00 - Circuits pour la charge ou la dépolarisation des batteries ou pour alimenter des charges par des batteries
• G08C 17/02 - Dispositions pour transmettre des signaux caractérisées par l'utilisation d'une voie électrique sans fil utilisant une voie radio

Abrégé

Disclosed in the present invention is a guide rail mechanism suitable for cleaning a steam generator. The guide rail mechanism comprises a first guide rail and a second guide rail which are in insertion fit with each other, and a line rail arranged on the first guide rail and the second guide rail, wherein a plurality of positioning holes are provided in the line rail, the distance between adjacent positioning holes is the same as that between adjacent heat transfer tubes in the steam generator, and the positioning holes cooperate with a proximity sensor on a cleaning mechanism, so as to achieve stepped positioning of the cleaning mechanism. The guide rail mechanism comprises a first clamping assembly and a second clamping assembly which are arranged on the first guide rail and the second guide rail, and used for clamping a left portion and a right portion, respectively, of a spreader plate in the steam generator. According to the guide rail mechanism suitable for cleaning a steam generator in the present invention, the cleaning mechanism can equidistantly move below the whole-section guide rail mechanism, and the guide rail mechanism is convenient to mount, and is structurally stable after being mounted.

Classes IPC  ?

• F28G 15/02 - Supports pour accessoires de nettoyage, p. ex. les châssis
• F22B 37/52 - Dispositifs de lavage

Abrégé

Disclosed is a multi-directional jet cleaning apparatus for a steam generator, comprising a frame assembly, and a transmission assembly, a first nozzle assembly and a second nozzle assembly disposed on the frame assembly, and a motor assembly used to drive the transmission assembly. The transmission assembly comprises a primary transmission mechanism, a secondary transmission mechanism, a second nozzle transmission mechanism, and a synchronous belt for implementing synchronous rotation of the primary transmission mechanism, the secondary transmission mechanism, and the second nozzle transmission mechanism. The motor assembly is used to drive the primary transmission mechanism to rotate. The second nozzle assembly is disposed on the second nozzle transmission assembly, and the first nozzle assembly is disposed on the primary transmission mechanism and/or the secondary transmission mechanism. The frame assembly comprises an upper cover and a lower cover, the first nozzle assembly and the second nozzle assembly being disposed on the lower cover, a water flow channel being provided in the lower cover, and the water flow channel being in communication with the second nozzle assembly and the first nozzle assembly.

Classes IPC  ?

• B08B 3/02 - Nettoyage par la force de jets ou de pulvérisations
• F28G 1/16 - Accessoires non rotatifs, p. ex. alternatifs utilisant des jets de fluide pour enlever les débris

Abrégé

A method for recognizing the type of a vortex signal of an evaporator of a nuclear power plant on the basis of an LSTM-CNN. The method comprises: calibrating data of each channel of a vortex signal; processing the calibrated data by using a time window; processing time sequence data in a differential manner; extracting time feature information of a time sequence by means of an LSTM network; a CNN network extracting local feature information of the time sequence; fusing the feature information of the LSTM network and that of the CNN network, wherein after the training and learning of a large amount of data, the feature information thereof can be represented by means of an input signal in vector form by using a triple loss principle; and constructing a defect signal feature database, representing same in vector form, comparing same to obtain the Euclidean distance between the vector feature of the input signal and the vector feature in a defect library, determining, according to the magnitude of the Euclidean distance, the category to which the signal belongs, and ultimately achieving the aim of classifying the vortex signal.

Classes IPC  ?

• G06K 9/00 - Méthodes ou dispositions pour la lecture ou la reconnaissance de caractères imprimés ou écrits ou pour la reconnaissance de formes, p.ex. d'empreintes digitales

Abrégé

An optical fiber grating high-temperature strain sensor, comprising a sensor substate (10), optical fiber mounting arms (11) provided on the sensor substrate (10), strain sensitive optical fibers (21, 22, 23), a temperature compensation optical fiber (24), bosses (14, 14'), and stretching rods (12). The sensor substrate (10) is in the shape of a circular ring, the optical fiber mounting arms (11) are formed by extending inwards along the inner circumference of the sensor substrate (10), and the optical fibers (21, 22, 23) are disposed along a diameter direction of the sensor substrate (10); the temperature compensation optical fiber (24) is used for compensation of a strain testing result; the bosses (14, 14') having different heights are provided on the sensor substrate (10); and the bosses (14, 14') are used for fixing the optical fibers (22, 23), and are used for avoiding cross contact among different optical fibers (21, 22, 23). According to the optical fiber grating high-temperature strain sensor, the influence of temperature on a strain measurement result is eliminated; design of the bosses (14, 14') on the sensor substrate (10) can effectively avoid a chirp phenomenon caused by the cross contact of FBG optical fibers (21, 22, 23); and the strain sensor has advantages of a simple structure, a small size, accurate positioning, synchronous multi-directional strain measurement, temperature compensation, high measurement accuracy, and the like.

Classes IPC  ?

• G01B 11/16 - Dispositions pour la mesure caractérisées par l'utilisation de techniques optiques pour mesurer la déformation dans un solide, p. ex. indicateur optique de déformation
• G01D 18/00 - Test ou étalonnage des appareils ou des dispositions prévus dans les groupes

Abrégé

The present application discloses a portable thermoelectric potential detector, which is small in size and easy to carry. A portable thermoelectric potential detector includes a test fixture for fixing a sample to be tested, a probe assembly unit for detecting the sample to be tested, and a collection and control unit for controlling detecting of the probe assembly and collecting a voltage signal of the probe assembly; the probe assembly unit includes two probe assemblies, each probe assembly includes a probe for loading on the surface of the sample to be tested and a linear motor for driving the probe to move and load on the surface of the sample to be tested; the collection and control unit is electrically connected to the linear motor, and is further configured to transmit a first control signal for controlling a moving distance and a loading force of the linear motor.

