JP2015222262A - Nuclear facility - Google Patents

Abstract

PROBLEM TO BE SOLVED: To ensure the safe and easy loading of a device for maintenance work in a structure.SOLUTION: A nuclear facility in which guide means 2 for guiding the movement of a device relative to an inner surface of a cooling medium circulation system in a structure (steam generator 13) before being contaminated with radioactive substances or a structure (steam generator 13) before being exposed to radiations and radioactivated is installed. With this configuration, in which the guide means 2 is provided in the steam generator 13, so that it is possible to avoid worker's entry into a position of a maintenance region in the steam generator 13. As a result, it is possible to safely, easily loading a device for maintenance work into the steam generator 13.

Description

  The present invention relates to a nuclear facility in consideration of maintainability.

  Nuclear facilities are regularly inspected to ensure their safety and reliability. Then, when it is recognized that maintenance replacement is required by inspection, maintenance is performed, and repair is performed for defective portions that are determined to be repaired by inspection. As described above, in order to maintain a normal operating state in a nuclear facility, work such as inspection, maintenance, and repair is required.

  For example, in the in-facility transfer device described in Patent Document 1, rail means laid in a sealed facility separated from the outside world, a self-propelled carriage that can travel along the rail means, and a detachable attachment to the self-propelled carriage Object mounting means that can be freely mounted and exchanged with facility equipment, a power supply / signal transmission system that supplies power to the self-propelled carriage and exchanges signals, and from outside the sealed facility via this power supply / signal transmission system And a control panel that performs travel control and operation control of the self-propelled carriage. And, with this in-facility transport device, the self-propelled cart that runs on its own along the rail means in the sealed facility is run or controlled from the outside so that it can be applied under the influence of high radiation and chemical substances. Yes.

Japanese Patent Laid-Open No. 10-324421

  However, when the in-facility transfer device described in Patent Document 1 is applied to nuclear equipment, in the work of laying rail means, an operator enters the structure of the nuclear equipment from a manhole provided in advance and is inspected, inspected, and replaced. Or the rail means must be attached to the place where maintenance work including repair is performed. Such work requires a contrivance to reduce the amount of radiation irradiated to the worker, and is difficult to carry out easily.

  The present invention solves the above-described problems, and an object thereof is to provide a nuclear facility capable of safely and easily introducing a self-propelled device that performs maintenance work in a structure.

  In order to achieve the above objective, the nuclear installation of the present invention is directed against the inner surface of a coolant circulation system in a structure prior to being contaminated with radioactive material or prior to exposure to radiation and activation. And a guide means for guiding the movement of the apparatus.

  According to this nuclear power facility, if the structure is provided with guide means, it is possible to prevent an operator from entering the inner surface of the coolant circulation system in the structure. As a result, a device for performing maintenance work can be safely and easily introduced into the structure.

  In order to achieve the above objective, the nuclear installation of the present invention is designed to provide equipment with respect to an assumed maintenance site in a structure prior to being contaminated with radioactive material or prior to being exposed to radiation and activated. Guide means for guiding the movement is provided.

  According to this nuclear power facility, if the structure is provided with guide means, it is possible to prevent an operator from entering the position of the maintenance site in the structure. As a result, a device for performing maintenance work can be safely and easily introduced into the structure.

  Further, in the nuclear power facility according to the present invention, the structure is a part of a circulation path of a primary coolant configured by sequentially connecting a reactor vessel, a pressurizer, a steam generator, and a pump by a primary coolant pipe. It is characterized by being.

  Moreover, in the nuclear power facility of the present invention, the guide means is installed in a portion where the path of the coolant changes depending on the diameter, direction, and access portion.

  Moreover, in the nuclear power facility of the present invention, the guide means has a series of grooves, a series of T-shaped protrusions connected in series, and a reverse T-shaped section connected in series to a series of rectangular protrusions. Grooves formed, protrusions projecting oppositely on both sides of a series of protrusions formed, holes provided intermittently, magnets provided intermittently, strips connected in series Line, intermittently provided strip-like line, intermittently provided strip-like light emitter, continuous wire, intermittently provided protrusion, intermittently provided cloud platform, or continuously provided It is characterized by being configured as a tunnel.

  Further, in the nuclear power facility of the present invention, the guide means is configured as a groove, a hole, an embedding or a tunnel without protruding from the surface of the structure, or a belt-like shape so as to be flush with the surface of the structure. It is characterized by being configured as a line or strip-shaped light emitter.

  Moreover, in the nuclear power facility of the present invention, the guide means is provided in the structure from a carry-in entrance for carrying the device into the structure.

  According to this nuclear power facility, since the worker only has to enter the carry-in entrance, the irradiation of radiation to the worker can be reduced.

  In the nuclear power facility of the present invention, the guide means is provided from the outside of the structure to the structure through a carry-in port for carrying the apparatus into the structure. .

