33results about "Facility decommissioning" patented technology

A cutting device and method for cutting a plurality of parallel fingers of at least one core component in a plane orthogonal to the longitudinal axis of the fingers, the fingers being adapted to be introduced into the fuel assembly of a nuclear reactor core. The cutting device includes: a first bearing plate including a plurality of abutments respectively for a finger to be cut. The cutting device also includes a rotatable cutting plate including a corresponding cutting blade for each abutment in the first bearing plate, the rotatable cutting plate being rotatable about a rotating axis between a starting position and a final position in a circumferential direction, the first bearing plate and the cutting plate being parallel to each other, the cutting blades including a plurality of groups of cutting blades. For each group of cutting blades the angle between the cutting blades and the corresponding abutments is different to an angle between the cutting blades and the corresponding abutments of any other group of cutting blades.

A structural panel (1) for a modular containment system (20). The structural panel (1) comprises a flat rectangular panel (2) having a front side (3), a rear side (4), and four edges (5); four side panels (6), each extending rearwardly from a different one of the four edges (5) perpendicular to the rear side (4) of the rectangular flat panel (2), each having a front edge affixed to the rectangular flat panel (2) and a rear edge; and four rear tabs (8), each extending inwardly from a rear edge of a different one of the four side panels (6), and being parallel to the rear side (4) of the flat panel (2). A modular containment system (20) constructed of a plurality of structural panels (1) is also provided. The modular containment system (20) is formed by affixing the structural panels (1) to one another.

The application belongs to the field of coolant purification of nuclear power plants, and particularly relates to a coolant circulating purification system and method applied to nuclear power plants. The system comprises: a primary coolant storage system cation exchanger, a primary coolant storage system anion exchanger, a primary coolant storage system resin collector, a primary coolant treatment system cation exchanger, a primary coolant treatment system anion exchanger, and a primary coolant treatment system resin collector. A third bypass is arranged in front of the inlet of the primary coolant treatment system cation exchanger, and a valve is arranged in the third bypass to connect to a position after the inlet of the primary coolant storage system cation exchanger. The application can effectively improve the reliability of the primary coolant treatment system in purifying the coolant, and can switch the primary coolant storage system ion exchanger to operate in the case of failure of the primary coolant treatment system ion exchanger.

A dismantling and decontamination system of biodegradable concrete of a nuclear power plant according to an exemplary embodiment includes: a dismantling device for dismantling an in-core instrument installed under biodegradable concrete to form a lower penetrated part of the biodegradable concrete; a decontamination device inserted inside the biodegradable concrete for decontaminating radioactive waste of the inner wall of the biodegradable concrete; a waste receiving device movable through the lower penetrated part of the biodegradable concrete; and a blocking device for blocking the upper opening of the biodegradable concrete to block an outflow of the radioactive dust.

Disclosed is a method for dismantling a D2O tank of a heavy water reactor installed on an inner wall of a containment building and surrounded by a concrete structure, the method including cutting and opening a front surface of the concrete structure so as to dismantle the D2O tank, descending the D2O Tank by using an dedicated dismantling apparatus, and taking the D2O tank out of the containment building by using a crane, and a dismantling apparatus.

An apparatus for cutting a curved wall of a structure, of the present invention, may comprise; a guide rail mounted on a curved wall of a structure; a chain mounted on the guide rail; a support plate supported by the guide rail so as to be movable by means of a plurality of rollers; a body case coupled to the support plate; a sprocket mounted at the body case so as to rotate while engaged with the chain; a driving motor mounted in the body case so as to rotate the sprocket; a cutting blade rotatably mounted at the front of the body case; and cutting motor mounted in the body case so as to rotate the cutting blade.

A module for use in a robot-deployable modular accessibility system. The module includes a block, an attachment portion, and a gripping portion. The attachment portion is configured to attach the module to another module. The gripping portion is configured to enable a robot to grip and handle the module. The robot-deployable modular accessibility system includes a plurality of modules. The plurality of modules is configured to be assembled by the robot to form a structure. Also, a method of assembling the robot-deployable modular accessibility system by a robot.