Classes IPC  ?

• G01R 29/12 - Mesure du champ électrostatique
• G01K 7/18 - Mesure de la température basée sur l'utilisation d'éléments électriques ou magnétiques directement sensibles à la chaleur utilisant des éléments résistifs l'élément étant une résistance linéaire, p. ex. un thermomètre à résistance de platine
• G01K 15/00 - Test ou étalonnage des thermomètres
• G01L 25/00 - Test ou étalonnage des appareils pour la mesure des forces, du couple, du travail, de la puissance ou du rendement mécanique
• G01R 19/00 - Dispositions pour procéder aux mesures de courant ou de tension ou pour en indiquer l'existence ou le signe

Abrégé

The present invention is used in the technical field of nuclear power, and provides a nuclear power plant leakage monitoring alarm method, comprising: acquiring a unit operating condition signal and, on the basis of the unit operating condition signal, determining leakage monitoring availability; if leakage monitoring is in an available state, then acquiring a processing system state signal and leakage monitoring instrument data, and determining whether the leakage monitoring data is reliable; if the leakage monitoring data is in a reliable state, then implementing leakage source positioning analysis and leakage source quantitative calculation; if the diagnostic results of the leakage source positioning analysis and the leakage rate quantitative calculation both show that a leak has occurred, and leakage response characteristics are met, then triggering a leakage alarm. Also provided in the present invention is a nuclear power plant leakage monitoring alarm system. The present invention can effectively increase the accuracy of leakage monitoring and reduce operator intervention, thereby reducing human factor faults and increasing the level of automation of leakage monitoring.

Classes IPC  ?

• 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 17/00 - SurveillanceTests
• G21D 3/06 - Dispositions de sécurité réagissant à des défaillances à l'intérieur de l'installation

Abrégé

A water sealing device of a nuclear power station pressurizer, comprising: an upper head body (10) provided with an inner surface surfacing layer (100) located at the inner side of the pressurizer, and a heat insulation layer (102) located at the outer side of the pressurizer; and a pressurizer safety valve connecting pipe (20) extending obliquely upward through the upper head body (10), the pressurizer safety valve connecting pipe (20) being provided with a safety end (200), one end of the safety end (200) being provided with a heat sleeve (202) located in the pressurizer safety valve, and the other end of the safety end being connected to a process pipe (30) of the pressurizer safety valve. The safety end (200) is provided with an elbow (40) extending obliquely downward into the pressurizer, and a tail end of the elbow (40) is vertically located above the lowest point of the inner sidewall of the elbow (40). A water sealing structure, in which the safety end (200) of the pressurizer safety valve connecting pipe (20) having the heat sleeve (202) is connected to the elbow (40), achieves water sealing by heat releasing and condensation of saturated water vapor through the pressurizer safety valve, the pressurizer safety valve connecting pipe (20) and the safety end (200), so that hydrogen leakage can be prevented, and said device has a simple structure and is easy to manufacture.

Classes IPC  ?

• G21C 1/09 - Dispositions pour la régulation de pression, c.-à-d. pressuriseurs

Abrégé

A safety-level functional control system and method for a steam atmospheric emissions system of a nuclear power plant. The safety-level functional control system comprises: three independent control columns, wherein each MSRIV is connected to a first control sub-column in the three independent control columns, each MSRCV is connected to a second control sub-column in one independent control column, and different MSRCVs are connected to different second control sub-columns. While meeting the triple redundant configuration of the steam atmospheric emissions system, the safety-level functional control system also meets the design principles of the three independent control columns, which simplifies the number of control columns of the control system, and reduces the complexity of the structure of the control system. The control function has a more centralized design, and the failure of any independent control column will at most lead to the loss of an opening function of one emissions loop in the steam atmosphere emissions system, and an isolation function of the steam atmosphere emissions system will remain unaffected and be highly reliable.

Classes IPC  ?

• F01D 17/10 - Organes de commande terminaux
• G21D 3/04 - Dispositions de sécurité

Abrégé

A nuclear power plant equipment gate connection fastening structure and fastening method therefor. The connection fastening structure comprises a sleeve flange (10) fixedly connected to a penetrating sleeve (12) pre-embedded in a containment wall body, and a shell cover flange (20) fixedly connected to a gate shell cover (22); multiple "U"-shaped holes (30) having openings facing outward are provided at the corresponding positions of the sleeve flange (10) and the shell cover flange (20) along the circumference; after the sleeve flange (10) and the shell cover flange (20) are in butt joint, the sleeve flange (10) and the shell cover flange (20) are fastened by means of an eyelet bolt component (40); the eyelet bolt component (40) comprises a detachable eyelet bolt (42), an external nut (44), and an adjustable gasket (46) sheathed onto the eyelet bolt (42). The fastening method comprises: 1) arranging orientations according to the eyelet bolt components (40) of an equipment gate, and performing bolt pre-tightening by a matched bolt tensioner, the bolt tensioner containing 2-4 combination tension heads, each combination tension head containing 2-4 tension cylinders for pre-tightening 4-16 eyelet bolt components (40) in each time; 2) during pre-tightening, symmetrically and evenly placing the combination tension heads on the eyelet bolt components (40) which are circumferentially arranged, and connecting a hydraulic pump station (83) by means of a hydraulic pipeline (82); 3) performing tension and pre-tightening operations on the eyelet bolts (42) by using hydraulic power assist after starting the hydraulic pump station (83); 4) after one set is pre-tightened in place, performing the pre-tightening operation by switching to the next set of the eyelet bolt components (40) clockwise or counterclockwise. The connection fastening structure and fastening method therefor can enable the equipment gate to be quickly opened and closed, so as to avoid some of bolts from being not mounted due to the deformation of the sleeve flange (10) and a bolt hole of the equipment from being damaged.