  According to this nuclear facility, since the worker does not enter even the carry-in entrance, the irradiation of radiation to the worker can be extremely reduced.

  In the nuclear power facility of the present invention, the guide means is provided along the welded portion.

  The welded part is a main part as a maintenance part for maintaining soundness in the nuclear facility, and by providing a guide means along the welded part, a device for performing maintenance work on the welded part can be safely and easily performed. The effect to introduce can be acquired notably.

  ADVANTAGE OF THE INVENTION According to this invention, the self-propelled apparatus which performs a maintenance work in a structure can be introduce | transduced safely and easily.

FIG. 1 is an explanatory diagram of an example of a nuclear facility. FIG. 2 is a schematic view of the reactor vessel in the nuclear facility shown in FIG. FIG. 3A is a schematic diagram illustrating an example of guidance means. FIG. 3-2 is a schematic diagram illustrating an example of a guiding unit. FIG. 3C is a schematic diagram illustrating an example of the guiding unit. FIG. 3-4 is a schematic diagram illustrating an example of guidance means. FIG. 3-5 is a schematic diagram illustrating an example of guidance means. FIG. 3-6 is a schematic diagram illustrating an example of guidance means. FIG. 3-7 is a schematic diagram illustrating an example of guidance means. FIG. 3-8 is a schematic diagram illustrating an example of guidance means. FIG. 3-9 is a schematic diagram illustrating an example of guidance means. FIG. 3-10 is a schematic diagram illustrating an example of a guiding unit. FIG. 3-11 is a schematic diagram illustrating an example of guidance means. FIG. 3-12 is a schematic diagram illustrating an example of the guiding unit. FIG. 3-13 is a schematic diagram illustrating an example of guidance means. FIG. 3-14 is a schematic diagram illustrating an example of guidance means. FIG. 3-15 is a schematic diagram illustrating an example of guidance means. FIG. 3-16 is a schematic diagram illustrating an example of a guiding unit. FIG. 4 is a schematic diagram of a pressurizer in the nuclear facility shown in FIG. FIG. 5 is a schematic view of a pressurizer in the nuclear facility shown in FIG. FIG. 6 is a schematic diagram of a steam generator in the nuclear facility shown in FIG. FIG. 7 is a schematic view of a steam generator in the nuclear facility shown in FIG. FIG. 8 is a schematic view of piping (primary coolant pipe) in the nuclear facility shown in FIG. FIG. 9 is a schematic diagram of piping (primary coolant pipe) in the nuclear facility shown in FIG. FIG. 10 is a schematic view of a pipe (primary coolant pipe) in the nuclear facility shown in FIG.

  Embodiments according to the present invention will be described below in detail with reference to the drawings. Note that the present invention is not limited to the embodiments. In addition, constituent elements in the following embodiments include those that can be easily replaced by those skilled in the art or those that are substantially the same.

  The present embodiment will be described with reference to the drawings. FIG. 1 shows an example of a nuclear facility. The nuclear facility 1 is, for example, a pressurized water reactor (PWR: Pressurized Water Reactor) (see FIG. 1). In this nuclear power facility 1, a reactor vessel 11, a pressurizer 12, a steam generator 13, and a pump 14 as a structure are sequentially connected by a primary coolant pipe 15 to constitute a circulation path for the primary coolant. . Further, a secondary coolant circulation path is formed between the steam generator 13 and the turbine (not shown).

  In this nuclear power facility 1, the primary coolant is heated in the reactor vessel 11 to become high temperature and high pressure, and is pressurized through the primary coolant pipe 15 while being pressurized by the pressurizer 12 to keep the pressure constant. It is supplied to the generator 13. In the steam generator 13, heat exchange between the primary coolant and the secondary coolant is performed, so that the secondary coolant evaporates and becomes steam. The secondary coolant that has become steam by heat exchange is supplied to the turbine. The turbine is driven by the evaporation of the secondary coolant. Then, the power of the turbine is transmitted to a generator (not shown) to generate electricity. The steam used for driving the turbine is condensed into water and supplied to the steam generator 13. On the other hand, the primary coolant after heat exchange is collected on the pump 14 side via the primary coolant pipe 15.

  The nuclear power facility 1 of the present embodiment takes into consideration the maintainability of the reactor vessel 11, the pressurizer 12, the steam generator 13, and the piping (for example, the primary coolant pipe 15) that are the structures. A typical configuration will be described below.

[Embodiment 1]
As shown in FIG. 1, the reactor vessel (pressure vessel) 11 is constituted by a vessel body 11a and a vessel lid 11b attached to the upper portion thereof so that a structure inside the vessel (not shown) can be inserted therein. Has been. The container lid 11b is provided so as to be openable and closable with respect to the container body 11a. The container body 11a has a cylindrical shape with an upper opening and a lower hemispherical shape that is closed, and an inlet pipe 11c and an outlet pipe 11d for supplying and discharging light water as a primary coolant are provided at the upper part. A plurality of inlet pipes 11c are arranged at positions symmetrical with respect to the center line of the cylinder of the container main body 11a. A plurality of outlet pipes 11d are also arranged at positions symmetrical with respect to the center line of the cylinder of the container body 11a.

