System and method for removing a calandria vessel from a nuclear reactor

Abstract

This invention provides a method for partitioning a pipe container within a reactor cavity of a nuclear reactor. The method includes: providing at least one cutting tool; cutting a portion of the reactor cavity to form an opening; forming a shielded space defined by a shielding wall, the reactor cavity, and end shields of the pipe container, the shielding wall being configured to absorb radiation from within the shielded space; partitioning the shell and internal components of the pipe container within the shielded space; and removing the shell and internal components of the pipe container from the shielded space. Optionally, filler, such as concrete, can be used to secure the pipe container. Once the shell and internal components of the pipe container are removed, the end shields can be partitioned or removed from the reactor cavity, and the end shields can be transported intact by positioning the tube sheet portions of each end shield abutting against each other.

Description

[0001] Cross-reference to related applications and application for preference This application claims priority to U.S. Provisional Patent Application No. 63 / 602,540, filed November 24, 2023, the entire contents of which are incorporated herein by reference. Technical Field

[0002] This disclosure generally relates to the decommissioning of nuclear reactors, and more specifically, to the removal of end-of-life pipe containers. Background Technology

[0003] Nuclear reactors have a limited operational lifespan. For example, second-generation CANDU... TM The type 2 reactor (“Canadian heavy water uranium”) is designed to operate for approximately 25 to 30 years. After that, the nuclear reactor can be decommissioned under certain conditions. The nuclear reactor decommissioning process involves the removal of numerous reactor components and includes various other activities such as shutting down the reactor, preparing the reactor cavity, installing material handling equipment, and various platform and equipment supports. The removal process may also include removing the closure plug and locating hardware components, disconnecting feeder assemblies, cutting bellows, removing end fittings, releasing and removing pipe inserts, cutting and removing pressure lines, removing pipes, and removing the pipe container. Many of the removed components may be radioactive and require special handling. Summary of the Invention

[0004] In one aspect, this disclosure describes a method for partitioning a pipe container within a reactor cavity of a nuclear reactor, the method comprising: providing at least one cutting tool; cutting a portion of the reactor cavity with one of the at least one cutting tool to form an opening; forming a shielded space defined by a shielding wall, the reactor cavity, and end shields of the pipe container, the shielding wall being configured to absorb radiation from within the shielded space, optionally, the shielding wall covering the opening; partitioning the shell and internal components of the pipe container within the shielded space; and removing the shell and internal components of the pipe container from the shielded space.

[0005] In one embodiment, the method includes: removing the shielded ball bearing from between the end shield and the pipe container side tube sheet; splitting the pipe container side tube sheet; removing the grid tube from the end shield; and splitting the end shield. The method may include: filling the pipe container with filler to support the pipe container and absorb radiation; wherein a portion of the cavity cut by at least one cutting tool is a reactive platform. Alternatively, the method may include: filling a portion of the shielded space and the pipe container with filler to support the pipe container and absorb radiation emitted by the pipe container; splitting the end shield within the shielded space, wherein the shielding wall includes shielding blocks defining the surface of the end shield; and removing the end shield from the shielded space. In one embodiment, the filler is lightweight concrete with a dried density of not less than 800 kg / m³ and not more than 2000 kg / m³. In another embodiment, splitting the shell and internal components of the pipe container within the shielded space includes: peeling the pipe container shell from the filler; and splitting the internal components.

[0006] In one embodiment, the method includes: positioning a transport aircraft below a pipe container; and using the transport aircraft to remove the shell and internal components of the pipe container from the shielded space.

[0007] In one embodiment, the method includes decoupling an end shield from a reactor cavity; and positioning one end shield on top of another end shield on a transport aircraft. The method may further include positioning one end shield on top of the other end shield by positioning a tube sheet portion of one end shield against a tube sheet portion of the other end shield.

[0008] In one embodiment, the method includes inserting at least one cutting channel through a pipe container, each of the at least one cutting channel defining a space for receiving one of at least one cutting tools; filling a portion of the shielded space and the pipe container with filler to support the pipe container and absorb radiation emitted by the pipe container, optionally, the filler is concrete; cutting a portion of the cavity with at least one cutting tool to form an opening, wherein the portion of the cavity is a reactive mechanism platform; and dividing the end shield within the shielded space. The filler may be lightweight concrete with a dried density in the range of 800 kg / m³ to 2000 kg / m³.

[0009] The method according to any one of claims 13, wherein at least one cutting tool comprises a wire cutting tool having a cutting line extending into a cutting channel, the method comprising cutting through the cutting channel and the filler.

[0010] In one embodiment, the method includes drilling a core opening in the packing material along a core opening axis; inserting at least one cutting tool into at least one cutting channel; cutting at least one of the packing material and the manifold container along a first plane connecting the core opening axis and the axis of one of the at least one cutting channels; and cutting at least one of the packing material and the manifold container laterally from the axis of one of the at least one cutting channels to define a second plane, the first and second planes intersecting to divide a portion of the packing material. In one embodiment, the portion has a substantially quadrilateral cross-section. In another embodiment, cutting at least one of the packing material and the manifold container laterally from at least one cutting channel may include: inserting a cutting tool into a first grid tube; and cutting at least one of the packing material and the manifold container along a second plane intersecting the first and second grid tubes. In another embodiment, cutting at least one of the packing material and the manifold container laterally from at least one cutting channel may include: cutting the packing material between adjacent fuel channels, wherein the second plane does not intersect the grid tubes of the manifold container.

[0011] In one embodiment, the method includes inserting at least one cutting tool into a cutting channel to divide the pipe container, the internal components of the pipe container, and the end shield.

[0012] Implementation methods may include combinations of the above features.

[0013] In another aspect, this disclosure describes a method for removing a pipe container from the reactor cavity of a nuclear reactor, the method comprising: providing at least one cutting tool; cutting a portion of the reactor cavity with the at least one cutting tool; positioning the pipe container on a transport aircraft; removing the pipe container from the reactor cavity; positioning a shielding liner over the shell of the pipe container; and filling the shielding liner with filler to secure the pipe container within the liner.

[0014] In one implementation, the filler is concrete.

[0015] In one embodiment, the method includes: positioning a first portion of a shielding liner on a transport vehicle before the pipe container is positioned on the transport vehicle; positioning a second portion of the shielding liner on the pipe container after the pipe container is positioned on the transport vehicle; and coupling the first and second portions of the shielding liner to confine the pipe container within the shielding liner.

[0016] Implementation methods may include combinations of the above features.

[0017] In another aspect, this disclosure describes a method for partitioning a pipe container within a reactor cavity. The method includes: providing at least one cutting tool; sealing each of a plurality of grid tubes in the reactor cavity with a sealing member; forming a shielded space defined by end shields of the reactor cavity and the pipe container; filling a portion of the shielded space with water to immerse the pipe container; cutting a portion of the reactive platform with at least one cutting tool to form an opening; partitioning the pipe container, internal components of the pipe container, and the tube sheet of the end shield within the water-filled space of the shielded space; and removing the pipe container, internal components of the pipe container, and the tube sheet of the end shield from the reactor cavity.

[0018] In one embodiment, the sealing member is at least one of a plug and a welded plate.

[0019] In one implementation, the tube sheet is a pipe container side tube sheet.

[0020] In one embodiment, the method includes removing water and splitting end shielding.

[0021] In one embodiment, the tube sheet for splitting the pipe container, the internal components of the pipe container, and the end shield includes: providing a box configured to receive split nuclear components of a nuclear reactor, the box having a plurality of openings for drainage; positioning a split portion of at least one of the pipe container, the internal components of the pipe container, and the end shield within the box; positioning a shield above the box, the shield being configured to receive the box and provide radiation shielding for the split components within the box; lifting the box out of water; draining water from the box; drying the split components; and positioning the dried split components into a container for transport to an external storage facility.

[0022] Implementation methods may include combinations of the above features.

[0023] In another aspect, this disclosure describes a system for handling radioactive waste. The system includes: a crane configured to move a container into and out of a reactor cavity filled with water; a container configured to receive fragmented nuclear components of the reactor, the container defining at least one opening for drainage; a shielding enclosure configured to receive the container and provide radiation shielding for the fragmented components within the container; a dryer configured to evaporate water from the fragmented components; and a container for transporting the fragmented components from the dryer.

[0024] In one embodiment, the dryer is at least one of an infrared heater, a blackbody radiation heater, a resistance heater, and a convection heater.

[0025] Implementation methods may include combinations of the above features.

[0026] Further details of these and other aspects of the subject matter of this application will become apparent from the detailed embodiments and accompanying drawings included below. Attached Figure Description

[0027] Now refer to the attached diagram, in which: Figure 1 It is CANDU TM A three-dimensional view of a type of reactor.