Classes IPC  ?

• G21C 13/028 - Joints, p. ex. pour les cuves de pression ou les enceintes de confinement

Abrégé

A nuclear power plant personnel airlock buffering device, comprising: a chuck structural member (12), fixed on a door frame (20) and comprising an electromagnetic chuck (120) and a chuck base plate (122) which are fixedly connected, sliding plates (124) being provided on the two sides of the chuck base plate (122), the electromagnetic chuck (120) and the chuck base plate (122) connected together being capable of moving up and down along the sliding plates (124), and the electromagnetic chuck (120) being connected to a power supply for controlling the power supply time of the electromagnetic chuck (120); and a suction plate structural member (14), fixed on a door plate (30) and comprising a suction plate (140), a suction plate connecting plate (142), and a door plate connecting plate (144), the suction plate (140) being fixed on the suction plate connecting plate (142), and a first spring (146) being provided between the suction plate connecting plate (142) and the door plate connecting plate (144); a first mandrel (148) penetrates through the interior of the first spring (146); one end of the first mandrel (148) is fixed to the suction plate connecting plate (142), and the other end penetrates through the door plate connecting plate (144), and then the first spring (146) is provided between the suction plate connecting plate (142) and the door plate connecting plate (144) by means of an auxiliary member; the chuck structural member (12) and the suction plate structural member (14) can be attracted to be locked or opened.

Classes IPC  ?

• E05F 5/02 - Dispositifs de freinage, p. ex. ralentisseursButéesTampons particulièrement pour éviter le claquement des battants
• E05C 19/16 - Dispositifs maintenant le battant par attraction magnétique ou électro-magnétique

Abrégé

Disclosed are a nuclear power plant digital auxiliary control panel system and design method, and a control system. The nuclear power plant digital auxiliary control panel system comprises a list establishment module (100) for acquiring a nuclear power plant running standard and historical operation running data and determining the minimum configuration function list according to the power plant running standard and the historical operation running data, and a design module (200) for classifying the minimum configuration function list and designing the minimum control panel system according to classifications. When a main digital human-machine interface fails, the monitoring and control of a nuclear power station is effectively completed by means of the provided digital auxiliary control panel system based on the minimum configuration, thereby satisfying the minimum collection required for safe running of the nuclear power station and saving on costs to the greatest extent, so that the safety and running of the nuclear power station are effectively ensured.

Classes IPC  ?

• G21D 3/00 - Commande des installations à énergie nucléaire

Abrégé

A passive condenser for a nuclear power plant, the passive condenser comprising an upper collecting tube (10) provided with multiple heat exchange tube steam inlets (100), with one end being of an open structure and the other end being of a closed structure, and with the end of an open structure being fixedly connected to a first connector (102); first flanges (12), provided with first through holes (120), are arranged at the positions of the heat exchange tube steam inlets (100) and are fixedly connected to the upper collecting tube (10), with the first through holes (120) being in communication with the heat exchange tube steam inlets (100); a lower collecting tube (20) provided with multiple heat exchange tube condensate return ports, with one end being of an open structure and the other end being of a closed structure, and with the end of an open structure being fixedly connected to a second connector (202); second flanges (22), provided with second through holes, are arranged at the positions of the heat exchange tube condensate return ports and are fixedly connected to the lower collecting tube (20), with the second through holes being in communication with the heat exchange tube condensate return ports; and a heat exchange tube bundle comprising multiple heat exchange tubes (30), wherein each of the heat exchange tubes (30) comprises an upper inclined section (300), a middle inclined section (302) and a lower inclined section (304), the upper inclined section (300) is fixedly connected to the first flange (12), and the lower inclined section (304) is fixedly connected to the second flange (22).

Classes IPC  ?

• F28B 1/02 - Condenseurs dans lesquels la vapeur d'eau ou autre vapeur est séparée de l'agent de refroidissement par des parois, p. ex. condenseur à surface utilisant l'eau ou un autre liquide comme agent de refroidissement

Abrégé

A support plate for a U-shaped heat transfer tube of a steam generator of a nuclear power plant, comprising a plate body (10). The plate body (10) is opened thereon with a plurality of three-leaf plum blossom-shaped holes (12) that penetrate the plate body (10). A hole bridge (14) is formed between two adjacent three-leaf plum blossom-shaped holes (12). The three-leaf plum blossom-shaped holes (12) comprise boss edges (120), side edges (122) and top edges (124). After U-shaped heat transfer tubes (16) are inserted into the three-leaf plum blossom-shaped holes (12), the boss edges (120) support tube walls of the U-shaped heat transfer tubes (16). The side edges (122) and the top edges (124) of the three-leaf plum blossom-shaped holes (12) and the tube walls of the U-shaped heat transfer tubes (16) enclose heat exchange fluid passages (18) at outer sides of the U-shaped heat transfer tubes (16). A tube gallery area (19) is formed at a middle portion of the plate body (10), the tube gallery area (19) is opened with a through hole (190), and the three-leaf plum blossom-shaped holes (12) are disposed at two sides of the tube gallery area (19), wherein the included angle of connection lines of centers of the three-leaf plum blossom-shaped holes (12) and side edges (122) corresponding thereto is α, and 0 <α≤ 13°. The support plate makes the U-shaped heat transfer tubes (16) more compactly arranged, and more U-shaped heat transfer tubes (16) may be arranged on the same area, such that the overall size and cost of the device may be reduced. The three-leaf plum blossom-shaped holes (12) have large heat exchange fluid flow areas, ensuring the structural continuity and strength at the weakest part of the hole bridges (14) of the support plate.