The invention relates to a modular ventilation system for a building, comprising: - at least one first extraction module comprising a first casing and at least one air extraction unit disposed inside the first casing, the air extraction unit being adapted to draw air from outside the first casing via the first air inlet opening and to inject the drawn air towards the first air outlet opening, and - at least one second filtration module comprising a second casing and at least one filtration unit disposed inside the second casing, the air filtration unit being adapted to filter air coming from the second air inlet opening, the filtered air being discharged towards the second air outlet opening, the modular ventilation system being configured to be able to selectively adopt a functional configuration and a storage and / or transport configuration. Figure for the abstract: Fig. 6

Disclosed is a method for dismantling metal equipment of a heat transport system in a containment building at a nuclear power plant, the metal equipment including a heat transport pump, a steam generator, a pressurizer, a condenser, and a D2O tank, including: a first dismantling step of dismantling the heat transport pump; a second dismantling step of dismantling the steam generator after the first dismantling step; a third dismantling step of dismantling the pressurizer after the second dismantling step; and a fourth dismantling step of dismantling the condenser and the D2O tank after the third dismantling step.

Disclosed is a method for dismantling a D20 tank of a heavy water reactor installed on an inner wall of a containment building and surrounded by a concrete structure, the method including cutting and opening a front surface of the concrete structure so as to dismantle the D20 tank, descending the D20 Tank by using an dedicated dismantling apparatus, and taking the D20 tank out of the containment building by using a crane, and a dismantling apparatus.

A nuclear instrument removal system (NIRS) for use with processing a nuclear instrument is provided. The NIRS includes a control system and an instrument processing system configured for use with the control system. The instrument processing system includes a counter module configured to receive the nuclear instrument, a feed and cut module removably coupled to the counter module and configured to receive the nuclear instrument after passing through the counter module, and a spool module removably coupled to the feed and cut module and configured to be mounted to a cask assembly. The spool module includes a spool canister and a drive shaft associated with the canister. The drive shaft is configured to rotate about an axis in order to spool a cold portion of the nuclear instrument within the canister.

Method (100) for carrying out a release process of a, in particular at least partially radioactive, measured material (10), comprising the following steps: - Recording (111) preliminary activity data (11) of the sample (10) depending on a preliminary investigation (110), - Preparation of the preliminary evaluation (112) of the preliminary investigation (110) of the measured material (10), - Planning (113) a subsequent part of the release process depending on the preliminary evaluation (112) and on a method of carrying out a decision measurement (140) for the release (150) of the measured item (10), - Performing the decision measurement (140) in a clearance measurement facility (1), wherein the decision measurement (140) is carried out using the method in which a detection (141) and an evaluation (142) of a radioactive activity distribution in the measured material (10) is carried out, wherein the preparation of the preliminary evaluation (112) of the measured material (10) is carried out taking into account the preliminary activity data (11) with regard to a specification criterion (111.1) for specifying at least a part of the release process by the measured material (10), wherein the release process begins with the dismantling of the measured material (10) in a nuclear facility (8), wherein the preliminary investigation (110) takes place in the nuclear facility (8) to record (112) the preliminary activity data (11).

There are provided a nuclear power plant dismantling method and apparatus. The nuclear power plant dismantling method includes: selecting a nuclear reactor to be dismantled; and performing nuclear power plant dismantling work on the nuclear reactor through a nuclear reactor dismantling apparatus, wherein the nuclear reactor dismantling apparatus includes: a frame unit shielding the nuclear reactor to prevent contaminants in the nuclear reactor from being released to the outside; a cutting module provided on the frame unit and performing cutting work on the nuclear reactor; a link fixing module having a hollow area formed therein, entering an internal space of the nuclear reactor to link the frame unit and the nuclear reactor with each other, and having a bar shape; and a purging module entering the hollow area of the link fixing module and performing purging on the inside of the nuclear reactor in order to secure safety in the cutting work.

A module (102) for a robotically deployable modular passage system (100) is described herein. The module (104) includes a block body (104), an attachment portion (106), and a grip portion (108). The attachment portion (106) is configured to attach the module (102) to another module (102). The gripping portion (108) is configured to enable a robot to grip and process the module (104). The robotically deployable modular passage system (100) includes a plurality of modules. The plurality of modules are configured to be assembled by the robot to form a structure. A method (500) of assembling a robotically deployable modular traffic system (100) by a robot is also described herein.