[0028] Figure 2A It is CANDU TM Cross-sectional view of the fuel channel assembly of a nuclear reactor.

[0029] Figure 2B It is based on the adjacent CANDU of the implementation method TM A perspective view of the end face platform, workbench, and pipe insert removal tool of the reactor.

[0030] Figure 3 An exemplary cutting tool is inserted. Figure 1 A schematic diagram of the piping container of the reactor shown.

[0031] Figure 4 This is a schematic diagram of an exemplary method for dismantling a nuclear reactor.

[0032] Figure 5A This is a front view of an exemplary pipe container wrapped in an outer packaging. Figure 5B yes Figure 5A The exemplary pipe container shown is a side view encased in an outer packaging.

[0033] Figure 6 This is a schematic diagram of another exemplary method for dismantling a nuclear reactor.

[0034] Figure 7 This is a schematic diagram of another exemplary method for dismantling a nuclear reactor.

[0035] Figure 8 This is a schematic diagram of another exemplary method for dismantling a nuclear reactor.

[0036] Figure 9 This is an elevation view of an exemplary end shield stacked on a transport aircraft.

[0037] Figure 10 This is a schematic diagram of another exemplary method for dismantling a nuclear reactor.

[0038] Figure 11A It is a frontal cross-sectional view of the piping container inside the reactor cavity of a nuclear reactor. Figure 11B yes Figure 11A The diagram shows a side cross-sectional view of the piping container inside the reactor cavity of a nuclear reactor.

[0039] Figure 12 yes Figure 11A The diagram shows a side cross-sectional view of the piping container inside the reactor cavity of a nuclear reactor, with a portion of the cavity removed.

[0040] Figure 13A yes Figure 11A The diagram shows a frontal cross-sectional view of the pipe container inside the reactor cavity, revealing a cut in the pipe container shell. Figure 13B yes Figure 13A The diagram shows a side cross-sectional view of the piping container inside the reactor cavity of a nuclear reactor.

[0041] Figure 14 yes Figure 13A The diagram shows a frontal cross-sectional view of the piping container inside the reactor cavity, illustrating the division of the piping container shell.

[0042] Figure 15A This is after the casing of the pipe container has been removed. Figure 14 The diagram shows a side cross-sectional view of the piping container inside the reactor cavity of a nuclear reactor. Figure 15B yes Figure 15A The diagram shows a side cross-sectional view of the pipe container inside the reactor cavity, with part of the central shield removed.

[0043] Figure 16 A schematic diagram illustrating another exemplary method for dismantling a nuclear reactor is shown.

[0044] Figure 17 The diagram shows a side cross-sectional view of the pipe container inside the reactor cavity of a nuclear reactor, with the cut channel 16 installed vertically through the pipe container 10.

[0045] Figure 18A This shows a frontal cross-sectional view of the piping container inside the reactor cavity of a nuclear reactor. Figure 11B yes Figure 18A The diagram shows a side cross-sectional view of the piping container inside the reactor cavity. Figure 11C is... Figure 18A The diagram shows a side cross-sectional view of the piping container inside the reactor cavity, including the core section within the cavity.

[0046] Figure 19A Showing Figure 18A The diagram shows a frontal cross-sectional view of the pipe container inside the reactor cavity, with the reactive platform removed.

[0047] Figure 19B yes Figure 19A A partial enlarged view of an exemplary segmented portion of the pipe container shown.

[0048] Figure 19C yes Figure 19AA partially enlarged view of another exemplary segmented portion of the pipe container shown.

[0049] Figure 19D An exemplary cutting tool is shown outside the pipe container.

[0050] Figure 19E The movement path of an exemplary cutting tool and waste container truck is shown.

[0051] Figure 20 A schematic diagram illustrating another exemplary method for dismantling a nuclear reactor is shown.

[0052] Figure 21 An exemplary system for drying and packaging radioactive waste is shown. Detailed Implementation

[0053] Before providing a detailed description of any implementation, it should be understood that this disclosure is not limited to its application in the construction details and component arrangements described below or shown in the accompanying drawings. This disclosure may be implemented or carried out in other ways.

[0054] limited Although terms such as “maximize,” “minimize,” and “optimize” may be used in this disclosure, it should be understood that such terms may be used to refer to improvement, adjustment, and refinement, and are not strictly limited to maximum, minimum, or optimal.

[0055] The term “connection” or “coupled to” can include direct coupling (where two elements are coupled to and in contact with each other) and indirect coupling (where at least one additional element is located between the two elements).

[0056] The term “substantially” as used in this application may be used to modify any quantitative description which may vary within permissible limits without altering its relevant essential function.

[0057] Terms such as “up to,” “at least,” “greater than,” “less than,” “more than,” or “or above” include the numbers mentioned, and such terms indicate a range that can be further subdivided into sub-ranges. In the same manner, all ratios described in this application also include all sub-ratios falling within the wider range of ratios.

[0058] Unless the context clearly specifies otherwise, the singular forms of “a,” “an,” and “the” include the plural meaning. The term “and / or” refers to any one, any combination of, or all of the items associated with this term.

[0059] The term "about" may refer to a range of variation of ±5%, ±10%, ±20%, or ±25% of the specified value. For example, "about 50%" may represent a range of variation of 45% to 55% in some embodiments. For integer ranges, the term "about" may include one or two integers greater than and / or less than the mentioned integer at each end of the range. Unless otherwise stated in this application, the term "about" is intended to include values ​​and ranges that are close to the mentioned range and are functionally equivalent in construction or implementation.

[0060] “Radioactive waste,” “radioactive materials,” and “radioactive components” include “low-level radioactive waste (LLW) and intermediate-level radioactive waste (ILW).

[0061] The term "low-level radioactive waste (LLW)" refers to radioactive waste with a dose rate of less than 10 mSv / h (1 rem / h) at 30 cm (unshielded). LLW consists of low-level radioactive material contaminated with radionuclides.

[0062] In terminology, horizontal radioactive waste (ILW) refers to radioactive waste with a dose rate greater than or equal to 10 mSv / h (1 rem / h) at 30 cm (unshielded). ILW mainly consists of used reactor core components, ion exchange columns, resins, and filters used to maintain the cleanliness of the reactor water system. ILW has higher radioactivity than LLW and requires shielding during handling to protect personnel.

[0063] The various embodiments are described with reference to the accompanying drawings.

[0064] Figure 1 It is CANDU TM A perspective view of the reactor core of reactor type 6. The reactor core is typically housed within a cavity sealed by a gaslock for radiation control and shielding. Although this disclosure specifically refers to CANDU for convenience... TM The CANDU reactor type 6 provides explanations of various aspects, but this disclosure is not limited to CANDU. TM This type of reactor, while potentially useful outside this specific field, is essentially a cylindrical container (called a CANDU). TM The pipe container 10 of the reactor type 6 contains heavy water moderator. The pipe container 10 has an annular shell 14 and tube sheets 18 at a first end 22 and a second end 24. The tube sheet 18 includes a plurality of orifices (referred to as orifices 19 in this application), each orifice receiving a fuel passage assembly 28. Figure 1 As shown, several fuel passage assemblies 28 extend from the first end 22 through the tube sheet 18 of the pipe container 10 to the second end 24.

[0065] like Figure 1 and Figure 2AIn some embodiments shown, the reactor core has two walls at each of its ends 22, 24: an inner wall defined by a tube sheet 18 (also referred to as a pipe container side tube sheet) at each end 22, 24 of the reactor core, and an outer wall 64 (often referred to as an "end shield" or "refueling machine side tube sheet") located at a distance outside the tube sheet 18 at each end 22, 24 of the reactor core. A grid tube 65 spans the distance between the tube sheet 18 and the end shield 64 at each pair of holes 19 (i.e., holes in the tube sheet 18 and the end shield 64, respectively).

[0066] Figure 2A yes Figure 1 A cross-sectional view of a fuel channel assembly 28 of the reactor core is shown. Figure 2A As shown, each fuel passage assembly 28 includes a tube bundle (“CT”) 32 surrounding other components of the fuel passage assembly 28. Each CT 32 spans the distance between tube sheets 18. Furthermore, the opposite ends of each CT 32 are received and sealed within respective orifices 19 in the tube sheets 18. In some embodiments, roll-fitted connectors (e.g., tube bundle inserts 34) are used to secure the CT 32 to the tube sheet 18 within the orifices 19. Pressure tubes (“PT”) 36 form the inner wall of the fuel passage assembly 28. PT 36 provides conduit for reactor coolant and fuel rod bundles or assemblies 40. For example, PT 36 typically accommodates two or more fuel assemblies 40 and serves as conduit for reactor coolant flow through each fuel assembly 40. An annular space 44 is defined by the gap between each PT 36 and its corresponding CT 32. The annular space 44 is typically filled with a circulating gas, such as dry carbon dioxide, helium, nitrogen, air, or a mixture thereof. One or more annular spacers or ring springs 48 are arranged between CT 32 and PT 36. The annular spacers 48 maintain the gap between PT 36 and the corresponding CT 32, while allowing annular gas to pass through and flow around the annular spacers 48.