  FIG. 2 is a schematic view of the reactor vessel in the nuclear facility shown in FIG. In FIG. 2, the in-vessel structure is omitted, and only the vessel main body 11 a of the nuclear reactor vessel 11 is shown. As shown in FIG. 2, guide means 2 is provided in the container body 11a. The guiding means 2 guides the movement of the self-propelled device (not shown) to the assumed maintenance site in the reactor vessel 11. In addition, as a self-propelled device, an inspection device for inspecting a maintenance part, an inspection device for inspecting the maintenance part, a replacement device for maintenance replacement required for the result of inspection and inspection, a cutting device for cutting the part for repair, There are welding devices that weld after cutting. Hereinafter, work including inspection, inspection, replacement or repair in the maintenance site is referred to as maintenance work.

  The assumed maintenance site is mainly the welded portion 11f. The welded portion 11f is formed between the inlet pipe 11c and the nozzle base 11e for connecting the inlet pipe 11c to the container main body 11a, or the nozzle base 11e for connecting the outlet pipe 11d and the outlet pipe 11d to the container main body 11a. Exists between. Moreover, the welding part 11f exists between the container main body 11a and the nozzle 11e. Moreover, the welding part 11f is a connection location of container main body 11a itself, Comprising: For example, it exists between a cylindrical shape part and a hemispherical part. The guide means 2 is disposed along the weld line of the welded part 11f as the maintenance part. The maintenance site is not limited to the welded portion 11f, but may be any site assuming that maintenance work is performed in the reactor vessel (pressure vessel) 11.

  Moreover, the guide means 2 is arrange | positioned at the inner periphery of the container main body 11a so that each part along the welding part 11f may be relayed. In this Embodiment, while arrange | positioning along the circular shape of the cylinder of the container main body 11a, it is arrange | positioned from this circular shape to the part along the welding part 11f, and the parts along circular shape are connected mutually. Is arranged.

  The guide means 2 will be specifically described with reference to FIGS. 3-1 to 3-16. The guide means 2 shown in FIG. 3A is configured as a groove having an inverted T-shaped cross section connected in series. The guide means 2 has a projecting piece 2a facing the opening portion of the groove, so that the opening portion of the groove is formed narrower than the groove bottom. And the guidance means 2 guides the movement of a self-propelled apparatus with the opening part connected in series, hold | maintaining the weight of a self-propelled apparatus by hanging the self-propelled apparatus which is not shown in figure on the protrusion 2a.

  The guide means 2 shown in FIG. 3-2 is configured as a groove having a V-shaped cross section connected in series. The guide means 2 guides the self-propelled device along the groove without shaking because the V-shaped groove bottom 2b is narrowed and formed into a line.

  The guide means 2 shown in FIG. 3C is configured as a protrusion having a T-shaped cross section connected in series. Since this guide means 2 is formed with projecting pieces 2c projecting oppositely on both sides, a series of self-propelled devices (not shown) are hung on the projecting pieces 2c while maintaining the weight of the self-propelled device in series. The movement of the self-propelled device is guided by the connected shape.

  The guide means 2 shown in FIG. 3-4 is configured as a rectangular projection connected in series, and a groove having an inverted T-shaped cross section connected to the projection is formed. The guide means 2 is formed with a projecting piece 2d facing the opening of the groove, so that the opening of the groove is narrower than the groove bottom. And the guidance means 2 guides the movement of a self-propelled apparatus by the opening part connected in series, hold | maintaining the weight of a self-propelled apparatus by hanging the self-propelled apparatus which is not shown in figure on the protrusion 2d.

  The guide means 2 shown in FIG. 3-5 is formed with a pointed opposing tip of the projecting piece 2d in the guide means 2 shown in FIG. 3-4. The guide means 2 is formed with a projecting piece 2d facing the opening of the groove, so that the opening of the groove is narrower than the groove bottom. And the guidance means 2 guides the movement of a self-propelled apparatus by the opening part connected in series, hold | maintaining the weight of a self-propelled apparatus by hanging the self-propelled apparatus which is not shown in figure on the protrusion 2d. In addition, since the opposing tip of the projecting piece 2d is pointed, the guiding means 2 guides the self-propelled device toward the opposing side of each projecting piece 2d by the sharp inclined surface 2e without shaking. .

