WO2001069609A1 - Procede de manipulation d'equipement - Google Patents
Procede de manipulation d'equipement Download PDFInfo
- Publication number
- WO2001069609A1 WO2001069609A1 PCT/JP2000/001573 JP0001573W WO0169609A1 WO 2001069609 A1 WO2001069609 A1 WO 2001069609A1 JP 0001573 W JP0001573 W JP 0001573W WO 0169609 A1 WO0169609 A1 WO 0169609A1
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- WO
- WIPO (PCT)
- Prior art keywords
- nozzle
- rpv
- new
- reactor
- reactor vessel
- Prior art date
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Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
- G21D1/003—Nuclear facilities decommissioning arrangements
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/02—Details of handling arrangements
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Definitions
- the present invention relates to a method for handling equipment in a nuclear power plant or a thermal power plant, and more particularly to a method suitable for replacing a reactor vessel of a nuclear power plant.
- the RPV to which the above-described conventional technology is applied is a large-sized device having a height of about 25 m, a diameter of about 6 m, and a weight of about 100 tons.
- the RPV is equipped with approximately 50 to 60 nozzles, such as main steam outlet nozzles and water supply nozzles, and piping is connected to these nozzles.
- the outer diameter of the pipe can be up to about 600 mm.
- a first object of the present invention is to replace a nozzle of a new reactor vessel with a new reactor vessel without re-use of existing pipes while performing a replacement operation of a reactor vessel in a nuclear power plant without providing an adjustment pipe for dimension adjustment. It is an object of the present invention to provide a method of handling equipment which can be connected to an existing pipe and can greatly shorten a work period.
- a second object of the present invention is to provide a device that can easily install a new device at the same position as an existing device (old device) when replacing a nuclear plant such as a reactor vessel of a nuclear plant or a device for a thermal power plant.
- the purpose is to provide a handling method.
- the present invention for achieving the first object measures a position and a size of a nozzle of a new reactor vessel outside a reactor terrestrial planet, and is provided in a reactor vessel based on the measured values. Beveling of existing pipes (existing pipes), and then carrying the new reactor vessel into a predetermined position in the reactor building. After carrying in the new reactor vessel, the nozzle of the new reactor vessel is joined to the pipe that has been grooved. The nozzle position of the new reactor vessel is measured using the three-dimensional reference point provided on the new reactor vessel. Preferably, the nozzle position of the existing reactor vessel is measured with the existing reactor vessel installed, and a new reactor vessel reflecting the measured nozzle position is manufactured. The nozzle position of the existing reactor vessel is measured using the reference point of the three-dimensional position provided in the reactor containment vessel.
- the reference point of the three-dimensional position provided on the reactor containment vessel and the three-dimensional position provided on the new Monitor and set the relative position to the reference point.
- an eccentric amount of a bolt to which an existing device is fixed and a mounting hole thereof is measured in a state where the existing device is installed. Attach a guide cap that reflects the amount of eccentricity to the fixed part of the device, and install a new device with the guide cap installed.
- Another aspect of the present invention for achieving the second object is to measure a relative position between the existing device and a surrounding structure using a positioning device provided at a plurality of locations in a state where the existing device is installed, Using the positioning devices provided at the plurality of locations, new devices are installed at the measured relative positions.
- FIG. 1 is a flowchart showing a first embodiment in which the present invention is applied to a method of replacing a reactor pressure vessel (RPV) of a boiling water reactor.
- RSV reactor pressure vessel
- FIG. 2 is a schematic longitudinal sectional view of a nuclear reactor star to which the method of FIG. 1 is applied.
- FIG. 3 is a schematic longitudinal sectional view around the containment vessel of FIG.
- FIG. 4 is a detailed longitudinal sectional view of the RPV of FIG.
- FIG. 5a is a longitudinal sectional view of a recirculation outlet nozzle and a recirculation outlet pipe connected thereto.
- FIG. 5b is a view showing a state where a joint between the nozzle safe end and the recirculation outlet pipe is cut in step S6 of FIG.
- FIG. 5c is a longitudinal sectional view of the nozzle portion showing a state in which the RPV is carried out after the nozzle is cut in step S8 in FIG.
- FIG. 5d is a longitudinal sectional view of the nozzle portion showing a state in which a new RPV is being loaded in step S12 of FIG.
- FIG. 5e is a vertical cross-sectional view of the nozzle portion showing a state in which the nozzle line of the new RPV is connected to the old connection pipe in step S13 of FIG.
- FIG. 6a is a schematic perspective view of the inside of the PCV showing a state where the nozzle position of the recirculation outlet nozzle is three-dimensionally measured in step S O of FIG.
- FIG. 6b is a schematic perspective view around the nozzle of FIG. 6a.
- FIG. 6c is a diagram showing a state in which the position and dimension of the nozzle of the new RPV are three-dimensionally measured in step S9 of FIG.