[0067] Just like Figure 2A As shown, each end of each fuel passage assembly 28 is provided with an end fitting assembly 50 located outside the corresponding tube sheet 18. Each end fitting assembly 50 includes an end fitting body 57 and an end fitting liner 58. At the end of each end fitting assembly 50 is a sealing plug 52. Each end fitting assembly 50 also includes a feeder assembly 54. The feeder assembly 54 supplies reactor coolant to or removes reactor coolant from the PT 36 via a feeder pipe 59. Figure 1 Specifically, for a single fuel channel assembly 28, the feeder assembly 54 at one end of the fuel channel assembly 28 serves as an inlet feeder, while the feeder assembly 54 at the opposite end of the fuel channel assembly 28 serves as an outlet feeder. Figure 2AAs shown, the feeder assembly 54 can be attached to the end fitting assembly 50 using a coupling assembly 56, which includes a plurality of screws, gaskets, seals, and / or other types of connectors. A grid tube 65 (as described above) covers the connection between the end fitting assembly 50 and the PT 36 housing the fuel assembly 40. Shielded ball bearings 66 and cooling water surround the exterior of the grid tube 65, providing additional radiation shielding.

[0068] Positioning hardware assembly 60 and bellows 62 are also coupled to each end fitting assembly 50. Bellows 62 enables axial movement of fuel passage assembly 28—a capability important in situations where fuel passage assembly 28 undergoes length changes over time (common in many reactors). Positioning hardware assembly 60 can be used to set the end of fuel passage assembly 28 to a locked or unlocked configuration with a fixed axial position. Positioning hardware assembly 60 is also coupled to end shield 64. Each illustrated positioning hardware assembly 60 includes a rod with an end received in a bore in its respective end shield 64. In some embodiments, the rod end and the bore in the end shield 64 are threaded. Similarly, it should be understood that, although in Figures 1-2A CANDU was shown in TM This invention pertains to type 1 reactors, but it can also be applied to other types of reactors, including those with [specific characteristics]. Figures 1-2A The reactor has components similar to those shown.

[0069] Figure 2B One embodiment of a heavy-duty workbench (“HWT”) 96 is shown, wherein the heavy-duty workbench 96 is mounted on a tool platform (“RTP”) 95 and adjacent to end 24 of the nuclear reactor. A similar HWT may be mounted adjacent to end 22 of the nuclear reactor. The HWT 96 and any tools mounted on the HWT are controlled via a control station (not shown).

[0070] like Figure 3 As shown, the pipe container cutting tool 100 is mounted on the HWT 96 and positioned to remove the pipe insert 34 from the tube sheet 18 at end 24. The position of the pipe container cutting tool 100 relative to the end shield 64 and the operation of the tool 100 can be controlled by a control station. Specifically, the operator can control the height of the RTP 95 along axis Y, the position of the cutting tool 100 on the HWT 96 along axis X, and the pitch angle relative to the end shield 64 to orient the axis Z perpendicular to the end shield 64. In some embodiments, the height of the RTP 95 can be adjusted by ball screws, for example, by one ball screw at each corner of the RTP 95.

[0071] When the cutting tool 100 is aligned with the selected opening in the end shield 64, the operator can insert the pipe container cutting tool 100 into the corresponding fuel passage along axis Z. The cutting tool 100 may include any number of suitable sensors and / or cameras to verify that the cutting tool 100 is correctly aligned with the corresponding opening in the end shield 64. Once inserted, the cutting tool 100 can begin the cutting operation as described below. Due to the high radiation field in the pipe container 10, all cutting operations can be performed remotely. For this purpose, a controller 300 can be provided to control the movement of the cutting tool 100, the workbench 96, the platform 95, the gripper 103, the movable contamination barrier 104, etc. In one embodiment, the cutting tool 100 may be the cutting tool described in International Patent Application No. PCT / CA2024 / 051259, the entire contents of which are incorporated herein by reference.

[0072] Figure 3 A schematic diagram shows a cutting tool 100 inserted into a pipe container 10. The pipe container 10 includes an A end face opposite to the C end face, and each end face has an end shield 64. The lateral sides of the pipe container 10 are referred to as the D end face and the B end face (not shown). Figure 3 As shown, the cutting tool 100 can be positioned on a worktable 96 on platform 95. A crane 101 can be configured to handle the segmented blocks of the pipe container 10 and can be mounted on the reactive mechanism (RM) table 102. A gripper 103 can extend from the RM table 102 and unfold inside the pipe container cavity 11 to grip the segmented portion of the pipe container 10. The gripper 103 can extend into the cavity 11 through holes cut in it to allow access to the pipe container 10. In some embodiments, the gripper 103 can extend into the cavity 11 and the pipe container 10 through a port in the reactive mechanism table 102 (which allows vertical access to the pipe container 10). In one embodiment, the port may include an observation port, a liquid zone control unit port, a flux detector port, a liquid injection shutdown nozzle, a reactive control unit nozzle, etc. Cutting the pipe container 10 inside the cavity 11 allows for the containment of debris and / or cutting byproducts (e.g., dust and particles) to prevent their migration to the outside of the cavity 11. During operation of the cutting tool 100, the interior of the cavity 11 can be maintained at a vacuum pressure relative to the outside of the cavity 11, for example, through an active ventilation system (not shown).

[0073] When the cutting tool 100 cuts / segments the components of the pipe container 10, the gripper 103 can be coupled to the segmented components and move them to the waste collection container 106. A remotely controlled demolition robot (not shown) can also be positioned inside the pipe container cavity 11 to assist in handling the segmented portions of the pipe container 10. Holes can also be cut into the pipe container 10 by the cutting tool 100 to handle the segmented pieces of the pipe container 10. The cutting tool 100 can use cutting techniques such as plasma arc, laser, water jet, milling, etc., to cut the pipe container 10.

[0074] In one embodiment, a contamination barrier 104, such as a movable shielding wall or shielding door, may be installed to shield the bottom portion of the pipe container cavity 11 after it has been opened. The contamination barrier 104 may be made of a material that reduces or prevents radioactive material from passing through it. The barrier 104 may be installed prior to the dismantling process. If necessary (during the removal of the divided portion of the pipe container 10 from the interior of the pipe container cavity 11), an existing shielding wall between the refueling machine (FM) maintenance room and the transfer corridor may be activated to isolate the operating area. Alternatively, a large shielding door may be activated between the FM room and the FM maintenance room. In one embodiment, the contamination barrier 104 may be installed before the pipe container cavity 11 is emptied.

[0075] To access the interior of the pipe container cavity 11, the walls of the pipe container cavity 11 can be removed. Barrier 104 can be installed before removing the walls of the pipe container cavity 11.

[0076] As described above, platform 95 can be mounted on both reactor end faces to provide Y-direction movement for tools mounted thereon. Workbench 96 can be mounted on platform 95 to provide X-direction movement for tools mounted thereon.

[0077] A transport vehicle (e.g., a waste collection vehicle) 105 can be positioned inside the stack cavity 11, below the pipe container 10. A waste collection container 106 (e.g., a waste transfer container) can be positioned on the vehicle 105 to collect the fragmented pieces. During the fragmentation of the pipe container 10, a barrier 104 can be positioned to close the opening in the stack cavity 11. When the container 106 is full, the barrier 104 can be moved / opened to allow the container 106 to be moved out into the fragmentation chamber, where the waste can be further fragmented, inspected, and packaged.

[0078] The following describes exemplary methods for dismantling a nuclear reactor. In some embodiments, the internal components of the piping container 10 are first removed, followed by the disassembly of the reactor cavity 11 and the remaining components of the piping container 10, removing them from the reactor building and transporting them to a storage facility. In other embodiments, the piping container 10 can be dismantled by removing it as a whole from the piping container reactor cavity, along with all its internal piping.

[0079] Figure 4 A schematic diagram of an exemplary method 400 for dismantling a nuclear reactor is shown. Specifically, method 400 removes the end shielding of the pipe container and its shell as an intact, integral assembly from the reactor cavity 11. In this embodiment, the pipe container 10 is radiation shielded by installing a steel liner over the pipe container 10 (particularly the pipe container shell) and filling the liner with concrete. Once removed from the nuclear reactor, the concrete-filled liner housing the pipe container 10 can be buried or stored in a permanent storage facility. This method minimizes the formation of radioactive particles resulting from the fragmentation of the radioactive components of the pipe container. Furthermore, the more radioactive components of the pipe container 10 are held between the end shielding and the pipe container shell, thereby preventing radiation leakage during the transport of the pipe container 10.