  The guide means 2 shown in FIG. 3-6 is configured as a series of protrusions, formed with protrusions 2f protruding oppositely on both sides of the protrusions, and formed with pointed tips of the protrusions 2f. . The guiding means 2 guides the movement of the self-propelled device by a shape connected in series while holding the weight of the self-propelled device by placing a self-propelled device (not shown) on the protrusion 2f. Moreover, since the leading end of the projecting piece 2f is pointed, the guiding means 2 guides the self-propelled device toward the opposite sides of the projecting pieces 2f by the sharp inclined surface 2g without shaking.

  3-7 is configured as a hole 2h provided intermittently. The guiding means 2 guides the movement of the self-propelled device using the hole 2h as a mark. The hole 2h may be formed as a screw hole. For this reason, it is possible to hold | maintain the weight of a self-propelled apparatus by screwing the male screw with which the self-propelled apparatus was equipped in the hole 2h.

  3-8 is configured as a hole 2i provided intermittently. The guide means 2 guides the movement of the self-propelled device using the hole 2i as a mark. Moreover, the hole 2i is formed so that the opening portion is narrower than the hole bottom because the protrusion 2j is formed on the opening edge. For this reason, it is possible to hold | maintain the weight of a self-propelled apparatus by hanging a self-propelled apparatus on the protrusion 2j.

  The guide means 2 shown in FIG. 3-9 is configured as a magnet (permanent magnet) 2k provided intermittently. The magnet 2k is preferably embedded so as to appear flush with the surface of the provided site. The guiding means 2 guides the movement of the self-propelled device by detecting the position by a magnetic sensor provided in the self-propelled device.

  The guiding means 2 shown in FIG. 3-10 is configured as a band-like line 2m connected in series. This guiding means 2 guides the movement of the self-propelled device by detecting the position by the imaging means provided in the self-propelled device.

  The guide means 2 shown in FIG. 3-11 is configured as a band-like line 2n provided intermittently. This guiding means 2 guides the movement of the self-propelled device by detecting the position by the imaging means provided in the self-propelled device.

  The guide means 2 shown in FIG. 3-12 is configured as a strip-shaped light emitter 2p provided intermittently. The guiding means 2 guides the movement of the self-propelled device by detecting the position by a light receiving sensor provided in the self-propelled device. In addition, the light emitter 2p may store light by emitting light and emit light other than having a light source that emits light.

  The guiding means 2 shown in FIG. 3-13 is configured as a wire 2q connected in series. This guiding means 2 guides the movement of the self-propelled device by hooking a hook provided in the self-propelled device on the wire 2q. In addition, as a structure for attaching the wire 2q, in the present embodiment, the stopper 2r through which the wire 2q passes is used, but the structure of the stopper 2r is not limited.

  The guide means 2 shown in FIG. 3-14 is configured as a protrusion 2s provided intermittently. The guiding means 2 guides the movement of the self-propelled device with the protrusion 2s as a mark. Further, since the protrusion 2s is formed with the protruding piece 2t around the tip, the protruding piece 2t can be hung on the protruding piece 2t to hold the weight of the self-propelled device.

  The guide means 2 shown in FIG. 3-15 is configured as a cloud platform 2u provided intermittently. This guide means 2 guides the movement of the self-propelled device by gripping the platform 2u with an arm mechanism provided in the self-propelled device.

  The guide means 2 shown in FIG. 3-16 is configured as a tunnel 2v provided continuously. The guiding means 2 guides the movement of the self-propelled device by detecting the position of the tunnel 2v by a sensor (for example, an ultrasonic sensor) provided in the self-propelled device. Further, the movement of the self-propelled device may be guided by flowing a fluid through the tunnel 2v and detecting the temperature and sound thereof. Further, the movement of the self-propelled device may be guided by flowing a fluid containing a radioactive element through the tunnel 2v and detecting the radiation.

  The guide means 2 having such a configuration is installed on a structure before being contaminated with radioactive material, a structure before being exposed to radiation and activated, or a structure contaminated with radioactive material. “To be contaminated with radioactive material” means that it can be decontaminated by attaching and contaminating the radioactive material (being in a radiation environment). In addition, “to be activated by exposure to radiation” means that a substance (metal) is activated by exposure to radiation for a long period of time, and can itself emit radiation, and cannot be decontaminated. It means that there is.

  As described above, the nuclear power facility 1 of the present embodiment described above is provided with the guide means 2 that guides the movement of the self-propelled device to the assumed maintenance site in the reactor vessel 11 that is a structure.

  According to this nuclear power facility 1, since the guiding means 2 is provided in the structure, it is possible to prevent an operator from entering the position of the maintenance site in the structure. As a result, it is possible to safely and easily introduce a self-propelled device that performs maintenance work in the structure. If the guide means 2 is provided in advance in the structure, there is no need to install a means for guiding the movement of the self-propelled device when performing maintenance work.