Classes IPC  ?

• F28F 9/013 - Supports auxiliaires pour les éléments pour les tubes ou les assemblages de tubes

Abrégé

A composite laser decontamination device and method for radioactive decontamination of a nuclear power plant component. The composite laser decontamination device comprises at least two laser emission modules (51, 52), beam shaping modules (61, 62) having one-to-one correspondence to the laser emission modules (51, 52), and a laser shaping module (2); laser light emitted by the laser emission module (51, 52) enters the corresponding beam shaping module (61, 62) for beam shaping and then enters the laser shaping module (2) for laser shaping, and finally is output to the surface of a to-be-decontaminated base layer (1) of the nuclear power plant component; a pulse width of the laser light emitted by the laser emission module (51, 52) is different; the particular laser emission modules (51, 52) are determined to be enabled according to the surface attachment condition of the to-be-decontaminated base layer (1). According to the novel composite laser decontamination solution for a nuclear power plant, the particular laser emission modules (51, 52) are selected to be enabled according to the condition of an actual to-be-decontaminated surface.

Classes IPC  ?

• G21F 9/30 - Traitements
• G21F 9/32 - Traitements par incinération
• G01N 21/71 - Systèmes dans lesquels le matériau analysé est excité de façon à ce qu'il émette de la lumière ou qu'il produise un changement de la longueur d'onde de la lumière incidente excité thermiquement
• G01N 21/88 - Recherche de la présence de criques, de défauts ou de souillures
• G01N 29/04 - Analyse de solides

Abrégé

Disclosed in the present invention is a portable thermoelectric potential detector, which is small in size and portable. The portable thermoelectric potential detector comprises a test clamp for fixing a sample to be tested, a probe assembly unit for detecting the sample to be tested, and an acquisition control unit for controlling probe assemblies to perform detection and acquiring voltage signals of the probe assemblies; the probe assembly unit comprises two probe assemblies; each of the probe assemblies comprises a probe for being applied on the surface of the sample to be tested and a linear motor which is used for driving the probe to move and being applied on the surface of the sample to be tested; an output end of the linear motor is connected to the probe; and the acquisition control unit is electrically connected to the linear motors respectively and is further used for sending, to the linear motors, a first control signal for controlling the movement distances of the linear motors and the forces applied by the linear motors.

Classes IPC  ?

• G01R 19/00 - Dispositions pour procéder aux mesures de courant ou de tension ou pour en indiquer l'existence ou le signe

Abrégé

A mobile emergency cooling apparatus (1) for a spent fuel pool of a nuclear power plant, comprising a power device (10), a circulating cooling pump (12), and a cooling device (14). The power device (10), the circulating cooling pump (12), and the cooling device (14) are connected in sequence, and are provided on a same mobile carrying platform (15). The inlet of the circulating cooling pump (12) is connected, by means of an inlet pipeline (16), to a water guide pipeline (18) connected to a water outlet of a primary cooling system (3) of a spent fuel pool (2). The outlet of the circulating cooling pump (12) is connected to the inlet of the cooling device (14). The outlet of the cooling device (14) is connected to a water return pipeline (22) by means of an outlet pipeline (20) to return cooled pool water to the spent fuel pool (2). A backflow pipeline (24) is connected between the outlet pipeline (20) and the inlet pipeline (16). Compared with the prior art, the mobile emergency cooling apparatus (1) for a spent fuel pool of a nuclear power plant integrates the power device (10), the circulating cooling pump (12), and the cooling device (14) onto the mobile carrying platform (15), the device integrity and usability of the mobile emergency cooling apparatus (1) can be improved. By connecting the backflow pipeline (24) between the outlet pipeline (20) and the inlet pipeline (16), the cooling device (14) is not easy to foul and implements a good cooling effect.

Classes IPC  ?

• G21D 1/02 - Dispositions d'équipement auxiliaire
• G21F 9/34 - Moyens de se débarrasser des résidus solides

Abrégé

A nuclear power plant reactor control rod driving mechanism comprising a pressure-resistant housing component (100), a hook component (200), a driving rod component (300), a coil component (400), and a rod position detector component (500), where the pressure-resistant housing component (100) is an integrated housing, the top part thereof is a blind pipe structure, and the bottom part is removably and hermetically mounted via a thread on a CRDM pipe base (700) of a pressure vessel top cover. The pressure-resistant housing component (100) has no welded seam thereon, is sealed with the CRDM pipe base (700) by employing a threaded connection and via a pair of sealing rings (103), and effectively reduces the risks of reactor coolant leakage.

Classes IPC  ?

• G21C 7/12 - Moyens pour amener les éléments de commande dans la position désirée

Abrégé

A passive parking sealing device (30) for a nuclear reactor coolant pump. The passive parking sealing device (30) comprises a complete sealing ring (40) that can be in a starting position and a non-starting position, and a complete limit ring (50) that softens when a state conversion temperature is reached. When the limit ring is in a temperature below at a state conversion temperature, the sealing ring surrounds in the circumferential direction of a pump shaft (18) of a nuclear reactor coolant pump and maintains a clearance with the pump shaft under the support of the limit ring. When the limit ring is in the state conversion temperature or in a temperature higher than the state conversion temperature, the limit ring is softened or melted, and the sealing ring loses the support of the limit ring and tightly holds the pump shaft, so as to prevent the reactor coolant from flowing along the pump shaft. The passive parking sealing device for a nuclear reactor coolant pump is only provided with a sealing ring providing the sealing effect and a limit ring providing the limit function, the movement of the sealing ring from the non-starting position to the starting position does not depend on external force, and the entire sealing has the advantages: the structure is simple and the sealing is reliable.