[0080] like Figure 4As shown, at block 401, method 400 may include setting up tools for operation within the reactor building (RB) enclosure, such as positioning cutting tool 100 within the RG enclosure. The reactor building RB may be maintained at a negative pressure relative to the surrounding environment to reduce the escape of contaminants such as dust and debris from the reactor building RB. At block 402, the concrete portion of the cavity 11 surrounding the end shield 64 may be segmented and removed to allow access to the end shield. At block 403, the concrete below the end shield may remain in place before installing jacks 41 to support the weight of the pipe container 10. At block 404, the concrete around the bottom of the end shield 64 may be removed so that the pipe container is suspended above the gap as shown. At block 405, the floor of the pipe container cavity may be cleaned, and at block 406, a transport 42, such as a self-propelled modular transport (SPMT), may be positioned below the pipe container 10. The path of the transport aircraft 42 can be reinforced to accommodate the combined weight of the transport aircraft, the piping container, and other materials positioned on the transport aircraft. At block 407, jacks 42 can lower the piping container 10 onto the transport aircraft 42 and remove it at block 408. In another embodiment, the transport aircraft 42 can be used as a jacking system, thereby raising the transport aircraft to support the weight of the piping container 10 until the concrete portion of the reactor cavity 11 below the piping container 10 is removed. With the reactor cavity 11 removed, new openings can be used to cut and remove pipes and pipe supports connecting the piping container 10 to the reactor cavity 11. At block 409, the transport aircraft 42 can remove the piping container 10 from the reactor cavity 11 in chamber R-108 of the reactor building; at block 410, the shielding liner 43 can be positioned above the piping container 10. At block 411, optionally, the piping container 10 can be filled with packing material. The filler material can be a material used to secure the internal components of the pipe container 10 and / or stabilize the shell 14 of the pipe container 10 for transport. In one embodiment, the filler material can be lightweight concrete with a dry density of not less than 800 kg / m³ and not more than 2000 kg / m³. Other types of concrete or filler material can be used to secure the internal components of the pipe container and / or stabilize the shell 14 of the pipe container 10. At block 412, the shielding liner 43 can also be filled with concrete, including the gap between the shielding liner 43 and the pipe container shell 14 and / or the interior of the pipe container shell 14. At block 413, the reactor building can be cleaned and decontaminated. At block 414, the shielding liner 43 housing the pipe container 10 can be removed from the reactor building, and at block 415, the shielding liner 43 housing the pipe container 10 can be transported to a storage facility.

[0081] Figure 5A and Figure 5BA front and side view of an exemplary pipe container 10 encased in an outer packaging is shown. The outer packaging 51 can be positioned on the pipe container 10 after it has been removed from the reactor cavity 11. The outer packaging 51 includes several sub-components. The lower portion 51a of the outer packaging 51 can be positioned on the transport vehicle 42 before the pipe container 10 is lowered onto the transport vehicle 42, and is installed around the pipe container 10 when the reactor cavity 11 is opened and the pipe container 10 is positioned on the transport vehicle 42. The upper portion 51b of the outer packaging 51 can be installed outside or inside the reactor building RB after the pipe container 10 has been positioned on the lower portion 51a of the outer packaging. In one embodiment, the upper portion 51b of the outer packaging can be installed as the pipe container 10 is moved out of the reactor cavity 11 by the transport vehicle. The outer packaging 51 can be filled with concrete and allowed to cure. In one embodiment, the outer packaging 51 is a shielding liner 43 made of a material configured to reduce radiation propagation through the outer packaging. For example, the shielding liner can be lead, steel, or other suitable materials.

[0082] Figure 6 A schematic diagram of an exemplary method 600 for dismantling a nuclear reactor is shown. In the illustrated method, the pipe container 10, along with all internal piping, is removed as a single reactor cavity 11. The pipe container 10 can be shielded by installing a liner (e.g., a steel liner) over the pipe container and filling it with concrete. Subsequently, the pipe container 10 can be stored in a temporary nuclear waste storage facility. Once radioactive decay reaches an acceptable level, the pipe container 10 can be disassembled, packaged, and transferred to a permanent storage facility.

[0083] like Figure 6As shown, at block 601, method 600 may include setting up tools for operation within the reactor building (RB) enclosure, such as positioning a cutting tool 100 within the RG enclosure. The reactor building RB may be maintained at a negative pressure relative to the surrounding environment to reduce the escape of contaminants such as dust and debris from the reactor building RB. At block 602, the concrete portion of the cavity 11 surrounding the end shield 64 may be segmented and removed to access the end shield. At block 603, the concrete below the end shield may remain in place before installing the jack 41 to support the weight of the pipe container 10. At block 604, the concrete around the bottom of the end shield 64 may be removed to allow the pipe container to suspend above the gap. At block 605, the floor of the pipe container cavity may be cleaned, and at block 606, a transport 42, such as a self-propelled modular transport (SPMT), may be positioned below the pipe container 10. The path of the transport aircraft 42 can be reinforced to accommodate the combined weight of the transport aircraft, the piping container, and other materials positioned on the transport aircraft. At block 607, jacks 42 can lower the piping container 10 onto the transport aircraft 42 and remove it at block 608. In another embodiment, the transport aircraft 42 can be used as a jacking system, thereby raising the transport aircraft to support the weight of the piping container 10 until the concrete portion of the reactor cavity 11 below the piping container 10 is removed. With the reactor cavity 11 removed, new openings can be used to cut and remove pipes and pipe supports connecting the piping container 10 to the reactor cavity 11. At block 609, the transport aircraft 42 can move the piping container 10 out of the reactor cavity 11 and into room R-108 of the reactor building. At block 610, a shielding liner 43 can be positioned above the piping container 10. The shielding liner 43 can be as described above. Figure 5A and Figure 5B The outer packaging is described. At block 611, optionally, the pipe container 10 can be filled with filler. The filler can be a material used to secure the internal components of the pipe container 10 and / or stabilize the shell 14 of the pipe container 10 for transport. At block 612, the shielding liner 43 can also be filled with concrete, including filling the gap between the shielding liner 43 and the pipe container shell 14 with concrete and / or filling the interior of the pipe container shell 14 with concrete. At block 613, the reactor building can be cleaned and decontaminated. At block 614, the shielding liner 43 housing the pipe container 10 can be removed from the reactor building, and at block 615, the shielding liner 43 housing the pipe container 10 can be transported to a temporary storage facility. At block 616, after the radioactive decay of the pipe container 10 has reached the expected level, the pipe container 10 can be segmented and packaged. At block 617, the pipe container 10 can be transported to a permanent storage facility.

[0084] Figure 7A schematic diagram of an exemplary method 700 for dismantling a nuclear reactor is shown. As illustrated, the dismantling method involves segmenting the pipe container shell 14 and then removing the end shield as a whole. A cutting tool 100 can be used to cut internal components of the pipe container 10, for example, by inserting the cutting tool 100 via grid points. The pipe container shell 14 can also be segmented from the inside using the cutting tool 100. The dimensions of the segmented portions of the pipe container shell 14 can be determined based on available waste containers, crane capabilities, etc. The segmented portions of the pipe container shell 14 can be collected on a transport vehicle positioned inside the pipe container cavity. The transport vehicle can exit the cavity through open cavity walls for packing and transport the segmented pieces of the pipe container for further processing. The end shield can be removed as a whole, unsegmented unit. The end shield of the pipe container defines a shielded ball bearing 66 within the end shield; the shielded ball bearing 66 is a tightly packed assembly to minimize the volume of the shielded ball bearing. Once the end shields are cut and separated from the reactor cavity, they can be stacked so that the radioactive tube sheet of the pipe container is shielded by the structure of the end shields. By holding the end shields of the pipe container in their operating position, coupled to the reactor cavity, and by segmenting the components of the pipe container between the end shields, the end shields can provide radiation protection and provide a segmentable, hermetically sealed environment.

[0085] like Figure 7 As shown, method 700 may include setting up tools for operation within the reactor building (RB) enclosure, such as positioning a cutting tool 100 within the RB enclosure. A remotely controlled robot may be positioned within the reactor building, and / or a crane may perform the processing operations. Additional processing equipment may be installed in the reactive facility area to assist in processing the segments / cut blocks of the pipe container. The reactor building RB and / or reactor cavity may be maintained at a negative pressure relative to the surrounding environment to reduce the escape of contaminants such as dust and debris from the reactor building RB and / or reactor cavity. At block 701, a shielding wall 71 may be installed below the A-face of the end shield 64. Since access to the pipe container reactor cavity may be required to collect the segments / cut blocks of the pipe container 10 and the associated moderator conduits 67, the shielding wall 71 may be a movable shielding door to shield the working area while accessing the reactor cavity 11.