The present invention essentially comprises the steps of disassembling and removing all components of the primary circuit except for the LWR reactor vessel, which is essentially emptied and neutralized, and subsequently replacing some of these components with sub-assemblies each composed of an integrated SMR reactor and a concrete / metal hybrid structure, where this concrete / metal hybrid structure is also used as a reactor pit for the SMR reactor, which is preferably filled with water, and fixing the SMR inside the reactor building and contributing to a third containment barrier, preferably while minimizing damage to the infrastructure of the reactor building. The present invention is related to a method for retrofitting a nuclear power plant.

A structural panel 1 suitable for a modular containment system, in which the structural panel comprises: a flat rectangular panel 2 with a front side 3 and a rear side 4 and four edges 5; four side pa

There are provided a nuclear power plant dismantling method and apparatus. The nuclear power plant dismantling method includes: selecting a nuclear reactor to be dismantled; and performing nuclear power plant dismantling work on the nuclear reactor through a nuclear reactor dismantling apparatus, wherein the nuclear reactor dismantling apparatus includes: a frame unit shielding the nuclear reactor to prevent contaminants in the nuclear reactor from being released to the outside; a cutting module provided on the frame unit and performing cutting work on the nuclear reactor; a link fixing module having a hollow area formed therein, entering an internal space of the nuclear reactor to link the frame unit and the nuclear reactor with each other, and having a bar shape; and a purging module entering the hollow area of the link fixing module and performing purging on the inside of the nuclear reactor in order to secure safety in the cutting work.

A wire saw apparatus comprises: a first pulley system from which a wire is withdrawn toward a structure to be cut; a second pulley system into which the wire is introduced from the structure; a first dust collection pipe unit provided to surround the wire between an end part at which surrounding of the structure by the wire ends and a part at which the wire is introduced into the first pulley system; and a second dust collection pipe unit provided to surround the wire between a start part at which surrounding of the structure by the wire starts and a part at which the wire is withdrawn from the second pulley system.

An apparatus comprises a cell with one or more wall panels, a floor, a ceiling, and one or more openings. The cell contains one or more components comprising a dexterous manipulator with at least one articulating robotic arm and a manipulator carriage. The manipulator carriage is coupled to rails and may traverse the cell length. The cell contains a boom with a proximal end, a distal end, and articulating links comprising two or more segments that fold back onto each other within the cell or extend partially or fully through one of the one or more cell openings. The cell also contains a boom carriage (coupled to the proximal end of the boom), boom rails, and a base. The boom carriage may traverse the boom rails in the cell or remain fixed to the base. One or more end effectors are coupled to the distal end of the boom.

The invention concerns a method for removing a vessel (10) from a cavity (30), the vessel (10) comprising a vessel shell (12) with a peripheral wall (14). The method comprises the following steps: a) arranging at least one robot system (36) on an upper edge (18) of the peripheral wall (14), b) cutting a plurality of segments (44) from a first horizontal portion (22A) of the peripheral wall (14) by means of a cutting tool (38) of the robot system (36) and removing the cut segments (44), c) arranging the robot system (36) on the upper edge (24B-D) of a next horizontal portion (22B-D) of the vessel shell (14), and d) repeating the second step (102) and the third step (103) for each horizontal portions (22B-D) of the peripheral wall (14).

Described herein is a module (102) for use in a robot-deployable modular accessibility system (100). The module 104 includes a block (104), an attachment portion (106), and a gripping portion (108). The attachment portion (106) is configured to attach the module (102) to another module (102). The gripping portion (108) is configured to enable a robot to grip and handle the module (104). The robot-deployable modular accessibility system (100) includes a plurality of modules. The plurality of modules is configured to be assembled by the robot to form a structure. Also described herein is a method (500) of assembling the robot-deployable modular accessibility system (100) by a robot.

A dismantling and decontamination system of bioprotective concrete of a nuclear power plant according to an exemplary embodiment includes: a dismantling device for dismantling an in-core instrument installed under bioprotective concrete to form a lower penetrated part of the bioprotective concrete; a decontamination device inserted inside the bioprotective concrete for decontaminating radioactive waste of the inner wall of the bioprotective concrete; a waste receiving device movable through the lower penetrated part of the bioprotective concrete; and a blocking device for blocking the upper opening of the bioprotective concrete to block an outflow of the radioactive dust.

