19results about "Facility decommissioning" patented technology

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.

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

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.

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.

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.

A volume reduction system for nuclear reactor components includes a feed unit to receive a radioactive tube from a nuclear reactor. The system also includes a segmenting unit to receive the tube from the feed unit. The segmenting unit includes a cutting element that segments the tube into segmented pieces. The system also includes a shredder unit to receive segmented pieces of the tube and shred the segmented pieces.