[0086] At block 702, a portion of the reactor cavity 11 below the end shield 64 can be removed at any end face of the reactor. For example... Figure 7 As shown, a gap can be formed on either end face A or end face C (as shown in the diagram). Figure 3(As shown). However, a gap can also be formed at the D or B end face. At block 703, a gap can be formed below the pipe container 10 inside the cavity 11, such that the pipe container is suspended above the gap. At block 704, as shown, a conveyor 42, such as a self-propelled modular conveyor (SPMT), can be positioned below the pipe container 10. The travel path of the conveyor 42 can be reinforced to accommodate the total weight of the conveyor, the pipe container, and other materials positioned on the conveyor. At block 705, the pipe container shell 14 can be cut and removed from the cavity 11 by the cutting tool 100, and packaged at block 706. At block 707, a portion of the cavity 11 can be removed, such as the portion below the C end face of the end shield. A portion of the cavity 11 can be removed from the other side of the cavity 11, such as at any one of the A, B, or D end faces. At block 708, support member 43 can be coupled to the A-face and C-face of end shield 64 to support each end shield for transport on conveyor 42 and prevent the A-face and C-face from tipping over. At block 709, the remaining portion of the cavity 11 around the end shield 64 at the A-face and C-face can be removed, and at block 710, each end shield 64 can be positioned on conveyor 42 while defining the tube sheet between the opposing end shield end faces. At block 711, the end shield 64 and the segmented portion of the pipe container 10 can be transported to a permanent storage facility.

[0087] like Figure 8 As shown, after the end shield 64 is separated from the reactor cavity 11, the end shield of end face A can be horizontally positioned on the transport machine 42 using a crane 101, a clamp 103, and / or other support / clamping equipment. The end shield of end face C can be positioned on top of the end shield of end face A, or vice versa. Each end shield can be positioned such that a portion of the tube sheet 18 of the end shield faces inward toward the opposite end shield to confine the radioactive components of the contaminated tube sheet 18 between the outer portions of the end shield 64. This orientation utilizes the shielding properties of the end shield 64 to mitigate radiation from the tube sheet 18.

[0088] Figure 9A schematic diagram of an exemplary method 900 for dismantling a nuclear reactor is shown. As illustrated, the dismantling method involves segmenting the pipe container shell 14 and then in-situ segmenting the end shield 64. Moving parts within the pipe container shell 14 (e.g., internal piping and sleeves) can be removed first by access from grid points in the end shield 64. As illustrated, the dismantling method involves segmenting the pipe container shell 14 and then in-situ segmenting and removing the end shield. A cutting tool 100 can be used to cut internal components of the pipe container 10, for example, by inserting the cutting tool 100 via grid points. The pipe container shell 14 can also be segmented from the inside using the cutting tool 100. The dimensions of the segmented portions of the pipe container shell 14 can be determined based on available waste containers, crane capabilities, etc. The segmented portions of the pipe container shell 14 can be collected on a transport vehicle positioned inside the pipe container reactor cavity. The transport vehicle can exit the reactor cavity through open cavity walls for packing and transport the segmented pieces of the pipe container for further processing. End shielding components can be disassembled, packaged, and transported to permanent storage facilities in situ.

[0089] At block 901 of method 900, similar to the method described above, a shielding wall can be installed to cover the portion of the pipe container cavity to be removed. The shielding wall is configured to allow access to the cavity to collect cut pieces of the pipe container shell 14 and to cut the moderator / casing pipes. The shielding wall can be a temporary, movable shielding door installed to shield the working area and allow access to the pipe container cavity. At block 902, a portion of the cavity, such as the lower portion of the pipe container cavity, can be removed, and at block 903, a gap can be formed below the pipe container 10 inside the cavity 11, such that the pipe container is suspended above the gap. At block 904, as shown, a conveyor 42, such as a self-propelled modular conveyor (SPMT), can be positioned below the pipe container 10. The travel path of the conveyor 42 can be reinforced to accommodate the total weight of the conveyor, the pipe container, and other materials positioned on the conveyor. At block 905, radioactive components within the pipe container shell 14 can be segmented using the cutting tool 100 and removed from the reactor cavity 11. The pipe container shell 14 can also be segmented piece by piece by the cutting tool 100, removed from the reactor cavity 11, and packaged at block 906. By segmenting the pipe container shell 14 within the end shield 64, the end shield can be used to mitigate radiation from the pipe container shell and components within it. At block 907, the shielded ball bearing 66 can be removed from the end shield 64. Since the shielded ball bearing 66 may degrade over time, its condition may be unknown. In one embodiment, the shielded ball bearing may be carbon steel and may be rusted. In one embodiment, to remove the shielded ball bearing 66, the inner diameter of the grid tube 65 can be cut, or the tube sheet 18 can be cut to determine a waste segregation strategy. The shielded ball bearing 66 can be removed through a cut section of the tube sheet 18 or through at least one cut section of the grid tube 65. At block 908, a portion of the end shield 64 can then be segmented; at block 909, the grid tube can be removed; and at block 910, the remaining portion of the end shield 64 can be removed. In one embodiment, the end shield on the pipe container side can be segmented, and the grid tube can be removed. Continuing with this embodiment, the end shield on the changeover machine side can then be segmented. A cutting tool 100 can be positioned on platform 96 to segment the end shield 64. At block 911, the segmented end shield 64 can be packaged, and at block 912, it can be transported to a permanent storage facility.

[0090] Figure 10A schematic diagram of an exemplary method 1000 for dismantling a nuclear reactor is shown. As illustrated, the dismantling method involves splitting and removing the pipe container shell 14, and then splitting and removing internal components that can be secured in place by filler material. Initially, at block 1001, the end fitting assembly 50 can be removed from the nuclear reactor, and pressure tubes can be cut at the end shield 64. Shielding plugs (also known as "thumbtack plugs") can be inserted into the grid tubes to seal the interior of the pipe container 10. At block 1002, a portion of the reactive mechanism (RM) platform 102 can be removed. At block 1003, after emptying the reactor cavity 11, the pipe container 10 can be filled with filler material to stabilize the pipe container shell 14 and internal piping. At block 1004, the reactor cavity 11 can be opened. At block 1005, a series of vertical circumferential cuts can be made to the pipe container shell 14, followed by splitting. At block 1006, a portion of the pipe container shell 14 can be peeled off, leaving the end shield 64. At block 1007, the internal pipes of the pipe container 10, such as the fuel channel assembly 28 and the moderator pipes, are retained. At block 1008, the remaining internal pipes of the pipe container 10 can then be segmented and removed; then, at block 1009, the end shield 64 is segmented and packaged. Since the internal pipes and internal components of the pipe container 10 are ILW (In-line Welded), the bonding of the internal pipe filling material can reduce radiation emissions and the formation of radioactive particles when the packing defining the internal pipes and internal components of the pipe container 10 is segmented.

[0091] The following describes an implementation of an exemplary method 1000 for dividing the pipe container 10.

[0092] Figure 11A This is a front view of the piping container inside the reactor cavity of a nuclear reactor; Figure 11B yes Figure 11A The diagram shows a side cross-sectional view of the piping container inside the reactor cavity. Figure 11A As shown, in one embodiment, the casing 17 (e.g., ionization chamber, liquid injector, shutdown unit, etc.) can be cut along lines AA and BB, and the moderator inlet and outlet pipes can be cut along lines CC and DD. After cutting, the resulting holes can be plugged so that the pipe container 14 (e.g., ...) can be filled with packing 20. Figure 11A and Figure 11B (As shown in the shaded area). At this point, CT 32 and PT 36 may still be present within the pipe container housing 14. Once the pipe container housing 14 is separated / decoupled from the external piping surrounding the pipe container housing 14, PT 36 can be fastened to CT 32 at a predetermined location.

[0093] Figure 12 yes Figure 11AThe diagram shows a side cross-sectional view of the piping container inside the reactor cavity of a nuclear reactor, with a portion of the cavity removed. Figure 12 As shown, the cavity 11 can be opened by cutting a portion of it (the cut section EE is shown in the diagram), thereby allowing access to the bottom portion of the cavity 11. Figure 12 As shown, the cut-off section EE can be on end face D and / or end face B. End faces A and C (including end shields 64 at the changeover station or grid point) can remain unchanged and intact to maintain the radiation shielding they provide.