Disclosed are a remote-controlled dismantling robot and dismantling method for nuclear facility decommissioning, relating to the technical field of nuclear facility decommissioning. The robot includes a tracked chassis, a hydraulic arm, a hydraulic system, and a quick change mechanism for hydraulic tool head, where the tracked chassis includes a vehicle chassis, a rotating mechanism, track systems, and support leg systems; and the hydraulic arm includes a multi-stage hinged arm and arm oil cylinder. The robot can dismantle to-be-decommissioned nuclear facilities under human remote control, which can decrease the radiation dose to the operators.

The present invention relates to a method for cutting a nuclear reactor and inserting cut materials, the method comprising the steps of: preparing cut materials by cutting a nuclear reactor through a plurality of processes; classifying the cut materials into a plurality of stack shapes; and inserting the cut materials into a packaging container according to the stack shapes, wherein the packaging container includes an external container, an internal container and a cover, and the inserting step includes the steps of: preparing the external container; accommodating the internal container in the external container; and mounting the cover on the upper portion of the internal container.

The invention relates to a detection system (2) for detecting radioactive radiation, in particular in a room (4) of a nuclear facility undergoing decommissioning, comprising a detector (6) for measuring radioactive radiation, a position determination device (8) that can be arranged on the detector (6) for determining an exact position of the detector (6) within the room (4), wherein the position determination device (8) comprises an angle determination unit (10) for manually determining the angular orientation of the detector (6) within the room (4).

A structural panel for a modular containment system. The structural panel includes a flat rectangular panel having a front side, a rear side, and four edges; four side panels, each extending rearwardly from a different one of the four edges perpendicular to the rear side of the rectangular flat panel, each having a front edge affixed to the rectangular flat panel and a rear edge; and four rear tabs, each extending inwardly from a rear edge of a different one of the four side panels, and being parallel to the rear side of the flat panel. A modular containment system constructed of a plurality of structural panels is also provided. The modular containment system is formed by affixing the structural panels to one another.

A system for manufacturing, installing, operating, and maintaining at least first and second transportable nuclear power plants. The system includes a first deployment site adapted to receive placement of the first transportable nuclear power plant therein and a second deployment site adapted to receive placement of the second transportable nuclear power plant therein. A first small modular reactor is disposed in the first transportable nuclear power plant. The first small modular reactor is adapted to receive a first nuclear fuel. A second small modular reactor is disposed in the second transportable nuclear power plant. The second small modular reactor is adapted to receive a second nuclear fuel. A special purpose facility is adapted to support the first and second transportable nuclear power plants. The special purpose facility is disposed at a third deployment site that differs from the first deployment site and from the second deployment site.

According to an example aspect of the present invention, there is provided a method for sampling a solid object, the method comprising: providing a solid object; treating the solid object mechanically to remove material, such as pulverized material, from the solid object; and aspirating the removed material through a solids separation system, thereby separating one or more solid fractions from said material.

Disclosed is a method for dismantling metal equipment of a heat transport system in a containment building at a nuclear power plant, the metal equipment including a heat transport pump, a steam generator, a pressurizer, a condenser, and a D2O tank, including: a first dismantling step of dismantling the heat transport pump; a second dismantling step of dismantling the steam generator after the first dismantling step; a third dismantling step of dismantling the pressurizer after the second dismantling step; and a fourth dismantling step of dismantling the condenser and the D2O tank after the third dismantling step.

The invention discloses a method and a system for judging the shutdown time of a main pump in a shutdown oxidation stage of a nuclear power plant, a computer readable storage medium and electronic equipment. The method comprises the following steps: acquiring nuclide activity data at each time point in the shutdown oxidation stage, which is measured by radiation monitoring equipment mounted on a plurality of monitoring points of a chemical and volume control system; on the basis of the nuclide activity data of the multiple monitoring points, standardized activity values of all time points in the shutdown oxidation period of the chemical and volume control system are obtained through calculation; the standardized activity value in the shutdown oxidation process is recorded, and an evaluation result of the activity change trend is generated; and based on the evaluation result, generating and outputting a judgment result of continuous operation or shutdown of the main pump. According to the method, dynamic and quantitative trend evaluation is carried out on the oxidation process, so that judgment on the outage time of the main pump is realized.