  Moreover, in the nuclear power facility 1 of this Embodiment, it is preferable that the guide means 2 is provided from the carry-in entrance for carrying the self-propelled device into the structure to the maintenance site in the structure. Here, in the present embodiment, the carry-in port is an opening 11g in the upper portion of the vessel main body 11a in the nuclear reactor vessel 11, and as shown in FIG. 2, the guide means 2 is provided in the opening 11g of the vessel main body 11a. The guide means 2 extends from the opening 11g to the maintenance site.

  According to this nuclear power facility 1, the worker only has to enter the opening 11 g (carry-in port), so that it is possible to reduce the irradiation of radiation to the worker.

  Further, in the nuclear power facility 1 of the present embodiment, the guide means 2 is provided from the outside of the structure to the maintenance site in the structure via the carry-in port for carrying the self-propelled device into the structure. Is preferred. That is, as shown in FIG. 2, the guide means 2 extends from the opening 11g to the outside of the container body 11a.

  According to this nuclear power facility 1, since the worker does not enter the opening 11g (carry-in port), it is possible to extremely reduce the irradiation of radiation to the worker.

  Further, in the nuclear power facility 1 of the present embodiment, it is preferable that the maintenance site is the welded portion 11f and the guide means 2 is provided along the welded portion 11f.

  The welded part 11f is a main part as a maintenance part for maintaining soundness in the nuclear power facility 1, and by providing the guide means 2 along the welded part 11f, the welded part 11f is automatically maintained. The effect of introducing the traveling device safely and easily can be remarkably obtained.

[Embodiment 2]
4 and 5 are schematic views of the pressurizer in the nuclear facility shown in FIG. In FIG. 4 and FIG. 5, the internal container structure is omitted, and only the pressurization container 12 a of the pressurizer 12 is shown. The pressurizer 12 has a pressurizing container 12a having a cylindrical shape in which an upper portion and a lower portion are formed in a hemispherical shape and closed. The pressure vessel 12a is provided with a surge tube 12b connected to the primary cooling system at the lower portion thereof. The pressure vessel 12a has a spray nozzle 12c connected to a spray nozzle (not shown) for reducing the pressure in the pressure vessel 12a at the upper portion thereof, and the pressure in the pressure vessel 12a is too high. A pressure relief valve nozzle 12d to which a pressure relief valve (not shown) for releasing pressure is connected, a safety valve nozzle 12e to which a safety valve (not shown) functioning as a backup of the pressure relief valve is connected, pressurization A manhole 12f is provided in the container 12a for an operator to enter and exit.

  Guide means 2 is provided in the pressurized container 12a. The guiding means 2 guides the movement of the self-propelled device (not shown) to the assumed maintenance site in the pressurizer 12. In addition, as a self-propelled device, an inspection device for inspecting a maintenance part, an inspection device for inspecting the maintenance part, a replacement device for maintenance replacement required for the result of inspection and inspection, a cutting device for cutting the part for repair, There are welding devices that weld after cutting. Hereinafter, work including inspection, inspection, replacement or repair in the maintenance site is referred to as maintenance work.

  The assumed maintenance site is mainly the welded portion 12g. The welding part 12g exists between the surge tube 12b and each nozzle stand 12c, 12d, 12e, and the pressurized container 12a. Moreover, the welding part 12g is a connection location of pressurization container 12a itself, Comprising: For example, it exists between a cylindrical shape part and a hemispherical part. The guide means 2 is disposed along the weld line of the welded part 12g as a maintenance site. The maintenance site is not limited to the welded portion 12g, and may be a site that is assumed to perform maintenance work in the reactor vessel (pressure vessel) 11.

  Moreover, the guide means 2 is arrange | positioned at the inner periphery of the pressurized container 12a so that each part along the welding part 12g may be relayed. In this Embodiment, while arrange | positioning along the circular shape of the cylinder of the pressurized container 12a, it arrange | positions from this circular shape to the part along the welding part 12g, and connects the parts along a circular shape mutually. Are arranged as follows.

  Specific examples of the guide means 2 have been described above with reference to FIGS.

  As described above, the nuclear power facility 1 according to the present embodiment described above is provided with the guide means 2 that guides the movement of the self-propelled device to the assumed maintenance site in the pressurizer 12 that is a structure.

  According to this nuclear power facility 1, since the guiding means 2 is provided in the structure, it is possible to prevent an operator from entering the position of the maintenance site in the structure. As a result, it is possible to safely and easily introduce a self-propelled device that performs maintenance work in the structure. If the guide means 2 is provided in advance in the structure, there is no need to install a means for guiding the movement of the self-propelled device when performing maintenance work.

  Moreover, in the nuclear power facility 1 of this Embodiment, it is preferable that the guide means 2 is provided from the carry-in entrance for carrying the self-propelled device into the structure to the maintenance site in the structure. Here, in the present embodiment, the carry-in port is a manhole 12f of the pressurization container 12a in the pressurizer 12, and the guide means 2 extends to the manhole 12f as shown in FIGS. The guide means 2 extends from the manhole 12f to the maintenance site.