[0094] Figure 13A yes Figure 11A The diagram shows a front view of the piping container inside the reactor cavity, with a cut showing the piping container shell. Figure 13B yes Figure 13A The diagram shows a side cross-sectional view of the pipe container inside the reactor cavity of a nuclear reactor. As described above, method 1000 includes cutting and peeling off the pipe container shell 14. In one embodiment, the outer shell, annular plate, and subshell of the pipe container shell are peeled off and separated. Known cutting methods, such as wire cutting, can be used for the cutting. The first cut is directed toward the circumference of the pipe container shell 14 and cuts from the surface of the pipe container shell 14 to a predetermined depth FF. The cutting tool can be operated from the RM table 102 or through... Figure 12 The opening shown in the middle cutting section EE operates adjacent to the stack cavity 11. In one embodiment, at least three cuts 21 may be performed to divide the cut pipe container into easily handleable blocks.

[0095] Figure 14 yes Figure 13A The diagram shows a front view of the pipe container inside the reactor cavity, illustrating the segmentation of the pipe container shell. In one embodiment, cutting tools can be positioned at the A and C ends through the fuel passage assembly 28 to perform cuts 25, 26 to cut segments from the pipe container shell 14. The cut pieces of the pipe container shell 14 can be collected from inside the reactor cavity 11 and packaged into waste containers in appropriate locations. Segmentation of the pipe container shell can continue until the pipe container shell 14 is stripped. The end shield 64 can be cut at the same depth as the pipe container shell 14. Because the outermost portion of the end shield is coupled to the reactor cavity 11 via concrete, these cut pieces can remain until the pipe container shell 14 has been segmented and removed.

[0096] Continuing with this embodiment, once the main housing is peeled off, a similar axial cutting operation can be repeated until the pipe container housing 14 is completely cut. The cut pieces can be collected by processing equipment, which then packages the pieces into a waste container. The cut pieces of the end shield 64 can remain in place until the pipe container housing 14 is segmented and removed.

[0097] Figure 15A This is after the casing of the pipe container has been removed. Figure 14 The diagram shows a side cross-sectional view of the piping container inside the reactor cavity of a nuclear reactor. As shown, end shields 64 are retained. End shields 64 can be cut such that a portion 64a of each end shield 64 is coupled to the reactor cavity 11 (e.g., via cement), and a portion 64b of each end shield 64 is not coupled to the reactor cavity 11. Portions 64b can be located radially inward of the reactor cavity 11. To remove the end shield 64, portions 64b can be removed. Additional supports may be required around the portions of the end shield to ensure the stability of the end shield 64 during removal and handling. Figure 15B As shown, this process can continue until the section of end shield 64 is removed, leaving only the portion coupled to the cavity 11 (e.g., with concrete). The remaining block can be separated from the cavity 11 using a cutting tool, processed, and packaged into a waste container.

[0098] Figure 16 A schematic diagram of an exemplary method 1600 for dismantling a nuclear reactor is shown. As illustrated, the dismantling method involves: after filling the reactor cavity 11 and the pipe container 10 with a filling material (e.g., concrete), dismantling the entire pipe container 10 and fuel channel assembly 28 in situ, wherein the filling material provides shielding and absorbs radiation emitted from the pipe container during the dismantling process. In one embodiment, the concrete may be lightweight concrete with a dry density of not less than 800 kg / m³ and not more than 2000 kg / m³. See below for reference. Figures 16-19D Method 1600 is explained.

[0099] The advantage of method 1600 is that it minimizes the preparation work required for the removal scheme. To fill the pipe container 10 and the pipe container cavity 11 with filler material, the penetrations through the cavity 11 can be blocked if necessary. At block 1601, the end fitting assembly 50 can be removed, and a shielding plug can be installed to seal the grid pipe. At block 1602, a shielding plate can be installed above the end shield 64 to further seal the cavity 11. CT 32, PT 36, pipe insert 34, and sleeve can remain inside the pipe container 10 and the cavity 11. At block 1603, after draining the liquid (e.g., moderator fluid) from the cavity 11 and the pipe container 10, a cutting channel 16 can be installed, extending through the pipe container 10, for example, as shown in the image. Figure 17 The cutting channel 16 extends vertically through the pipe container 10. It allows a cutting tool to enter and divide adjacent portions of the pipe container 10 after the cavity and pipe container 10 have been filled with filler. At block 1604, after the cutting channel 16 is installed, the pipe container 10 and cavity 11 are filled and shaped with filler (e.g., concrete). Once the filler is shaped, the cavity 11, pipe container 10, and filler define a solid space that can be divided and removed. At block 1605, a core hole 15 (e.g., a horizontal core hole) can be drilled through the end shield 64, for example via a pressure relief pipe; at block 1606, the RM platform 102 can be removed to allow the cutting tool to enter the concrete-filled pipe container 10 and cavity 11. At block 1607, the cutting tool can then divide the layers of the solid space comprising the cavity, pipe container, and filler. At block 1608, the cutting tool can utilize the cutting channel 16 and core hole 15 to cut and remove portions of the solid space layer by layer. In one embodiment, the cutting tool may be a wire cutting tool with a cutting line that extends into the cutting channel 16 or the core hole 15 to cut through the cutting channel 16 and the filling material.

[0100] The following describes an implementation of an exemplary method 1600 for dividing the pipe container 10.

[0101] Figure 17 A side sectional view of the pipe container 10 is shown inside the reactor cavity of a nuclear reactor, with a cutting channel 16 installed vertically through the pipe container 10. The cutting channel 16 can be a conduit suitable for forming the channel, such as a metal conduit. The cutting channel 16 can be inserted into the pipe container 10 through a vertical conduit in the pipe container (e.g., a rupture disc and / or reactivity control unit penetration in the reactor cavity 11). After the pipe container 10 is filled with packing material, the cutting channel 16 can allow a cutting tool (e.g., a wire cutter) to enter the interior of the pipe container 10 to cut portions of the solid space comprising the pipe container 10, the reactor cavity 11, and the packing material. Each PT 36 can also be fastened to its respective CT 32 before the pipe container 10 and / or the reactor cavity 11 are filled with packing material.

[0102] Figure 18A The diagram shows a front view of the piping container inside the reactor cavity of a nuclear reactor. Figure 11B yes Figure 18A The diagram shows a side cross-sectional view of the piping container inside the reactor cavity; Figure 11C is... Figure 18AThe diagram shows a side cross-sectional view of the pipe container inside the reactor cavity, including a core section within the cavity. In one embodiment, the casing 17 (e.g., ionization chamber, liquid injector, shutdown unit, etc.), moderator inlet and outlet conduits, pipe insert 34, and other conduits within the pipe container 10 and reactor cavity 1 can remain in situ. Filler (e.g., concrete) can be poured into and shaped into the pipe container 10 and / or reactor cavity 11. For adequate shielding, the filler can be poured to a specific height above the top of the pipe container shell 14 to allow for... Figure 18B The RM stage 102 is removed as shown. The packing 20, pipe container 10, and reactor cavity 11 can then be segmented, for example by wire cutting, core drilling, diamond cutting, or similar methods. Segmentation of the pipe container 10 and reactor cavity 11 can be performed from top to bottom. Vertical cutting can be performed through the cutting channel 16 installed inside the pipe container 10 and through the core opening 15 drilled into the packing 20. Horizontal cutting can be performed using a cutting tool inserted through the fuel passage assembly 28. These operations can be performed entirely or partially remotely. The end shield 64 can be cut along with the reactor cavity 11.

[0103] Figure 19A Showing Figure 18A The diagram shows a front view of the piping container inside the reactor cavity, with the RM stage removed. Vertical cut 27 can be made via cut channel 16 or core opening 15; horizontal cut 29 can be made via fuel channel assembly 28 and / or grid tubes to intersect with vertical cut 27, thereby forming a segmented portion of packing 20, piping container 10, and / or reactor cavity 10. The segmented portion can be formed via openings in RM stage 102 and / or reactor cavity 11 (e.g., Figure 13A The cut-off segment (EE) shown is removed and transported to a location for packaging into a waste container. In some embodiments, the cut-off portion may need to be stored and / or transported in a radiation shielding container.

