Patent classifications
G21D1/003
Safety cover structure usable in dismantling operations at nuclear facility
A safety cover structure of a nuclear facility is disclosed. The safety cover structure includes: a cover portion rotatably installed on a body protection concrete slab to cover a cavity where a reactor pressure container is located; a driving portion configured to rotate the cover portion relative to the cavity; an opening and closing portion that is installed on the cover portion and is configured to allow materials resulting from cutting and dismantling of the reactor pressure container to move therethrough; a fire extinguishing portion configured to extinguish a fire generated inside the cover portion; a dose sensor installed in the cover portion and configured to measure a radiation dose emitted from the reactor pressure container; and an alarm portion configured to receive a sensing signal from the dose sensor and provide an alarm when the measured radiation dose exceeds a predetermined value.
METHOD OF DETERMINING CONDITIONS FOR ACCOMMODATING RADIOACTIVE WASTE IN CONTAINER, RADIOACTIVE WASTE ACCOMMODATING METHOD, AND WASTE BODY PRODUCED USING SAID METHOD
A container accommodation condition determination method of determining an accommodation condition for accommodating a plurality of waste pieces, obtained by at least cutting radioactive waste, into at least one storage container, for obtaining at least one waste body by accommodating the plurality of waste pieces into the at least one storage container, includes: a step of, assuming, for each of a plurality of arrangement condition candidates specifying the storage container in which each of the waste pieces is to be stored and an accommodation position inside the storage container, that the waste pieces are arranged inside the storage container in accordance with the arrangement condition candidate, selecting at least one of the arrangement condition candidates which satisfy a limiting condition required for the waste body in each of the storage containers; a step of calculating a necessary storage container number which is the number of the storage container required to accommodate the plurality of waste pieces in accordance with the selected arrangement condition candidate; and a step of specifying the arrangement condition candidate such that the necessary storage container number is minimum.
MACHINE FOR CUTTING NOZZLES OF REACTOR VESSELS
Disclosed herein is a machine for cutting nozzles of reactor vessels. The machine for cutting nozzles of reactor vessels comprises a cutting unit positioned at an upper surface edge of a reactor vessel having a nozzle and having a saw blade part having different contact areas to cut the nozzle, a drive unit providing the saw blade part with rotary power, and a foreign substance suction unit provided at one end of the cutting unit in contiguity with the saw blade part to suck foreign substances generated when the nozzle is cut by the saw blade part, wherein the foreign substance suction unit sucks the foreign substances by approaching an outer peripheral surface of the nozzle when the saw blade part moves in a cutting direction of the nozzle.
Method and an installation for cutting up a mass of reinforced concrete
Disclosed are examples of methods and systems for cutting up a reinforced concrete mass, in which a drilling tool is provided. In various embodiments, the drilling tool comprises: a drill tube carrying a cutter member; a device for causing the drill tube to vibrate, the device comprising a vibration generator for generating longitudinal vibration in the drill tube; a device for injecting a drilling fluid at the distal end of the drill tube; and a device for moving the drill tube along its longitudinal direction. In the disclosed methods and systems, the reinforced concrete mass is cut up by drilling at least one hole with the help of the drill tool by causing the drill tube to vibrate while injecting the drilling fluid into the mass from the distal end of the drill tube.
Device and method for removing contaminated material
The present invention relates to a device (10) and a method for removing contaminated material from a wall, the device (10) comprising suction plates (26) which fix a support system (13) of the device (10) to the wall by means of negative pressure, and a first rotating tool (14) that has impact cutters (16) in the circumferential direction. Disc-shaped saw blades (20) are provided in a second rotating tool (18) mounted upstream of the first rotating tool (14) in the working direction.
ARC SAW BLADES
Arc saw blades and systems and methods for segmenting components utilizing improved arc saw blades.
Apparatus and method for volume reduction for nuclear decommissioning and refurbishment
An apparatus for volume reduction of material removed from a hazardous environment. The apparatus includes a shielded housing for receiving a workpiece therein, at least one cutting unit having a cutting head operable for contactless cutting, and a drive unit for rotating the at least one cutting unit around a main axis so the cutting head cuts the workpiece.
Nuclear dismantling apparatus and method
A nuclear dismantling system for dismantling equipment contaminated with radioactive contamination, including a dismantling apparatus to be operated remotely while in a nuclear facility and a control system communicatively coupled to the dismantling apparatus to control the dismantling apparatus remotely.
APPARATUS AND METHOD FOR SIMULATION OF DISMANTLING OPERATION OF NUCLEAR FACILITY
The present invention relates to a simulation of a nuclear facility dismantling operation, comprising: a database which includes information on at least one task constituting a nuclear facility dismantling operation and information on a virtual space related to the simulation of the dismantling operation; a plurality of head mounted displays (HMDs) which receives inputs of users related to the simulation; a simulation unit which generates the virtual space, transmits to the plurality of HMDs, the image of the virtual space including operator objects corresponding to each of the users of the plurality of HMDs, and processes the simulation of the dismantling operation according to the inputs received from each HMD user, wherein, when simulations which are different in at least one of the number of the users and the progress order of the tasks are processed, the simulation unit compares the simulations on the basis of at least one of the number of the users or the progress order of the tasks and displays a comparison result.
Method for decommissioning nuclear facility
A method for decommissioning a nuclear facility includes: floating a nuclear reactor pressure vessel above a cavity; positioning a mounting device on bio-protective concrete to cover the cavity with the mounting device; mounting a lower portion of the nuclear reactor pressure vessel on the mounting device; and cutting and decommissioning the nuclear reactor pressure vessel mounted on the mounting device.