  According to this nuclear power facility 1, the worker only needs to enter the manhole 12 f (carry-in entrance), so that it is possible to reduce the irradiation of radiation to the worker.

  Further, in the nuclear power facility 1 of the present embodiment, the guide means 2 is provided from the outside of the structure to the maintenance site in the structure via the carry-in port for carrying the self-propelled device into the structure. Is preferred. That is, as shown in FIGS. 4 and 5, the guide means 2 extends from the manhole 12f to the outside of the pressurized container 12a.

  According to this nuclear power facility 1, since the worker does not enter the manhole 12f (carry-in entrance), the irradiation of radiation to the worker can be extremely reduced.

  Moreover, in the nuclear power facility 1 of this Embodiment, it is preferable that a maintenance site | part is the welding part 12g and the guide means 2 is provided along the welding part 12g.

  The welded part 12g is a main part as a maintenance part for maintaining soundness in the nuclear power plant 1, and by providing the guide means 2 along the welded part 12g, the welded part 12g is automatically maintained. The effect of introducing the traveling device safely and easily can be remarkably obtained.

[Embodiment 3]
As shown in FIG. 1, the steam generator 13 is provided with an inlet-side water chamber 13a and an outlet-side water chamber 13b via a partition plate 13c in a lower part formed in a hemispherical shape. The ceiling part of the inlet side water chamber 13a and the outlet side water chamber 13b is provided with a tube plate 13d that divides the upper portion of the steam generator 13 from the inlet side water chamber 13a and the outlet side water chamber 13b. This tube sheet 13d supports the end portion of the heat transfer tube 13e formed in an inverted U shape so as to connect the inlet side water chamber 13a and the outlet side water chamber 13b. The inlet side water chamber 13a is provided with an inlet nozzle 13f, and the inlet side primary coolant pipe 15 is connected to the inlet nozzle 13f by welding. On the other hand, the outlet side water chamber 13b is provided with an outlet nozzle 13g, and the outlet side primary coolant pipe 15 is welded to the outlet nozzle 13g. In addition, the inlet-side water chamber 13a and the outlet-side water chamber 13b are provided with manholes 13h (see FIGS. 6 and 7) for an operator to enter and exit the inlet-side water chamber 13a and the outlet-side water chamber 13b. .

  6 and 7 are schematic views of the steam generator in the nuclear facility shown in FIG. 6 and 7, only one water chamber (for example, the outlet-side water chamber 13b) is shown, but the other water chamber (for example, the inlet-side water chamber 13a) is similarly configured.

  As shown in FIGS. 6 and 7, the guide means 2 is provided in the outlet water chamber 13 b of the steam generator 13. The guiding means 2 guides the movement of the self-propelled device (not shown) to the assumed maintenance site in the outlet water chamber 13b of the steam generator 13. In addition, as a self-propelled device, an inspection device for inspecting a maintenance part, an inspection device for inspecting the maintenance part, a replacement device for maintenance replacement required for the result of inspection and inspection, a cutting device for cutting the part for repair, There are welding devices that weld after cutting. Hereinafter, work including inspection, inspection, replacement or repair in the maintenance site is referred to as maintenance work.

  The assumed maintenance site is mainly the welded portion 13i. The welding part 13i exists between the primary coolant pipe 15 and the inlet nozzle 13f, or between the primary coolant pipe 15 and the outlet nozzle 13g. The welded portion 13i exists between the inlet-side water chamber 13a and the inlet nozzle 13f, or between the outlet-side water chamber 13b and the outlet nozzle 13g. Moreover, the welding part 13i exists between water chamber 13a, 13b and the partition plate 13c, and between water chamber 13a, 13b and the tube sheet 13d. The guide means 2 is disposed along the weld line of the welded portion 13i as the maintenance site. The maintenance site is not limited to the welded portion 13i, and may be a site that is assumed to perform maintenance work in the reactor vessel (pressure vessel) 11.

  Moreover, the guide means 2 is arrange | positioned at the inner periphery of the exit side water chamber 13b so that each part along the welding part 13i may be relayed.

  Specific examples of the guide means 2 have been described above with reference to FIGS.

  As described above, the nuclear power facility 1 according to the present embodiment described above is provided with the guide means 2 that guides the movement of the self-propelled device to the assumed maintenance site in the steam generator 13 that is a structure.

  According to this nuclear power facility 1, since the guiding means 2 is provided in the structure, it is possible to prevent an operator from entering the position of the maintenance site in the structure. As a result, it is possible to safely and easily introduce a self-propelled device that performs maintenance work in the structure. If the guide means 2 is provided in advance in the structure, there is no need to install a means for guiding the movement of the self-propelled device when performing maintenance work.