[0104] Figure 19B This is a partial enlarged view of Detail GG. Detail GG shows an exemplary cross-section of a portion of the pipe container 10 and packing 20 cut by a cutting tool according to this disclosure. In one embodiment, as referenced above... Figure 19AThe core opening 15 can be drilled into the concrete along the core opening axis 39. A cutting tool can be inserted into at least one cutting channel 16. At least one of the filler 20 and the pipe container 10 is cut along a generally vertical first plane II, which connects the core opening 15 and at least one cutting channel 27. Multiple cuts generally parallel to the first plane II can be made through additional core openings and / or cutting channels to achieve a series of parallel cuts. The vertical cut 27 along the first plane II may intersect with a generally horizontal cut 29. In one embodiment, at least one of the filler and the pipe container is cut laterally from the core opening 15 and / or cutting channel 16 to define a second plane JJ, which intersects to divide a portion of the filler and / or pipe container 10. Figure 19B In the illustrated embodiment, cutting at least one of the packing material and the pipe container from at least one cutting channel side comprises: inserting a cutting tool into the grid tube 65; and cutting at least one of the packing material 20 and the pipe container 10 along a generally horizontal second plane JJ intersecting the grid tube and another grid tube. Figure 19B As shown, vertical cut 27 and horizontal cut 29 may intersect with adjacent grid tubes. Because vertical cut 27 and horizontal cut 29 may intersect with radioactively contaminated pipes, fuel channels, and / or grid tubes 65 of the pipe container 10, portions of these pipes, fuel channels, and / or grid tubes may be exposed due to lack of coverage by packing 20. Therefore, it may be necessary to... Figure 19B The cut portions (one or more) of the pipe container 10 and packing 20, as shown by the cutting tool, are placed in a radiation shielding container for storage and / or transport to provide omnidirectional shielding of the cut portions. Additional radioactive dust may also be generated when the vertical cut 27 and horizontal cut 29 intersect with the pipes, fuel channels, and / or grid tubes of the pipe container 10 that need to be collected and removed.

[0105] Figure 19CThis is a partial enlarged view of Detail HH. Detail HH shows an exemplary cross-section of a portion of the manifold container 10 and the packing 20 cut by a cutting tool according to this disclosure. As shown, the vertical cut 27 and the horizontal cut 29 do not intersect with the manifold, fuel passages, and / or grid tubes 65 of the manifold container 10. Instead, cutting the packing 20 and the manifold container 10 laterally from the cut channel 27 includes cutting the packing 20 between adjacent fuel passages such that the cutting planes (i.e., the generally horizontal plane KK and the generally vertical plane LL) do not intersect with the manifold, fuel passages, and / or grid tubes 65 of the manifold container 10. Since the cutting planes (i.e., the horizontal plane KK and / or the vertical plane LL) can be located between the manifold, fuel passages, and / or grid tubes 65 of the manifold container 10, less radioactive surface is exposed, thereby reducing the need for radiation shielding and the number of radioactive particles generated during cutting. In this way, Figure 19C The segmented portion of detail HH shown may not need to be related to... Figure 19B The segmented portion shown is used for storage and / or transport with adequate radiation shielding because only two sides of the segmented portion contain exposed radioactive conduits belonging to the ILW, i.e., the opposite sides of the segmented portion after the conduits have been cut. Since the packing material 20 can define at least four sides of the segmented portion, it can reduce the exposure of the radioactive conduits. Thus, radiation shielding can be applied only to the sides of the segmented portion that expose the radioactive conduits (i.e., the opposite sides of the segmented portion after the conduits have been cut).

[0106] In one embodiment, the divided portions of the packing and piping container may have a substantially quadrilateral cross-section.

[0107] Figure 19D An exemplary cutting tool coupled to a collaborative robot 70 according to the present disclosure is shown, wherein the cutting tool is positioned outside the pipe container 10. The collaborative robot 70 can perform both vertical cuts 27 and horizontal cuts 29 while positioned outside the pipe container 10.

[0108] Figure 19E An exemplary path for a cutting tool and a waste container vehicle is illustrated. A collaborative robot 70 (e.g., a cutting tool) can move through an opening in the cavity 11 to segment portions of the pipe container 10 and / or connect the pipe container to pipes and supports in the cavity 11. A barrier 104 can be placed to provide radiation shielding to cover openings created by removing portions of the side of the cavity 11. The segmented portions of the pipe container 10 and the packing 20 can be positioned on a vehicle 105, which can remove the segmented portions from the cavity 11.

[0109] Figure 20A schematic diagram of an exemplary method 2000 for dismantling a nuclear reactor is shown. As illustrated, the dismantling method involves in-situ underwater dismantling of the entire pipe container 10 and fuel passage assembly 28. Cutting tools can be accessed from the RM platform 102 into the pipe container 10. See below for further details. Figure 20 and Figure 21 Method 2000 is described below. By underwater segmentation of the pipe container 10, fuel passage assembly 28, and its components, the formation of airborne radioactive particles caused by cutting radioactive components can be reduced. This reduces or eliminates the need for one or more ventilation systems around the reactor cavity 11 during decommissioning.

[0110] Another advantage of Method 2000 is that it minimizes the preparation work required to remove the piping container 10. Penetrations through the reactor cavity 11 (e.g., fuel passages, grid pipes, and sleeves) can be blocked if necessary to provide a sealed space configured to be filled with water. Each fuel passage on each side of the nuclear reactor can be waterproof to prevent water leakage from the interior of the reactor cavity 11 when it is filled with water. Figure 20 As shown, at block 2001, end fitting assembly 50 can be removed and a shielding plug installed to seal the grid tubes. CT 32, PT 36, pipe insert 34, and sleeve may remain inside the pipe container 10 and the reactor cavity 11. At block 2002, sealing member 201 (e.g., sealing plate and / or plug) can seal each fuel passage. In one embodiment, the sealing member is a sealing plate that can be welded to seal one or more fuel passages. In another embodiment, sealing member 201 may be a plug (one or more) positioned in each fuel passage and / or grid tube. At block 2003, a portion of RM station 102 can be removed to allow direct access to the pipe container 10. Removal of RM station 102 can be parallel to sealing the fuel passages. Cutting and processing tools can be positioned in the RM station area along with the waste bin and drying and packing station. At block 2004, the cutting and packing of the pipe container 10 (including internal piping) is completed. The segmented portion of the pipe container 10 can be used to load waste containers underwater inside the reactor cavity 11. Once the waste containers are full, they can be loaded as follows: Figure 21The waste is lifted from the water for drainage and then moved to system 200 for drying and packaging. System 200 may include a receiving station, a thermal drying and packaging section, and radiation measurement instruments. After the waste container containing the waste is completely dry, it can be placed in a shielded container for transport. Drying and packaging can be performed in parallel with underwater segmentation. In some embodiments, the sleeve, sleeve anti-vibration components, and moderator pipes should be cut and removed first to allow access to the pipe container shell. After the area above the pipe container shell is cleaned, the upper section of the pipe container shell can be segmented and removed, followed by the segmentation and removal of its internal pipes. At block 2005, after removing the pipe container and its internal components, the shielded ball bearing 66 can be removed. The tube sheet 18 can be opened with a cutting tool, and the shielded ball bearing 66 can be collected in a container. At block 2007, after removing the pipe container 10 and the shielded ball bearing 66, the tube sheet 18 can be segmented and removed; and the grid tube 65 can also be segmented and removed. Tubesheet 18 and grid tubes 65 can be cut using tools and techniques similar to those used for splitting the tube stack container 10. The cut tubesheet 18 can be a tube stack container side tubesheet, leaving the refueling machine side tubesheet (i.e., end shield) intact to form a water-filled sealed space. At block 2009, once all underwater splitting is complete, the reactor cavity 11 can be emptied and filtered using an activated water filtration system to separate particulate matter and waste material from the water. Optionally, at block 2009, the reactor cavity 11 can be used to split other equipment within the reactor building. At block 2010, the refueling machine tubesheet can be split using the same tools used for underwater splitting.

[0111] In one embodiment, a method 2000 including a segmented pipe container, internal components of the pipe container, and a tube sheet of end shielding may include: providing a container configured to receive segmented nuclear components of a nuclear reactor. The container can receive the segmented components from a processing tool inside the reactor cavity. The container may have a plurality of openings for drainage. The method may further include positioning a segmented portion of at least one of the pipe container, internal components of the pipe container, and the tube sheet of end shielding within the container; and positioning a shielding cover above the container. The shielding cover may be configured to receive the container and provide radiation shielding for the segmented components within the container. Once the shielding cover is positioned above the container, the container can be lifted out of the water. When the components are outside the reactor cavity and water, the shielding cover provides radiation shielding to prevent personnel from being exposed to radiation from the segmented components. The method may further include: draining water from the container; drying the segmented components; and positioning the dried segmented components in a container for transport to an external storage facility. In one embodiment, water in the divided components can be removed by drying them with a heater without moving particulate matter (e.g., dust, debris, and flakes) generated by dividing the components of the pipe container 10. Once dried, the divided components of the pipe container 10 can be positioned in a radiation shielding container configured to shield the divided components from radiation. International Patent Application No. PCT / CA2024 / 051337 describes exemplary radiation shielding containers (one or more), the entire contents of which are incorporated herein by reference.

