摘要:
A device for separating a shielding slab for a heavy water reactor according to an embodiment includes: a body; a circular rail installed on at least one side of the body; and a decommissioner for decommissioning a shielding slab installed on the circular rail and installed on an inner wall of a heavy water reactor, wherein the decommissioner includes a decommission head moving on the circular rail, a separator installed in the decommission head and separating and desalinizing the shielding slab, and a gripper installed in the decommission head and gripping the separated shielding slab.
摘要:
An exemplary embodiment of the present invention provides an apparatus for dismantling for heavy water reactor facilities, including: a cutting device configured to divide a calandria of the heavy water reactor facilities into a main shell and a sub-shell; and a transfer device configured to draw the main shell cut by the cutting device to the outside, wherein the transfer device includes a fixing unit configured to fix the calandria; and a transfer unit configured to transfer the fixing unit.
摘要:
A decommissioning method of biological shielding concrete of a nuclear power plant according to an exemplary embodiment includes: decommissioning a neutron detector positioning device installed to biological shielding concrete surrounding a nuclear reactor to form a plurality of penetrated parts in the biological shielding concrete; inserting a part of a cutting device into the plurality of penetrated parts; and decomposing the biological shielding concrete into a plurality of sub-concrete parts by using the cutting device.
摘要:
Disclosed herein are a treatment apparatus and method for a waste steam generator, and an installation method of a treatment apparatus for a waste steam generator. The treatment apparatus includes a cutting part for cutting a body of a waste steam generator, a driving part for driving the cutting part, and a support frame for supporting the cutting part and the driving part, wherein the support frame is coupled to an outer peripheral surface of the body of the waste steam generator in a divided state, and the cutting part is driven and cuts the body in a state in which the support frame is coupled to the outer peripheral surface of the body. Consequently, since the treatment apparatus is easily moved and installed, an installation time of the treatment apparatus may be shortened and an exposure time of a worker can be reduced.
摘要:
A method of decommissioning a nuclear reactor including a vessel defining an inner chamber and reactor internal components positioned within the inner chamber includes removing at least some of the internal components and repackaging at least some of the removed internal components in at least one of the first and second predefined sections of the vessel defining a cutting zone between the at least first and second predefined sections. The method further includes disposing the vessel in a container, and encapsulating the internal components in the vessel and encapsulating the vessel in the container to generate a package. A package including components from a decommissioned and dismantled nuclear reactor includes a vessel and a plurality of components encapsulated in the vessel.
摘要:
A mobile system for intervention in an atmosphere of radioactive gas, notably tritium, which includes: a dynamic confinement device, including a removable confinement barrier to surround an intervention zone and a device for controlled extraction of air to keep the zone at a lower pressure than the exterior; a device for monitoring the radioactive gas concentration in the air of the zone; a device to detect and signal the exceedance of a predefined threshold by this concentration to the persons present in the zone.
摘要:
A method for recycling AgInCd control rod absorber bar material from a used control rod from a nuclear power plant includes sectioning AgInCd absorber bar from a used control rod into a first section and a second section, the first section having a higher radioactivity than the second section; and recycling the material of the second section of the AgInCd absorber bar.
摘要:
Systems and methods for dismantling a nuclear reactor are described. In one aspect the system includes a remotely controlled heavy manipulator (“manipulator”) operatively coupled to a support structure, and a control station in a non-contaminated portion of a workspace. The support structure provides the manipulator with top down access into a bioshield of a nuclear reactor. At least one computing device in the control station provides remote control to perform operations including: (a) dismantling, using the manipulator, a graphite moderator, concrete walls, and a ceiling of the bioshield, the manipulator being provided with automated access to all internal portions of the bioshield; (b) loading, using the manipulator, contaminated graphite blocks from the graphite core and other components from the bioshield into one or more waste containers; and (c) dispersing, using the manipulator, dust suppression and contamination fixing spray to contaminated matter.
摘要:
The invention relates to an optimized laser cutting method for cutting a part from a material by means of a cutting system comprising: a laser source for producing a laser beam having a certain power; and a cutting head comprising an end nozzle for passage of a cutting laser beam, wherein the method comprises: determining a cutting power Pd such that Pd=Max(Popt;λe) where Max is the mathematical operator of the maximum, Popt is an optimal power of the laser beam of the cutting system, which is predetermined in accordance with the part to be cut, and/or with cutting parameters and/or with system parameters, in order to minimize the amount of aerosols produced when the part is cut, λ is a leading coefficient representing the number of kW required for cutting the part per mm of the thickness of the part, and e is the thickness of the part in mm.
摘要:
According to an embodiment, a radioactivity evaluation method has: a first input step; a selection step in which the calculating section selects a representative neutron energy spectrum and a representative neutron fluence rate; a second input step; an radioactivity calculating step in which the calculating section calculates quantities of the radioactivity that correspond to the representative neutron energy spectra and the representative neutron fluence rates; a data storing step; a nuclide-by-nuclide radioactivation reaction rate calculating step in which the calculating section calculates a radioactivation reaction rate of each nuclide based on the neutron energy spectra at the position of each of the object sections; an object-by-object adding-up step; a nuclide determining step; and an object position determining step.