Classes IPC  ?

• F04D 29/12 - Joints d'étanchéité pour arbre utilisant des bagues

Abrégé

A non-destructive assessment method for the radiation damage of a reactor pressure vessel in a nuclear power plant, comprising the following steps: S01, monitoring in real time magnetic performance parameters of a certain monitored part of the steel of a reactor pressure vessel during a normal operation period of a nuclear power plant, the magnetic performance parameters being any one from among magnetic susceptibility χ, residual magnetization MR and coercivity HC; S02, on the basis of the measured magnetic performance parameters, calculating neutron radiation damage fluence Φ or mechanical properties of the reactor pressure vessel; S03, using the neutron radiation damage fluence Φ or the mechanical properties as analysis input parameters, performing safety assessment or service life prediction for the structural integrity of the reactor pressure vessel during a radiation damage process. The method may achieve real-time repeated non-destructive measurement, while data is accurate and test operations are safe; the present invention may simultaneously monitor the degree of radiation damage at multiple positions of the reactor pressure vessel.

Classes IPC  ?

• G21C 17/003 - Inspection à distance des enceintes, p. ex. des cuves de pression

Abrégé

An ultimate heat sink system utilized in a nuclear power plant comprises at least one non-safe series used by a non-safe user (200), and at least one safe series (A, B) used by a safe user (100, 110, 120). The non-safe series and the safe series (A, B) comprise water cooling systems and water supply systems. Each of the water supply systems comprises a cooling pump set (500, 510) and a heat exchange set (400, 410). The water supply system in each series comprises a set of a cooling pool (700, 710) and a cooling tower (600, 610). The cooling pool (700, 710) is located at the upstream of the cooling pump set (500, 510), and the cooling pump set (500, 510) is connected to a water outlet of the heat exchange set (400, 410) and the cooling pool (700, 710), respectively. A water supply pool (800) communicating with an external water area is provided at the upstream of the cooling pool (700, 710). The cooling pool (700, 710) of each series communicates with a respective water supply pool (800). The ultimate heat sink system provides a highly reliable water source to a power plant, employs the atmosphere as the ultimate heat sink to maximally reduce the impact of an external hydrological and meteorological condition change, thereby achieving goals of a strong capability of resisting an external extreme condition, a simple system configuration, and low operation and maintenance costs.

Classes IPC  ?

• G21D 1/02 - Dispositions d'équipement auxiliaire
• G21D 3/06 - Dispositions de sécurité réagissant à des défaillances à l'intérieur de l'installation

Abrégé

A nuclear power plant spent fuel storage and transportation metal tank comprises a metal tank (1) and a fuel basket (2) detachably accommodated in the metal tank. The metal tank (1) comprises: a housing (10); a base (12) hermetically sealed and fixed at a bottom portion of the housing (10); a top cover (14) hermetically sealed and fixed at a top portion of the housing (10); and a redundant top cover (16) hermetically sealed and fixed on the housing (10). In comparison to the prior art, the nuclear power plant spent fuel storage and transportation metal tank resolves issues of safe storage of spent fuel and post-transportation of the spent fuel, realizing long-term safe storage and transportation of the spent fuel. In addition, since that the fuel basket (2) is detachably accommodated in the metal tank, the fuel basket (2) can be used for loading fuel frames having different structures, providing universality.

Classes IPC  ?

• G21F 5/008 - Récipients pour éléments combustibles
• G21F 5/06 - Détails ou accessoires des récipients
• G21C 19/06 - Moyens pour supporter ou emmagasiner des éléments combustibles ou des éléments de commande

Abrégé

Disclosed is a degassing device for gaseous impurities in radioactive waste liquid of a reactor of a nuclear power plant, comprising: a degassing tower (10) used for receiving the radioactive waste liquid of the reactor of the nuclear power plant and removing the gas dissolved in the waste liquid, and the degassing tower (10) being equipped with a tower top gas outlet (102) and a tower kettle liquid outlet (104); a condenser (20) communicating with the degassing tower (10) and located at the downstream side of the degassing tower, and the condenser being used for condensing the gas extracted from the top of the degassing tower (10); a vacuum pump (30) communicating with the condenser (20) and used for pumping and compressing the gas condensed by the condenser (20) and the uncondensed water vapor and maintaining the running pressure required by the interior of the tower; and a gas-water separator (30) communicating with the vacuum pump (30) and used for separating gas from water and removing the gas. Moreover, further disclosed is a degassing method for gaseous impurities in radioactive waste liquid of a reactor of a nuclear power plant. According to the degassing device and method for gaseous impurities in radioactive waste liquid of a reactor of a nuclear power plant, negative pressure degassing is adopted, the operation is convenient, safe and reliable, and system safety can be guaranteed even if system leakage occurs.

Classes IPC  ?

• G21F 9/02 - Traitement des gaz
• G21F 9/06 - Traitements

Abrégé

A method and system for evaluating a safety state of a nuclear power plant, and a nuclear power plant device. The method for evaluating a safety state of a nuclear power plant comprises: acquiring operating states of all nuclear power plant safety parameters in a pre-established nuclear power plant safety parameter logical relationship model (S101); according to a pre-set safety evaluation rule and safety levels for the nuclear power plant safety parameters, evaluating the safety levels of the operating states of all the acquired nuclear power plant safety parameters so as to acquire the safety levels of all the nuclear power plant safety parameters (S102); and carrying out logical operation processing on the acquired safety levels of all the nuclear power plant safety parameters according to a safety parameter logical relationship in the established nuclear power plant safety parameter logical relationship model so as to acquire a safety level of the overall safety state of a nuclear power plant (S103). The method improves the convenience, accuracy and reliability of nuclear power plant safety state evaluation, and improves the safety and reliability of a nuclear power plant.