- FIG. 7a is a longitudinal sectional view of a recirculation outlet nozzle and a recirculation outlet pipe connected thereto.
- FIG. 7b is a longitudinal sectional view of the nozzle portion showing a state where the joint portion is cut in step S6 of FIG.
- FIG. 7c is a longitudinal sectional view of the nozzle portion showing a state in which the RPV is being carried out in step S8 in FIG.
- FIG. 7d is a longitudinal sectional view of the nozzle portion showing a state in which a new RPV is being loaded in step S12 of FIG.
- FIG. 7e is a longitudinal sectional view of the nozzle portion showing a state before the nozzle safe end is attached in step S13 of FIG.
- FIG. 7f is a vertical cross-sectional view of the nozzle portion showing a state after the nozzle safe fend is attached in step S13 of FIG.
- FIG. 8a is a schematic longitudinal sectional view of the lower portion of the RPV showing a state where the positioning device is mounted between the RPV skirt flange and the inner wall of the RSW.
- FIG. 8b is a detailed view of part B of FIG. 8a.
- FIG. 9a is a longitudinal sectional view of the RPV base showing a state in which the RPV skirt flange is fixed to the ring girder.
- FIG. 9b is a vertical cross-sectional view of the RPV base showing a situation where the reference bolt for measuring the amount of eccentricity is attached in step S7 of FIG.
- FIG. 9c is a longitudinal sectional view of the RPV foundation showing the situation after the old RPV has been carried out in step S8 of FIG.
- FIG. 9d is a longitudinal sectional view of the RPV foundation showing a state where the guide cap is attached to the reference bolt in step S11 of FIG.
- FIG. 9e is a longitudinal sectional view of the RPV foundation showing a state where the RPV skirt flange of the new RPV is set on the reference bolt with the guide cap attached thereto in step S12 of FIG.
- FIG. 9f is a longitudinal sectional view of the RPV base showing a state in which the guide cap is removed and the RPV skirt flange and the ring girder are fixed in step S14 of FIG.
- FIG. 10a is a longitudinal sectional view of the RPV base showing a state in which the RPV skirt flange and the ring plate are directly fixed to the pedestal.
- FIG. 10b is a longitudinal sectional view of the RPV foundation showing a state in which the guide cap is attached to the foundation port in step S11 of FIG.
- Fig. 10c is a longitudinal cross-sectional view of the RPV foundation showing the state in which the RPV skirt flange of the new RPV is set on the foundation bolt with the guide cap attached in step S12 of Fig. 1. It is.
- Fig. 11 shows that the RPV with the radiation shield It is a key map showing the state where it is carried out of a building.
- Fig. 12 is a schematic diagram showing a state in which a large crane is used to carry out the RPV from the reactor building and carry it into the RPV storage room installed outdoors.
- FIG. 1 is a flowchart showing an RPV replacement method of the first embodiment.
- FIG. 2 is a schematic longitudinal sectional view of a nuclear reactor star to which the method of FIG. 1 is applied.
- FIG. 3 is a schematic longitudinal sectional view around the reactor containment vessel (hereinafter referred to as PCV) of FIG.
- FIG. 4 is a detailed longitudinal sectional view of the RPV of FIG.
- PCV 16 for storing RPV 1 spent fuel pool 33 for storing spent fuel, and equipment for storing reactor internals (structures in RP VI) Pools 38, etc. are provided in the reactor building 31.
- the reactor well 32 provided above the PCV 16 is filled with water when the reactor internals are taken out or when fuel is changed.
- a fuel rack 33a for storing spent fuel is provided inside the spent fuel boule 33.
- RPV 1 is mounted on its underlying RPV pedestal 18.
- a reactor shield wall (hereinafter referred to as RSW) 17 is provided to shield radiation from the RPVI.
- nozzles such as the main steam nozzle 9, the water supply nozzle 10, the core spray nozzle 11, the recirculation inlet nozzle 12, and the recirculation outlet nozzle 13 are provided on the side wall of the RPV 1.
- Each system piping such as piping 13a is connected to each nozzle.
- Insulation material 14 is provided outside RPV 1.
- the RPV 1 is fixed on the ring girder 25 by a flange bolt 26.
- the ring girder 25 is fixed to the RPV ⁇ distal 18 by a foundation bolt 28.
- a fuel exchange port 15 for partitioning the inside of the PCV 16 and a bulk head plate 19 are provided on the top of the PCV 16.
- a control rod drive mechanism (CRD) housing 23 and an in-core neutron flux module (hereinafter referred to as ICM) housing 24 are provided in the RPV pedestal 18.
- R SW 17 is fixed to RPV pedestal 18 by foundation bolts 29.