  Moreover, in the nuclear power facility 1 of this Embodiment, it is preferable that the guide means 2 is provided from the carry-in entrance for carrying the self-propelled device into the structure to the maintenance site in the structure. Here, in the present embodiment, the carry-in port is a manhole 13h provided in each of the water chambers 13a and 13b. As shown in FIG. 6, the guide means 2 extends in the manhole 13h. The guide means 2 extends from the manhole 13h to the maintenance site. Further, the carry-in port is a machine hole 13j provided in each of the water chambers 13a and 13b in the present embodiment. The machine hall 13j is dedicated for carrying the self-propelled device into the structure rather than entering and leaving the worker. The machine hole 13j is provided in a portion where there is no scaffold inside each of the water chambers 13a and 13b, and is provided in the middle of the guide means 2 and closer to the maintenance site than the manhole 13h. That is, by loading the self-propelled device from the machine hole 13j, the self-propelled device can be sent to the maintenance site more quickly than the manhole 13h.

  According to this nuclear power facility 1, since the worker only has to enter the carry-in entrance such as the manhole 13 h and the machine hall 13 j, it is possible to reduce the irradiation of radiation to the worker.

  Further, in the nuclear power facility 1 of the present embodiment, the guide means 2 is provided from the outside of the structure to the maintenance site in the structure via the carry-in port for carrying the self-propelled device into the structure. Is preferred. That is, as shown in FIG. 6, the guide means 2 extends from the manhole 13h and the machine hall 13j to the outside of the water chambers 13a and 13b.

  According to this nuclear power facility 1, since the worker does not enter the carry-in entrances such as the manhole 13 h and the machine hall 13 j, it is possible to extremely reduce the irradiation of radiation to the worker.

  Moreover, in the nuclear power plant 1 of this Embodiment, it is preferable that a maintenance site | part is the welding part 13i and the guide means 2 is provided along the welding part 13i.

  The welded part 13i is a main part as a maintenance part for maintaining the soundness in the nuclear power facility 1, and by providing the guide means 2 along the welded part 13i, the welded part 13i is automatically maintained. The effect of introducing the traveling device safely and easily can be remarkably obtained.

[Embodiment 4]
8 to 10 are schematic views of piping in the nuclear facility shown in FIG. As shown in FIG. 8, the pipes (in the present embodiment, the primary coolant pipe 15 is shown as an example of the pipe, and the same reference numerals are attached), and each straight pipe 15a is formed in an approximately L shape via the bent pipe 15b. As shown in FIG. 9, the straight pipes 15c and 15d having different thicknesses are connected via the variable diameter pipe 15e, and as shown in FIG. 10, the straight pipe 15f is another straight pipe 15g. For example, there is a configuration in which the side portion is connected via a branch pipe 15h. Although not clearly shown in the figure, the pipe 15 is provided with a manhole for an operator to enter and exit the pipe 15.

  The pipe 15 is provided with guide means 2. The guiding means 2 guides the movement of the self-propelled device (not shown) to the assumed maintenance site in the pipe 15. In addition, as a self-propelled device, an inspection device for inspecting a maintenance part, an inspection device for inspecting the maintenance part, a replacement device for maintenance replacement required for the result of inspection and inspection, a cutting device for cutting the part for repair, There are welding devices that weld after cutting. Hereinafter, work including inspection, inspection, replacement or repair in the maintenance site is referred to as maintenance work.

  The assumed maintenance site is mainly the welded portion 15i. As shown in FIG. 8, the welded portion 15i includes a connecting portion between each straight tube 15a and the bent tube 15b, as shown in FIG. 9, a connecting portion between the straight tubes 15c and 15d and the variable diameter tube 15e, As shown, it exists in the connection part of the straight pipe 15f and the branch pipe 15h. The guide means 2 is disposed along the weld line of the welded portion 15i as the maintenance site. The maintenance site is not limited to the welded portion 15 i, but may be any site assuming that maintenance work is performed in the reactor vessel (pressure vessel) 11.

  Moreover, the guide means 2 is arrange | positioned at the inner periphery of the piping 15 so that each part along the welding part 15i may be relayed.

  Specific examples of the guide means 2 have been described above with reference to FIGS.

  As described above, the nuclear power facility 1 according to the present embodiment described above is provided with the guide means 2 that guides the movement of the self-propelled device with respect to the assumed maintenance site in the pipe 15 that is a structure.

  According to this nuclear power facility 1, since the guiding means 2 is provided in the structure, it is possible to prevent an operator from entering the position of the maintenance site in the structure. As a result, it is possible to safely and easily introduce a self-propelled device that performs maintenance work in the structure. If the guide means 2 is provided in advance in the structure, there is no need to install a means for guiding the movement of the self-propelled device when performing maintenance work.