Classes IPC  ?

• G06Q 10/06 - Ressources, gestion de tâches, des ressources humaines ou de projetsPlanification d’entreprise ou d’organisationModélisation d’entreprise ou d’organisation

Abrégé

A steam generator water level warning method and device are provided. The method comprises: obtaining real-time data of a steam generator water level and a key parameter (S101); detecting whether the key parameter meets a preset key parameter warning condition (S102); if the key parameter meets the key parameter warning condition, receiving an input steam generator water level control instruction by means of an operation interface of a steam generator water level control main interface (S103); performing faster-than-real-time simulation on the steam generator water level by means of a preset faster-than-real-time acceleration mode, the real-time data, and the steam generator water level control instruction, to obtain an operation effect of the steam generator water level in advance (S104); and predetermining, according to the operation effect, effectiveness of the steam generator water level control instruction (S105). The method and device of the present invention predetermine the effectiveness of the steam generator water level control instruction by means of an acceleration function, providing a theoretical basis for an operator to implement a correct operation.

Classes IPC  ?

• G21D 3/00 - Commande des installations à énergie nucléaire

Abrégé

Disclosed is an internally installed refuelling water storage tank for a nuclear-power-plant containment. The tank comprises an inner-circulation water tank (10) located between a nuclear-power-plant reactor pit (41) and a secondary shielding wall (42), and a load-bearing floorslab (20) located above the inner-circulation water tank (10). The load-bearing floorslab (20) is provided with an inner-circulation water return hole (200). An inner-circulation retention basket (30) corresponding to the inner-circulation water return hole (200) is arranged inside the inner-circulation water tank (10). An inner-circulation backflow buffering pool (32) is provided between the inner-circulation water return hole (200) and the inner-circulation retention basket (30). An annular space (40) is provided between the secondary shielding wall (42) and a nuclear-power-plant containment (44). An outer-circulation water tank (60) is arranged below a floorslab of the annular space (40). The outer-circulation water tank (60) is in communication with the annular space (40) via an outer-circulation water return hole (90). An outer-circulation retention basket (70) corresponding to the outer-circulation water return hole (90) is arranged inside the outer-circulation water tank (60). The outer-circulation water tank (60) is in communication with the inner-circulation water tank (10) via a channel (80). By means of arranging the outer-circulation water tank (60) of the refuelling water storage tank inside the containment (44), the volume of the internal refuelling water storage tank for a containment increases, and the depth of water decreases, thereby improving the earthquake resistance capacity of a reactor pit plant. The inner-circulation backflow buffering pool (32) can significantly reduce the impact force to which the inner-circulation retention basket (30) is subjected, thereby reducing the device design difficulty and costs.

Classes IPC  ?

• G21C 13/02 - Enceintes sous pressionEnceintes d'enveloppeEnveloppes en général Détails
• G21C 15/18 - Dispositions pour le refroidissement d'urgenceMise hors circuit de la chaleur

Abrégé

A main pump shaft seal water injection system of a nuclear power plant includes a jet pump, a high pressure cooler, a hydrocyclone, valves and a main connection pipeline outside of a main pump, and an auxiliary pump and an internal flow path inside the main pump. Inner and outer flow paths of the main pump are connected with a shaft seal water injection hole and a high temperature water drainage hole. The main connection pipeline is connected between an upper filling water pipeline and a shaft seal water injection hole. A bypass pipeline connected with the jet pump, the high pressure cooler and the hydrocyclone, the main connection pipeline is provided with a normally open main pipeline isolating valve. The bypass pipeline allows low temperature upper filling water in the RCV system to enter the shaft seal water injection hole of the main flange directly.

Classes IPC  ?

• G21D 1/04 - Dispositions de pompage
• G21D 1/02 - Dispositions d'équipement auxiliaire
• F04D 29/10 - Joints d'étanchéité pour arbre
• F16J 15/16 - Joints d'étanchéité entre deux surfaces mobiles l'une par rapport à l'autre
• F16J 15/34 - Joints d'étanchéité entre deux surfaces mobiles l'une par rapport à l'autre par bague glissante pressée contre la face plus ou moins radiale d'une des deux parties

Abrégé

Disclosed is an arrangement structure of a main building of a single-reactor nuclear island of a nuclear power plant. The arrangement structure comprises a reactor building (1) located in the centre of the main building of the nuclear island, three adjacent rows of safety buildings (2, 3, 4) arranged to surround the reactor building (1) from one side of the reactor building (1) and to be connected to the reactor building (1), as well as a fuel building (5) and a nuclear auxiliary building (6) which are arranged to surround the reactor building (1) from the other side of the reactor building (1). The arrangement of the main building of the single-reactor nuclear island of the nuclear power plant is compact, and has an excellent anti-seismic performance.

Classes IPC  ?