- a PCV space stabilizer 30 which is a seismic support for the PCV 16 and an RPV space stabilizer 30a which is a seismic support for the RPV 1 are provided above the RSW 17.
- RP V1 is equipped with various in-furnace Z-furnace auxiliary equipment.
- Furnace Z Ancillary external equipment consists of the furnace internal structure installed inside the RPV 1 and structures other than the furnace internal structure.
- the reactor internal structure 2 is composed of a steam dryer 3, a shroud head (including a steam separator) 4, a core shroud 5, a core support plate 6, an upper lattice plate 7, a jet pump 8, and the like.
- the in-furnace structure 2 accommodates the fuel 27 that forms the core region 2a (only the-part is shown), equipment such as control rods 20b, and guides the cooling water flowing from the nozzle into the core region 2a. And forms a circulation path for cooling water.
- the above-described various nozzles 9 to 13 and the like are provided.
- RPV head Reactor pressure vessel lid
- Head 37 is fixed to RPV 1 by a stud port 37a attached to flange 37b.
- control A CRD housing 23 for accommodating the rod drive mechanism (CRD) 20, an ICM housing 24 for accommodating the ICM 21 and an RPV skirt lb are provided at the bottom of the RPV 1. .
- the shading 0 housing 23 and the ICM housing 24 are structures other than the furnace internal structure.
- step S O during the periodic inspection before RPV replacement work, the cutting position (3D position) of the nozzle of the existing reactor pressure vessel (hereinafter referred to as the old RPV) is measured.
- the new RPV is manufactured by reflecting the measured nozzle position on the nozzle position of the new reactor pressure vessel (hereinafter referred to as “new RPV”).
- the timing of measuring the nozzle position in step S0 is determined by the production period of the new RPV.
- FIG. 5a is a longitudinal sectional view of the recirculation outlet nozzle 13 and the recirculation outlet pipe 13 connected thereto.
- the nozzle safe 13 b is provided between the recirculation outlet nozzle 13 and the recirculation outlet pipe 13 a, and the nozzle safe fend 13 b is a recirculation outlet pipe serving as a connection pipe. This is to prevent the breakage or damage of a from affecting the recirculation outlet nozzle 13 when it occurs.
- 14 is a scale? Insulation material, 14a is nozzle insulation material, 14b is pipe insulation material, 17 is R SW, 17a is RSW nozzle opening RSW plug, 17b is R SW plug 17a
- This is a shield block that is removably installed in the building.
- the junction 13 c between the nozzle safety fend 13 b and the recirculation outlet pipe (connection pipe) 13 a is located in the space between the RPV 1 and the RSW 17. For this reason, cut the joint 1 3 c When the RPV 1 is unloaded, the nozzle fend 13 b does not interfere with the RSW 17.
- the three-dimensional measurement of the nozzle position is performed with the shielding block 17b of RSW17 in Fig. 5a removed and the nozzle insulation material 14a and pipe insulation material 14b removed.
- the cutting position of the nozzle is located inside the RSW plug 17a. Therefore, a plurality of reference points (reference points of three-dimensional positions) 81 are provided on the inner surface of the side wall of the PCV 16 and the relative position of each nozzle with respect to the reference point 81 (hereinafter referred to as a first relative position) is measured. .
- the coordinate analyzer 82 processes the measured value of the first relative position of each nozzle in a short time, and calculates a relative position (hereinafter referred to as a second relative position) with respect to a reference point (reference point of a three-dimensional position) provided in the RPVI. ).
- a relative position hereinafter referred to as a second relative position
- a reference point reference point of a three-dimensional position
- FIG. 6a is a schematic perspective view of the inside of the PCV 16 showing a state where the nozzle position of the recirculation outlet nozzle 13 is three-dimensionally measured.
- 80 is a surveying instrument for measuring a three-dimensional position
- 81 is a reference point
- 82 is a coordinate analyzer.
- the coordinate analyzer 82 is installed outside the PCV 16 (for example, in a clean area such as an office).
- FIG. 6b is a schematic perspective view around the nozzle of FIG. 6a.
- reference numeral 81a denotes a reference origin provided in RPV 1
- reference numeral 83 denotes a reflection target for reflecting light waves.
- two reflection evening targets 83 are installed at the nozzle measurement points.
- the reference origin 81a is set as the origin of the three-dimensional coordinates on the body of the RPV 1 (RPV body).
- the reference point 81 is set on the inner surface of the PCV, and the three-dimensional coordinates of each reference point 81 with respect to the reference origin 81a are measured using a surveying instrument 80a.
- the surveying instrument 80 includes an angle measuring unit for measuring an angle and a distance measuring unit for measuring a distance.
- the data recording device built into the surveying instrument 80 records three-dimensional coordinate data on the first relative position of the nozzle cutting position (relative position in the coordinate system of the reference point 81).