[0112] Figure 21 An exemplary system 200 for drying and packaging radioactive waste is shown. System 200 includes a drying and packaging station 210, a waste container 211, and a dryer 212. The waste container 211 can receive a segmented portion of a pipe container 10 underwater from a holder 103 within a reactor cavity 11. The waste container 211 may include a shield 213 for reducing radiation propagation and a drain port for draining water when the waste container is lifted out of the water-filled reactor cavity 11. In one embodiment, the waste container 211 may define at least one opening 215 (e.g., at the bottom of the waste container 211) sized to allow water to drain from the segmented portion without causing the component to fall when lifted out of the reactor cavity 11. The dryer 212 may include a heater for heating the segmented waste to evaporate water and dry the segmented waste. In one embodiment, the dryer is at least one of an infrared heater, a blackbody radiation heater, a resistance heater, and / or a convection heater. The dried, segmented waste can then be packaged into shielded container 214 for transport to a waste storage facility.

[0113] Alternative implementation methods The above description is merely exemplary, and those skilled in the art will recognize that changes can be made to the described embodiments without departing from the scope of the disclosed invention. This disclosure may be embodied in other specific forms without departing from the subject matter of the claims. This disclosure is intended to cover and include all suitable changes in technical aspects. Modifications falling within the scope of this invention will be apparent to those skilled in the art upon reading this disclosure, and such modifications should be considered to fall within the scope of the appended claims. Furthermore, the scope of the claims should not be limited to the preferred embodiments set forth in the examples, but should be given the broadest interpretation consistent with the overall specification.

[0114] It is understood that the above description and the specific embodiments shown are merely exemplary. The present invention is defined by the appended claims.

[0115] The claims are not intended to include, and should not be construed as including, means-plus-function or step-plus-function limitations unless such limitations are expressly referred to in a given claim using “means for…” or “step for…”.

Claims

1. A method for dividing a pipework container within the reactor cavity of a nuclear reactor, characterized in that, The method includes: Provide at least one cutting tool; An opening is formed by cutting a portion of the cavity with one of the at least one cutting tools; A shielded space is formed by a shielding wall, the stack cavity, and the end shielding of the pipe container. The shielding wall is configured to absorb radiation from within the shielded space. Optionally, the shielding wall covers the opening. The shell and internal components of the pipe container are separated within the shielded space; and Remove the shell and internal components of the pipe container from the shielded space.

2. The method according to claim 1, characterized in that, include: Remove the shielded ball bearing from between the end shield and the side tube sheet of the pipe container; The side tube sheet of the pipe container is split; Remove the grid tube from the end shield; as well as The end shield is split.

3. The method according to any one of claims 1-2, characterized in that, include: Position the transport aircraft below the pipe container; And the transport aircraft is used to remove the shell and internal components of the pipe container from the shielded space.

4. The method according to claim 1, characterized in that, include: Decouple the end shield from the cavity; as well as Position one of the end shields on top of the other end shield on the transport aircraft.

5. The method according to claim 4, characterized in that, Positioning one end shield on top of the other end shield includes positioning a tube sheet portion of one end shield against a tube sheet portion of the other end shield.

6. The method according to claim 2, characterized in that, This includes filling the pipe container with filler to support the pipe container and absorb radiation; wherein the portion of the reactor cavity cut by the at least one cutting tool is a reactive mechanism platform.

7. The method according to claim 2, characterized in that, include: The shielded space and the pipe container are filled with filler to support the pipe container and absorb the radiation emitted by the pipe container; The end shield is divided within the shielded space, wherein the shielding wall includes shielding blocks that define the surface of the end shield; as well as Remove the end shield from the shielded space.

8. The method according to claim 6 or 7, characterized in that, The filler is lightweight concrete with a dried density of not less than 800 kg / m³ and not more than 2000 kg / m³.

9. The method according to claim 6 or 8, characterized in that, The separation of the shell and internal components of the pipe container within the shielded space includes: Peeling the housing of the pipe container from the packing; and Divide the internal components.

10. A method for removing a pipe container from the reactor cavity of a nuclear reactor, characterized in that, The method includes: Provide at least one cutting tool; Cut a portion of the cavity using the at least one cutting tool; Position the pipe-laying container on the transport aircraft; Remove the pipe container from the stack cavity; Position the shielding liner above the shell of the pipe container; and The shielding liner is filled with the filler to secure the pipe container within the liner.

11. The method according to claim 10, characterized in that, The filler is concrete.

12. The method according to any one of claims 10-11, characterized in that, include: Before the pipe container is positioned on the transport machine, a first portion of the shielding liner is positioned on the transport machine; After the pipe container is positioned on the transport aircraft, the second portion of the shielding liner is positioned on the pipe container; And to couple the first and second portions of the shielding liner to confine the pipe container within the shielding liner.

13. The method according to claim 1, characterized in that, include: Insert at least one cutting channel through the pipe container, each of the at least one cutting channel defining a space for receiving one of the at least one cutting tools; The shielded space and the pipe container are filled with filler to support the pipe container and absorb the radiation emitted by the pipe container. Optionally, the filler is concrete. An opening is formed by cutting a portion of the cavity with the at least one cutting tool, wherein the portion of the cavity is a reactive mechanism platform; The end shield is divided within the shielded space.

14. The method according to claim 13, characterized in that, The filler is lightweight concrete with a dried density ranging from 800 kg / m³ to 2000 kg / m³.

15. The method according to any one of claims 13-14, characterized in that, The at least one cutting tool includes a wire cutting tool having a cutting line extending into the cutting channel, and the method includes cutting through the cutting channel and the filler.

16. The method according to claims 13-15, characterized in that, include: Drill a core hole opening in the packing along the axis of the core hole opening; Insert the at least one cutting tool into the at least one cutting channel; Cut at least one of the packing and the pipe container along a first plane, the first plane connecting the axis of the core opening and the axis of one of the at least one cutting channels; At least one of the packing and the pipe container is cut laterally from the axis of the at least one cutting channel to define a second plane, the first plane and the second plane intersecting to divide a portion of the packing.

17. The method according to claim 16, characterized in that, Cutting at least one of the packing and the pipe container from the side of the at least one cutting channel includes: Insert the cutting tool into the first grid tube; Cut at least one of the packing material and the pipe container along the second plane that intersects with the first grid tube and the second grid tube.

18. The method according to claim 16, characterized in that, Cutting at least one of the packing and the pipe container from the side of the at least one cutting channel includes: The packing is cut between adjacent fuel passages, wherein the second plane does not intersect with the grid tube of the manifold container.

19. The method according to any one of claims 16-18, characterized in that, The portion has a substantially quadrilateral cross-section.

20. The method according to any one of claims 13-16, characterized in that, This includes inserting at least one cutting tool into the cutting channel to divide the pipe container, the internal components of the pipe container, and the end shield.

21. A method for dividing a pipe container within the reactor cavity of a nuclear reactor, characterized in that, The method includes: Provide at least one cutting tool; Each of the plurality of grid tubes in the stack cavity is sealed with a sealing member; A shielded space is formed by the end shields of the stack cavity and the pipe container; Fill the shielded space with water to submerge the pipe container. An opening is formed by cutting a portion of the reactive mechanism stage using the at least one cutting tool; The pipe container, the internal components of the pipe container, and the tube sheet of the end shield are separated within the water-containing space of the shielded space. Remove the pipe container, the internal components of the pipe container, and the tube sheet of the end shield from the stack cavity.

22. The method according to claim 21, characterized in that, The sealing member is at least one of a plug and a welded plate.

23. The method according to any one of claims 21-22, characterized in that, The tube sheet is the side tube sheet of the pipe-laying container.

24. The method according to any one of claims 21-23, characterized in that, This includes removing water and splitting the end shield.

25. The method according to any one of claims 21-24, characterized in that, The tube sheet that separates the pipe container, the internal components of the pipe container, and the end shield includes: A container is provided that is configured to receive the segmented nuclear components of a nuclear reactor, the container having a plurality of holes for drainage; The divided portion of at least one of the pipe container, the internal components of the pipe container, and the tube sheet of the end shield is positioned in the box; A shielding cover is positioned above the box, the shielding cover being configured to receive the box and provide radiation shielding for the segmented components within the box; The box was lifted out of the water; Drain the water from the tank; The segmented components are dried; The dried, segmented components are positioned in containers for transport to external storage facilities.

26. A system for treating radioactive waste, characterized in that, The system includes: A crane configured to move a container into and out of the reactor cavity of a nuclear reactor, the cavity being filled with water; A container, configured to receive a segmented nuclear component of a nuclear reactor, the container defining at least one opening for drainage; A shielding cover configured to receive the enclosure and provide radiation shielding for the segmented components within the enclosure; A dryer configured to evaporate water from the divided components; and A container for transporting the segmented components from the dryer.

27. The method according to claim 26, characterized in that, The dryer is at least one of an infrared heater, a blackbody radiation heater, a resistance heater, and a convection heater.

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