• E04H 5/02 - Bâtiments ou groupes de bâtiments à des fins industrielles, p. ex. pour centrales énergétiques ou usines
• G21D 1/00 - Détails des installations à énergie nucléaire
• G21D 1/02 - Dispositions d'équipement auxiliaire

Abrégé

A passive pH value adjusting system and method for long-term water source of a reactor of a nuclear power plant in case of serious accidents. The pH value adjusting system comprises: a containment vessel (60); and a reactor pressure container (10), a fragment intercepting apparatus (20), a water return pipe (30), and a room (40) provided with an overflow port (404) on the sidewall and a pH value adjusting basket (402) at the bottom, and a built-in refueling pool (50) communicated with the room (40) by means of the overflow port (404), wherein the reactor pressure container (10), the fragment intercepting apparatus (20), the return pipe (30), the room (40), and the built-in refueling pool (50) are provided inside the containment vessel (60). After a serious accident occurs, the pH value adjusting system passively adds a chemical agent into a water source in the built-in refueling pool by using the circular water flow formed when a safety injection system injects water into the reactor for cooling, to adjust the pH value of the water source without devices such as an external power supply and safety-level storage battery in a nuclear power plant. Therefore, the pH value adjusting system has simple and reliable structure.

Classes IPC  ?

• G21C 15/08 - 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 provenant du matériau modérateur
• G21C 9/00 - Dispositions pour la protection d'urgence structurellement associées avec le réacteur

Abrégé

A nuclear power plant reactor pressure vessel and shielding wall combination structure. The combination structure comprises a reactor pit shielding wall (10), a reactor pit (20) formed by the reactor pit shielding wall (10) in an enclosed manner, a reactor pressure vessel (30) disposed in the reactor pit (20), and a thermal insulation layer (34) disposed outside the reactor pressure vessel (30). Up-and-down-through flow channels are respectively disposed between the thermal insulation layer (34) and the reactor pressure vessel (30) and between the thermal insulation layer (34) and the reactor pit shielding wall (10). A reactor pit water injection pipeline (18) is disposed at the lower part of the reactor pit shielding wall (10) in a penetration manner. An accommodation space (120) is disposed on the inner wall of the upper part of the reactor pit shielding wall (10). A flow return path (124) for communicating the accommodation space (120) with a bottom space of the reactor pit is disposed in the reactor pit shielding wall (10). In the combination structure, the flow return path is disposed in the reactor pit shielding wall to ensure saturated water entrained by steam can smoothly flow back into the reactor pit, so that a stable natural circulation can be formed between a rising flow path and the flow return path in the reactor pit to ensure that the reactor pressure vessel can be continuously and rapidly cooled under severe accident working conditions.

Classes IPC  ?

• G21C 15/18 - Dispositions pour le refroidissement d'urgenceMise hors circuit de la chaleur

Abrégé

The present invention provides a compound mobile communication method for a nuclear power plant, including the steps of: receiving a communication signal sent by a base station in a restricted area or an unrestricted area, the communication signal including a coded-modulation optical signal and/or an electromagnetic wave signal; judging the communication signal received; and reducing transmission power or not transmitting the electromagnetic wave signal if the communication signal is a coded-modulation optical signal or a wireless electromagnetic wave communication signal sent by a base station in the restricted area. The compound mobile communication method for a nuclear power plant of the present invention can meet the requirements of mobile communication in special places without electromagnetic interference. The present invention also provides a compound mobile communication terminal and system for a nuclear power plant.

Classes IPC  ?

• H04W 52/28 - Commande de puissance d'émission [TPC Transmission power control] le TPC étant effectué selon des paramètres spécifiques utilisant le profil utilisateur, p. ex. la vitesse, la priorité ou l'état du réseau, p. ex. en attente, libre ou absence de transmission
• H04M 1/725 - Téléphones sans fil
• H04M 1/737 - Téléphones sans fil caractérisés par une transmission d'ondes électromagnétiques autres que des ondes hertziennes, p. ex. d'ondes infrarouges
• H04M 3/42 - Systèmes fournissant des fonctions ou des services particuliers aux abonnés
• H04W 48/04 - Restriction d'accès effectuée dans des conditions spécifiques sur la base des données de localisation ou de mobilité de l'utilisateur ou du terminal, p. ex. du sens ou de la vitesse de déplacement
• H04B 10/40 - Émetteurs-récepteurs
• H04B 10/50 - Émetteurs
• H04B 10/60 - Récepteurs

Abrégé

A nuclear reactor coolant system main circuit arrangement structure, comprising: a reactor building, a pressure vessel (30), a steam generator (36), a pressure regulator, a main pump (38) and main pipeline (32), the reactor building being provided therein with a raft foundation. The pressure vessel (30) is installed in the reactor building, and is disposed above the raft foundation. The main pipeline (32) is connected between the pressure vessel (30), the steam generator (36), and the main pump (38) to form a main circuit, with the pressure regulator arranged on the main pipeline (32). A height difference L between the center of the main pipeline (32) connected to the pressure vessel (30) and an upper surface of the raft foundation in the reactor building is 9.7-10.8 m. Compared to the prior art, the present application adopts a sunken arrangement of the main circuit, and therefore can increase reactor fuel module seismic acceleration resistance to 0.3 g or more without making large adjustments to a reactor fuel module structure configuration, thereby improving the seismic acceleration resistance capability of the reactor, and satisfying internationally-recognized third generation nuclear reactor technology anti-earthquake requirements.

Classes IPC  ?