- the coordinate analysis device 82 inputs the coordinate data relating to the first relative position, and converts the coordinate data into coordinate data relating to the second relative position with respect to the reference origin 81a of the RPV cylinder.
- the position of the same reflection target 83 is measured using two surveying instruments 80.
- a plurality of reflection targets 83 are arranged evenly on this circumference. It is preferable to measure.
- a rotating reflection target, a two-point reflection target, or the like can be used to measure the position of a point that becomes a shadow of another structure. In this way, the cutting position of the nozzle is measured.
- the reference origin 81a is set to the body of the RPV 1, but the present invention is not limited to this. That is, the reference origin 8la may be provided on the RPV head flange, nozzle, or the like of RPV1.
- step S1 the generator is disconnected at the beginning of the periodic inspection for replacing RPV1.
- step S2 the reactor is opened.
- remove the RPV head 37 RPV head Removal work removal of the steam dryer to remove the steam dryer 3, and removal of the shroud head to remove the shroud head 4 are performed.
- Opening the reactor is a critical operation required to handle fuel 27 in the reactor core.
- the steam dryer 3 and the shroud head 4 are moved to the equipment pool 38 and reused.
- step S3 an operation of removing all the fuel 27 from the core is performed.
- all the fuel 27 loaded in the core is moved to the rack 33 a in the spent fuel pool 33.
- steps S4 structures around the RPV, such as the bulk head plate 19 and the refueling bellows 15, are dismantled.
- step S5 the shield around the nozzle of the old RPV and the heat insulating material are removed.
- step S O remove the shielding block 17 b of the R SW 17 in FIG. 5a, and remove the nozzle insulation material 14 a and the pipe insulation material 14 b.
- step S6 the nozzle of the old RPV and the connection pipe are cut.
- FIG. 5b shows, as an example, a state in which a joint 13c between the nozzle safe end 13b and the recirculation outlet pipe 13a is cut.
- step S7 the amount of eccentricity of the old RPV is measured. The details will be described later.
- FIG. 5c is a longitudinal sectional view of the nozzle portion showing a state in which the RPV 1 is carried out after the nozzle is cut.
- a pipe moving device 71 for example, a chain block, jack, etc.
- the closing plate 13 d is attached to the nozzle fender 13 b, and the RPV 1 is carried out with the nozzle fender 13 b attached using a large crane.
- FIG. 11 shows that the RPV 1 with the radiation shield 60 attached is lifted
- FIG. 2 is a schematic view showing a state in which the reactor is unloaded from a reactor building 31.
- 60a is the curing sheet
- 61 is the junction between the RPV sunset bracket 30b and the radiation shield 60
- 31a is the ceiling of the reactor building 31
- the opening, 64, is an openable shirt at the opening 31a
- 63 is a strong back for lifting 1 ⁇ 1.
- FIG. 12 is a schematic diagram showing a state where the RPV 1 is carried out of the reactor building 31 by the large crane 65 and is carried into the RPV storage 66 installed outdoors.
- Step S9 the nozzle position of the manufactured new RPV is three-dimensionally measured outside the reactor building.
- the factory where the new RPV was manufactured is realistic. This measurement is performed using the three-dimensional position measurement device 80 and the coordinate analysis device 82 used in step S0.
- the nozzle ends of the new RPV will be manufactured longer than the nozzles of the old RPV, taking into account the cutting allowance for piping.
- FIG. 6c shows a state in which the position and dimensions (height) of the nozzle (nozzle-end) of the new R P Vln are three-dimensionally measured.
- the measurement method described in Fig. 6b can be used.
- the reference origin 81a provided on the body of the new RPVln is used instead of the reference point 81 of the PCV16.
- step S10 using the three-dimensional measurement data (measured value) of each nozzle of the new RPV 1n, the connection length of the connection pipe to be reused in the PCV 16 (hereinafter referred to as the old connection pipe). Determine the length and perform groove processing of the old connection piping. When determining the connection length, take into account errors during construction (shrinkage due to welding, etc.).
- step S11 a guide cap is set on the base port of the RPV. The details will be described later.
- step S12 using the large crane 65, the new RPV ln is loaded into the reactor building at the position where the old RPV was installed (predetermined position). You. At this time, as in step S8, the old connection pipe is moved to the opposite side of the RPV using the pipe moving device 71, and the gap between the nozzle and the old connection pipe is secured. This makes it easier to carry in the new RPV 1 n.
- Fig. 5d shows that the recirculation outlet pipe 13a to be reused by using the pipe moving device 7 1 is moved to the opposite side of the RPV, and the new RPV 1 n with the new nozzle safe 13 bn is installed.
- step S13 the old connection pipe is returned to the original position, the groove is aligned with the nozzle of the new RPV1n, and the old connection pipe and the nozzle of the new RPV1n are joined by welding.