  Moreover, in the nuclear power facility 1 of this Embodiment, it is preferable that the guide means 2 is provided from the carry-in entrance for carrying the self-propelled device into the structure to the maintenance site in the structure. Here, in the present embodiment, the carry-in port is a manhole (not shown) provided in the pipe 15, and the guide means 2 extends from the manhole to the maintenance site. Further, the carry-in port is a machine hall provided in the pipe 15 although not shown in the drawing. The machine hall is dedicated to carrying the self-propelled device into the structure, not to the worker. This machine hole is provided in a portion where there is no scaffold inside each pipe 15, and is provided in the middle of the guide means 2 and closer to the maintenance site than the manhole. That is, by loading the self-propelled device from the machine hall, the self-propelled device can be sent to the maintenance site more quickly than the manhole.

  According to this nuclear power facility 1, the worker only has to enter a carry-in entrance such as a manhole or a machine hall, so that it is possible to reduce the irradiation of radiation to the worker.

  Further, in the nuclear power facility 1 of the present embodiment, the guide means 2 is provided from the outside of the structure to the maintenance site in the structure via the carry-in port for carrying the self-propelled device into the structure. Is preferred. That is, although not shown in the drawing, the guide means 2 extends from the manhole or machine hall to the outside of the pipe 15.

  According to this nuclear power facility 1, since the worker does not enter even a carry-in entrance such as a manhole or a machine hall, the irradiation of radiation to the worker can be extremely reduced.

  Further, in the nuclear power facility 1 of the present embodiment, it is preferable that the maintenance site is the welded portion 15i, and the guide means 2 is provided along the welded portion 15i.

  The welded part 15i is a main part as a maintenance part for maintaining soundness in the nuclear power facility 1. By providing the guide means 2 along the welded part 15i, the welded part 15i is self-maintaining the welded part 15i. The effect of introducing the traveling device safely and easily can be remarkably obtained.

  In each of the embodiments described above, a pressurized water reactor (PWR) has been described as an applied nuclear facility, but a boiling water reactor (BWR) or a fast breeder reactor (FBR) (Reactor).

  As described above, the nuclear power facility according to the present invention is suitable for safely and easily introducing a self-propelled device that performs maintenance work into a structure.

1 Nuclear equipment 11 Reactor vessel 11f Welded part (maintenance part)
11g opening (carriage entrance)
12 Pressurizer 12f Manhole (carriage entrance)
12g welded part (maintenance part)
13 Steam generator 13h Manhole (inlet)
13i welded part (maintenance part)
13j Machine hall (carriage entrance)
15 Primary coolant pipe (pipe)
15i welded part (maintenance part)
2 guiding means 2a protruding piece 2b groove bottom 2c protruding piece 2d protruding piece 2e inclined surface 2f protruding piece 2g inclined surface 2h hole 2i hole 2j protruding piece 2k magnet 2m line 2n line 2p luminous body 2q wire 2r stopper 2s protrusion 2t protruding piece 2u Yundai 2v tunnel

Claims (9)

  Guiding means for guiding the movement of the device to the inner surface of the coolant circulation system in the structure before being contaminated with radioactive material or before being exposed to radiation and activated. A featured nuclear facility.   Guide means for guiding the movement of the apparatus to an assumed maintenance site in a structure before being contaminated with radioactive material or before being exposed to radiation and activated. Nuclear equipment.   2. The structure according to claim 1, wherein a reactor vessel, a pressurizer, a steam generator, and a pump are part of a circulation path of a primary coolant configured by sequentially connecting a primary coolant pipe. Or the nuclear facility described in 2;   The nuclear facility according to any one of claims 1 to 3, wherein the guide means is installed in a portion where a path of the coolant changes depending on a diameter, a direction, and an entrance / exit.   The guide means includes a series of grooves, a series of T-shaped protrusions connected in series, a series of inverted T-shaped grooves connected to a series of rectangular protrusions, and a series of Protruding pieces projecting oppositely on both sides of the connected projection, intermittently provided holes, intermittently provided magnets, a series of continuous lines, and intermittently provided belts Line, intermittently provided strip-like light emitters, continuous wires, intermittently provided protrusions, intermittently provided cloud ladders, or continuously provided tunnels The nuclear facility according to any one of claims 1 to 4, wherein:   The guide means is configured as a groove, hole, embedding or tunnel without projecting from the surface of the structure, or is configured as a band-shaped line or a band-shaped light emitter so as to be flush with the surface of the structure. The nuclear facility according to any one of claims 1 to 4, wherein the nuclear facility is provided.   The nuclear power facility according to any one of claims 1 to 6, wherein the guide means is provided in the structure from a carry-in port for carrying the device into the structure.   The said guide means is provided in the said structure through the carrying-in entrance which carries in the said apparatus into the said structure from the said structure outside, The any one of Claims 1-6 characterized by the above-mentioned. The nuclear equipment described in 1.   The nuclear facility according to claim 1, wherein the guide unit is provided along the welded portion.

Images