• G21C 15/00 - Dispositions pour le refroidissement à l'intérieur de l'enceinte sous pression contenant le cœurEmploi de réfrigérants spécifiques
• G21C 15/18 - Dispositions pour le refroidissement d'urgenceMise hors circuit de la chaleur
• 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
• G21D 1/00 - Détails des installations à énergie nucléaire

Abrégé

A method for measuring the hydrogen concentration in a containment vessel of a nuclear power station and a corresponding measurement apparatus and system. The method comprises: provide a hydrogen measurement component (501) coated with a palladium-silver alloy membrane in a containment vessel of a nuclear power station; a processor cabinet (503) collects a conductivity signal of the hydrogen measurement component (501) after hydrogen absorption and release; the processing cabinet (503) determines the hydrogen concentration in the containment vessel of the nuclear power station according to the collected conductivity signal and a pressure signal in the containment vessel of the nuclear power station. The method for measuring the hydrogen concentration in a containment vessel of a nuclear power station can achieve safe and accurate measurement of the hydrogen concentration in the containment vessel of the nuclear power station.

Classes IPC  ?

• 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
• 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

Abrégé

A coordinated control method for a nuclear power station reactor. The method comprises: receiving an electric power signal of a steam turbine of a nuclear power station (101); acquiring load information of the steam turbine on the basis of the electric power signal (103); detecting, on the basis of the load information of the steam turbine, whether or not the steam turbine has reached a load of 96% Pn (105); and, if the steam turbine is detected to have reached a load of 96% Pn, then triggering the steam turbine to enter a "reactor pressure control" mode (107). Also disclosed is a piece of coordinated control equipment for the nuclear power station reactor.

Classes IPC  ?

• G21D 3/12 - Régulation de différents paramètres dans l'installation par ajustement du réacteur en réponse uniquement aux changements se produisant dans la demande du moteur
• F01D 17/00 - Régulation ou commande par variation de flux

Abrégé

A diversity drive method for a nuclear power plant. The method comprises: acquiring parameter information about various processes in the operation of a nuclear power plant; comparing the parameter information about various processes with a preset corresponding setting value; and if the parameter information about a process exceeds the corresponding setting value, outputting a signal to drive the execution of an automatic function, the automatic function comprising an emergency shutdown scram function, an automatic tripping function of a steam turbine, an automatic start function of a safety injection, an automatic start function of an auxiliary water supply, an automatic isolation function of main steam, an automatic isolation function of a main water supply, and an automatic pump tripping function of a reactor coolant pump.

Classes IPC  ?

• G21D 3/04 - Dispositions de sécurité
• G21D 3/08 - Régulation de différents paramètres dans l'installation

Abrégé

A nondestructive detection robot for a pressure vessel (1) of a nuclear reactor, and a detection method therefor. The robot comprises multiple supporting legs (22), multiple mechanical arms (25a, 25b, 25c, 25d), and a main rotating joint (23). Two ends of each supporting leg (22) are separately connected onto a stand column assembly (21) and the pressure vessel (1), so that an axis line of the stand column assembly (21) coincides with an axis line of the pressure vessel (1). The multiple mechanical arms (25a, 25b, 25c, 25d) are configured to scan and check multiple groups of probe assemblies (24a, 24b, 24c, 24d) of the components. The main rotating joint (23) can be rotationally connected to the lower part of the stand column assembly (21) in the axial direction of the stand column assembly (21). The second mechanical arm (25b) is rotationally connected, by means of an oscillating joint (26), to the main rotating joint (23) in the direction perpendicular to the axial direction of the stand column assembly (21). The other mechanical arms are detachably connected to the main rotating joint (23).

Classes IPC  ?

• G21C 17/00 - SurveillanceTests

Abrégé

Disclosed is a compound mobile communication method for a nuclear power plant. The method comprises: receiving a communication signal which is sent by a base station in a restricted area or an unrestricted area, the communication signal comprising a coded-modulation optical signal and/or an electromagnetic wave signal; judging the received communication signal; and if the communication signal is the coded-modulation optical signal or a radio electromagnetic wave communication signal which is sent by the base station in the restricted area, reducing transmission power, or not transmitting the electromagnetic wave signal. By means of the compound mobile communication method for a nuclear power plant of the present invention, the requirement of mobile communication on the premise of avoiding electromagnetic interference in a special place can be achieved. In addition, also disclosed are a compound mobile communication terminal and system for a nuclear power plant.

Classes IPC  ?

• H04W 48/02 - Restriction d'accès effectuée dans des conditions spécifiques

Abrégé

A method of producing a sheet of B 4C/AL neutron absorbent material by continuous cast rolling, the method comprising the following steps: 1) providing B 4C particulate and aluminum matrix melt, adding the B 4C particulate into the aluminum matrix melt while mixing the composite; 2) applying an electromagnetic field to the B 4C particulate-containing aluminum matrix melt passing through a headbox; 3) applying ultrasonic vibration to the B 4C particulate-containing aluminum matrix melt passing through a casting nozzle; and 4) conducing double-roller continuous cast rolling on the B 4C particulate-containing aluminum matrix melt passing out of the casting nozzle to obtain a B 4C/AL neutron absorbent material sheet. The method uses double-roller continuous cast rolling under coupled ultrasonic and electromagnetic oscillation to rapidly cool and refine the grains of the solidified composite material, ensuring uniform distribution of B 4C particles without separation.

Classes IPC  ?

• C22C 32/00 - Alliages non ferreux contenant entre 5 et 50% en poids d'oxydes, de carbures, de borures, de nitrures, de siliciures ou d'autres composés métalliques, p. ex. oxynitrures, sulfures, qu'ils soient soient ajoutés comme tels ou formés in situ
• C22C 21/00 - Alliages à base d'aluminium
• C22C 1/10 - Alliages contenant des composants non métalliques
• B21B 1/46 - Méthodes de laminage ou laminoirs pour la fabrication des produits semi-finis de section pleine ou de profilésSéquence des opérations dans les trains de laminoirsInstallation d'une usine de laminage, p. ex. groupement de cagesSuccession des passes ou des alternances de passes pour laminer du métal immédiatement après la coulée continue