- FIG. 5e is a longitudinal sectional view of the nozzle portion showing a state in which the nozzle safe end 13n of the new RPV 1n and the old connection pipe 13a are connected.
- step S14 the guide cap set on the foundation bolt of the RPV is removed.
- step S15 the heat insulating materials 14a and 14b around the nozzle, the shielding block 17b of the RSW, and the like are restored.
- the structures around the RPV, such as the bulkhead plate 19 and the refueling bellows 15 will be restored.
- Step S16 fuel loading and nuclear reactor installation will be performed. With the above procedure, the replacement work of the RPV is completed.
- the RPV skirt flange attached to the foundation bolt has a bolt hole larger than the diameter of the foundation bolt. For this reason, when installing the new RPV, there is a possibility that the displacement between before and after replacement may occur due to the difference between the outer diameter of the foundation bolt and the inner diameter of the bolt hole. A method for correcting this displacement will be described below.
- the first method of correcting the displacement of the new RPV is to attach a guide cap that reflects the eccentricity of the old RPV to the foundation bolt of the RPV.
- RPV can be fixed in two ways.
- the first structure is as follows: ⁇ ⁇ Secure the ring girder 25 supporting the foundation bolt embedded in the pedestal 18 and the RPV skirt flange 1 d with the flange bolt 26 a and the nut 26 b Structure.
- the second structure is a structure that directly fixes the RPV skirt flange 1d with the foundation bolt 28 embedded in the pedestal.
- FIG. 9a is a longitudinal sectional view of the RPV base portion showing a state in which the RPV skirt flange 1d is fixed to the ring girder 25 by the flange bolt 26a and the nut 26b.
- the eccentric amount of the RPV in a state where the old RPV is installed is measured in advance in step S7 in FIG.
- the eccentricity is measured by removing the flange bolt 26a, attaching the reference bolt 87, and measuring the distance between the reference bolt 87 and the bolt hole 1e of the RPV skirt flange 1d.
- To install the reference bolt 87 insert the nut 88 into which the base port 28 can be inserted and the nut into which the reference bolt 87 can be inserted. Attach 7 to nut 8 8.
- the distance between the outer surface of the reference port 87 and the inner surface of the bolt hole 1 e of the RPV skirt flange 1 d (hereinafter, referred to as the distance between the reference port and the flange bolt hole) is measured.
- FIG. 9b is a vertical cross-sectional view of the RPV base showing the mounting state of the reference bolt 87.
- Reference port and flange as shown by arrow C-C in Figure 9b
- the intervals between the bolt holes are indicated by a, b, c, and d. That is, the inner gap in the radial method of RPV is a, the outer gap is b, the left gap in the circumferential method of RPV is c, and the right gap is d.
- the left and right sides correspond to the counterclockwise and clockwise sides as viewed from the central axis of the RPV (the left side in Fig. 9b).
- FIG. 9c is a longitudinal sectional view of the RPV base showing the ring girder 25 and the reference bolt 87 after the old RPV is carried out.
- the reference port 87 is attached to a plurality of positions (3 to 4 locations) in the circumferential direction of the RPV, among a plurality of port holes provided in the RPV skirt flange Id. At each position, the eccentricity of the old RPV can be measured by measuring the distance between the reference port and the flange port in the same manner. It is preferable that the position at which the reference bolt 87 is attached be symmetrical with respect to the central axis of the RPV.
- FIG. 9d is a vertical cross-sectional view of the RPV base showing a state in which a guide cap 89 is attached to the reference port 87 after the old RPV is carried out.
- the guide cap 89 has a columnar space in which the reference bolt 87 can be inserted.
- the center axis of this space corresponds to the displacement based on the above four gaps a to d. It is eccentric from the central axis of 7. That is, Guido Yap 89 is formed so that the inner and outer thicknesses in the RPV diameter method are a and b, and the left and right thicknesses in the RPV circumferential method are c and d.
- FIG. 9e shows the RPV base in step S12 of Fig. 1 with the reference port 87 fitted with guide caps 89 and the RPV skirt flange 1dn of the new RPV 1n set.
- step S14 of FIG. 1 the guide cap and the reference port are removed, and the RPV skirt flange and the ring girder are fixed.
- Fig. 9f shows that in step S14 in Fig. 1, the guide cap 89 and the reference bolt 87 are removed, and the flange bolt 26a and the nut 26b are used to connect the RPV skirt flange ldn and the ring guide.
- FIG. 9 is a longitudinal sectional view of the RPV base portion showing a state where the damper 25 is fixed.
- the guide cap that reflects the eccentricity of the old RPV can be used.
- the position deviation at the time of setting the old RPV can be reflected in the setting of the new RPV. That is, the new RPV can be installed at the same position as the old RPV.
- step S7 of FIG. 1 the eccentricity of the RPV when the old RPV is installed is measured in advance. This eccentricity is measured, for example, by removing the nut from the foundation port and measuring the distance between the foundation bolt and the bolt hole in the RPV skirt flange.
- FIG. 4 is a longitudinal sectional view of the RPV foundation showing a state where it is directly fixed to the pedestal 18 by foundation bolts 28 and nuts 28a. The figure shows a state in which one nut 28a has been removed from the foundation bolt 28. In this state, the outer surface of the foundation bolt 28 and the bolt hole 1e of the RPV skirt flange 1d are shown. Measure the distance from the inner surface (hereinafter referred to as the distance between the foundation bolt and the flange bolt hole).
- the distance between the base bolt and the flange bolt hole is indicated by e, f, g, and h, as shown in the D-D view of Fig. 10a. That is, the inner gap in the diameter method of RPV is e, the outer gap is f, the left gap in the circumferential method of RPV is g, and the right gap is h.
- the left and right sides correspond to the counterclockwise and clockwise sides as viewed from the central axis of RPV (the left side in Fig. 10a).
- e the outside in the radial method
- g the left side in the circumferential method
- g> h the right in the circumferential method
- the distance between the foundation bolt and the flange bolt hole is measured at multiple positions (3-4 locations) in the circumferential direction of the RPV, among the multiple bolt holes provided in the RPV skirt flange 1d.
- the eccentricity of the old RPV can be measured by measuring the interval between the base bolt and the flange bolt hole at a plurality of positions in the circumferential direction. It is preferable that the position at which the distance between the base port and the flange bolt hole is measured is a position symmetrical with respect to the central axis of the RPV.
- a guide cap is set on the foundation bolt.
- 10b is a longitudinal sectional view of the RPV foundation showing a state in which the guide cap 89 is attached to the foundation bolt 28 after the old RPV is carried out.
- the guide cap 89 has a cylindrical space in which the foundation bolt 28 can be inserted, and the center axis of this space corresponds to the displacement based on the above four gaps e to h. Eccentric from the center axis of That is, the guide cap 89 is formed such that the inner and outer thicknesses in the RPV diameter method are e and f, and the left and right thicknesses in the RPV circumferential method are g and h. It is fixed to the base port 28 by screws 90.
- Fig. 10c shows the RPV foundation with the RPV skirt flange 1dn of the new RPV ln set on the foundation bolt 28 with the guide cap 89 attached in step S12 of Fig. 1. It is a longitudinal cross-sectional view of a part.
- lcn represents the RPV skirt of the new RPV ln.
- step S14 of FIG. 1 the guide cap is removed, and the RPV skirt flange and the ring plate are fixed.
- FIG. 8a is a schematic vertical sectional view of the lower portion of the RPV showing a state where the positioning device 83 is mounted between the RPV scart flange 1d and the inner wall of the RSW 17;
- FIG. 8b is a detailed view of part B of FIG. 8a.
- the position display device 84 is installed outside the PCV 16 (for example, on the operating floor), and displays the RPV position measured by the positioning device 83.
- the positioning device 83 is symmetrical at a plurality of locations in the circumferential direction of the RPV (for example, four locations of 0 °, 90 °, 180 °, and 270 ° based on a certain circumferential position). Placed in
- step S7 of FIG. 1 the relative positions of the RPV skirt flange 1d and the inner wall of the RSW17 are measured at a plurality of positions in the circumferential direction using the positioning device 83. In this way, the amount of eccentricity in the installation state of the old RPV is measured in advance. In this case, since the guide cap is not used, steps 11 and 14 in FIG. 1 can be omitted.
- step 12 in Fig. 1 the new RPV 1n is set on the ring girder 25 while being suspended by a large crane, and the positioning device 83 is used to set the RPV cut flange 1d and RSW17. Measure the relative position with the inner wall at the same multiple locations as the old RPV. At this time, the measured values of the relative positions of the new RPV at a plurality of locations displayed on the position display device 84 are compared with the measured values of the old RPV previously measured in step S7.
- the position of the new RPV is corrected by the positioning devices 83 installed at multiple locations to match the measured value of the old RPV.
- the correction of the position of the new RPV is performed by adjusting each positioning device 83 while the new RPV ln is slightly lifted by a large crane.
- the measured values of the new RPV and the old RPV are equal, it is not necessary to correct the position of the new RPV.
- the position deviation at the time of setting the old RPV can be reflected in the setting of the new RPV, and the new RPV is placed at the same position as the old RPV.
- the installation positions of the old RPV and the new RPV can be made the same, so that the connection between the new RPV and the existing connection pipe can be easily performed while reusing the existing connection pipe (old connection pipe). be able to. Also, since the existing connection pipe and the new RPV nozzle can be directly connected without using the adjustment pipe, there is no need to manufacture, wait for processing, and carry in the adjustment pipe, greatly shortening the installation period. Furthermore, since the amount of waste in piping can be significantly reduced, the man-hours and storage facilities required for waste disposal can also be reduced.
- steps S0 to S5, S7 to S12, and S14 to S16 in FIG. 1 are the same as those in the first embodiment.
- steps S6 and S13 in FIG. The other steps are the same as those in the first embodiment, and the description is omitted here.
- FIG. 7a is a longitudinal sectional view of the recirculation outlet nozzle 13 and the recirculation outlet pipe 13a connected thereto.
- the nozzle safe end 13 b and recirculation POO / 01573 are connected thereto.
- FIG. 7b is a longitudinal sectional view of the nozzle portion showing a state where the joint portion 13c and the joint portion 13cl are cut.
- FIG. 7c is a vertical cross-sectional view of the nozzle part showing a state in which the RPV 1 is being carried out in step S8 of FIG.
- 13 d is a closing plate attached to the recirculation outlet nozzle 13. As described above, in the present embodiment, the RPV 1 is carried out with the nozzle safe 13b removed.
- step S12 of FIG. 1 a new RPV1n is carried in with the nozzle safe fender removed.
- FIG. 7d is a longitudinal sectional view of the nozzle portion showing a state where the new RPV 1n is being carried in.
- step S13 in Fig. 1 the new RPV recirculation outlet nozzle 13n and the new nozzle safen 13bn are welded and the new nozzle safen 13bn is reused for recirculation outlet piping.
- Weld 1 3 a is
- the new nozzle safe 13bn is longer than the nozzle safe 13b before replacement in consideration of the cutting allowance of the recirculation outlet pipe 13a and the shrinkage during welding. Also, the recirculation outlet pipe 13a is moved to the opposite side of the RPV using the pipe moving device 71 to secure a gap between the recirculation outlet nozzle 13n and the recirculation outlet pipe 13a. This makes it easier to set a new nozzle safe end 13 bn.
- FIG. 7e is a longitudinal sectional view of the nozzle portion showing a state before the nozzle safe fender 13 bn is attached.
- FIG. 7f is a longitudinal sectional view of the nozzle portion showing a state after the nozzle safe 13bn is attached.
- 13 e (broken line) Indicates the end position of the nozzle fend of the old RPV
- 13 f indicates the end position of the nozzle fend of the new RPV.
- the existing connection pipe can be directly connected to the new RPV nozzle without replacing (reusing) the existing connection pipe, so that the same effect as in the first embodiment can be obtained.
- the nozzle position when replacing the RPV, the nozzle position is three-dimensionally measured with the old RPV installed, and the measurement result is reflected in the production of the new RPV.
- the nozzle position is measured three-dimensionally after the new RPV is manufactured, and the length of the existing connection pipe is determined based on the measurement results, and the groove is machined.
- the existing connection pipe and the nozzle of the new RPV can be directly connected without providing an adjustment pipe for dimension adjustment. That is, the existing connection pipe can be reused when replacing the RPV. Since there is no need to use an adjustment pipe, there is no need to manufacture, wait for, and carry in the adjustment pipe, thus greatly shortening the installation period.
- connection pipes are reused as pipes to be connected to the nozzle of the new RPV, so the amount of pipe waste can be reduced by about 50 tons (in the case of a BWR plant with an output of OO MWe class).
- the number of man-hours and storage facilities required for storage can be reduced.
- the period of RPV replacement work can be shortened, and consequently the shutdown period of the nuclear power plant can be shortened.
- step S9 the nozzle position of the new RPV is measured in step S9 after the old RPV is carried out in step S8.
- step S9 may be performed in parallel with steps S1 to S8.
- pressurized water type It is also applicable to the replacement of reactor vessels (RV) in a nuclear reactor (PWR), the replacement of equipment such as heat exchangers or heaters in nuclear power plants and thermal power plants.
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
Selon l'invention, l'un des procédés de manipulation d'équipement consiste à mesurer l'emplacement et la dimension d'une buse d'une nouvelle cuve de réacteur placée hors d'un bâtiment de réacteur, à biseauter les tuyaux (tuyaux existants) installés dans le réservoir de réacteur en fonction des valeurs mesurées, à placer une nouvelle cuve de réacteur en un emplacement spécifié dans le bâtiment de réacteur et à raccorder une buse de la nouvelle cuve de réacteur aux tuyaux biseautés. Ladite buse peut être raccordée aux tuyaux existants sans besoin de régler les dimensions des tuyaux lorsque l'on remplace une cuve de réacteur par une nouvelle dans une centrale atomique, ce qui réduit considérablement le temps requis par les travaux de remplacement.
Priority Applications (2)
Application Number | Priority Date | Filing Date | Title |
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PCT/JP2000/001573 WO2001069609A1 (fr) | 2000-03-15 | 2000-03-15 | Procede de manipulation d'equipement |
JP2001567596A JP4221177B2 (ja) | 2000-03-15 | 2000-03-15 | 機器の取扱方法 |
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PCT/JP2000/001573 WO2001069609A1 (fr) | 2000-03-15 | 2000-03-15 | Procede de manipulation d'equipement |
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WO2001069609A1 true WO2001069609A1 (fr) | 2001-09-20 |
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PCT/JP2000/001573 WO2001069609A1 (fr) | 2000-03-15 | 2000-03-15 | Procede de manipulation d'equipement |
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JP (1) | JP4221177B2 (fr) |
WO (1) | WO2001069609A1 (fr) |
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2003329796A (ja) * | 2002-05-16 | 2003-11-19 | Ishikawajima Harima Heavy Ind Co Ltd | 連結管製作方法及びフランジ位置計測システム |
JP2004361265A (ja) * | 2003-06-05 | 2004-12-24 | Ishikawajima Harima Heavy Ind Co Ltd | プラントの連結管製作方法 |
JP2012122516A (ja) * | 2010-12-07 | 2012-06-28 | Ihi Corp | 配管分離接続方法と配管接続部構造 |
JP2021528657A (ja) * | 2018-07-06 | 2021-10-21 | コリア ハイドロ アンド ニュークリアー パワー カンパニー リミテッド | 原子炉圧力容器の廃棄物処理装置および原子炉圧力容器の廃棄物処理方法 |
Citations (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPH07218696A (ja) * | 1994-02-08 | 1995-08-18 | Ishikawajima Harima Heavy Ind Co Ltd | 原子炉圧力容器の新替え方法 |
JPH0862368A (ja) * | 1994-08-26 | 1996-03-08 | Hitachi Ltd | 原子炉圧力容器と炉内構造物取替時の搬出方法及び原子炉建屋 |
JPH08285981A (ja) * | 1995-04-14 | 1996-11-01 | Ishikawajima Harima Heavy Ind Co Ltd | 原子炉圧力容器の取り替え方法 |
JPH1039076A (ja) * | 1996-07-24 | 1998-02-13 | Ishikawajima Harima Heavy Ind Co Ltd | 原子炉圧力容器搬出方法 |
JPH1039077A (ja) * | 1996-07-24 | 1998-02-13 | Ishikawajima Harima Heavy Ind Co Ltd | 原子炉圧力容器搬出及び搬入方法 |
-
2000
- 2000-03-15 JP JP2001567596A patent/JP4221177B2/ja not_active Expired - Fee Related
- 2000-03-15 WO PCT/JP2000/001573 patent/WO2001069609A1/fr active Search and Examination
Patent Citations (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPH07218696A (ja) * | 1994-02-08 | 1995-08-18 | Ishikawajima Harima Heavy Ind Co Ltd | 原子炉圧力容器の新替え方法 |
JPH0862368A (ja) * | 1994-08-26 | 1996-03-08 | Hitachi Ltd | 原子炉圧力容器と炉内構造物取替時の搬出方法及び原子炉建屋 |
JPH08285981A (ja) * | 1995-04-14 | 1996-11-01 | Ishikawajima Harima Heavy Ind Co Ltd | 原子炉圧力容器の取り替え方法 |
JPH1039076A (ja) * | 1996-07-24 | 1998-02-13 | Ishikawajima Harima Heavy Ind Co Ltd | 原子炉圧力容器搬出方法 |
JPH1039077A (ja) * | 1996-07-24 | 1998-02-13 | Ishikawajima Harima Heavy Ind Co Ltd | 原子炉圧力容器搬出及び搬入方法 |
Cited By (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2003329796A (ja) * | 2002-05-16 | 2003-11-19 | Ishikawajima Harima Heavy Ind Co Ltd | 連結管製作方法及びフランジ位置計測システム |
JP2004361265A (ja) * | 2003-06-05 | 2004-12-24 | Ishikawajima Harima Heavy Ind Co Ltd | プラントの連結管製作方法 |
JP2012122516A (ja) * | 2010-12-07 | 2012-06-28 | Ihi Corp | 配管分離接続方法と配管接続部構造 |
JP2021528657A (ja) * | 2018-07-06 | 2021-10-21 | コリア ハイドロ アンド ニュークリアー パワー カンパニー リミテッド | 原子炉圧力容器の廃棄物処理装置および原子炉圧力容器の廃棄物処理方法 |
US11682496B2 (en) | 2018-07-06 | 2023-06-20 | Korea Hydro & Nuclear Power Co., Ltd. | Apparatus for treating waste of nuclear reactor pressure vessel, and method for treating waste of nuclear reactor pressure vessel |
Also Published As
Publication number | Publication date |
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JP4221177B2 (ja) | 2009-02-12 |
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