WO2011070997A1 - Procédé de réparation d'une cuve de réacteur nucléaire - Google Patents

Procédé de réparation d'une cuve de réacteur nucléaire Download PDF

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Publication number
WO2011070997A1
WO2011070997A1 PCT/JP2010/071787 JP2010071787W WO2011070997A1 WO 2011070997 A1 WO2011070997 A1 WO 2011070997A1 JP 2010071787 W JP2010071787 W JP 2010071787W WO 2011070997 A1 WO2011070997 A1 WO 2011070997A1
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WO
WIPO (PCT)
Prior art keywords
reactor vessel
repair method
cooling water
nozzle
platform
Prior art date
Application number
PCT/JP2010/071787
Other languages
English (en)
Japanese (ja)
Inventor
剛 山本
和秀 山本
昌弥 山口
光司 宿谷
Original Assignee
三菱重工業株式会社
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by 三菱重工業株式会社 filed Critical 三菱重工業株式会社
Priority to EP10835917.5A priority Critical patent/EP2511910B1/fr
Priority to US13/319,773 priority patent/US9070485B2/en
Publication of WO2011070997A1 publication Critical patent/WO2011070997A1/fr

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Classifications

    • 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
    • G21C19/20—Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
    • G21C19/207—Assembling, maintenance or repair of reactor components
    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B23—MACHINE TOOLS; METAL-WORKING NOT OTHERWISE PROVIDED FOR
    • B23P—METAL-WORKING NOT OTHERWISE PROVIDED FOR; COMBINED OPERATIONS; UNIVERSAL MACHINE TOOLS
    • B23P6/00—Restoring or reconditioning objects
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/003—Remote inspection of vessels, e.g. pressure vessels
    • G21C17/01—Inspection of the inner surfaces of vessels
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/017—Inspection or maintenance of pipe-lines or tubes in nuclear installations
    • 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
    • G21C19/14—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 characterised by their adaptation for use with horizontal channels in the reactor core
    • 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
    • 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
    • Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
    • Y10T—TECHNICAL SUBJECTS COVERED BY FORMER US CLASSIFICATION
    • Y10T29/00—Metal working
    • Y10T29/49—Method of mechanical manufacture
    • Y10T29/49718—Repairing

Definitions

  • the present invention relates to a reactor vessel repair method.
  • the present invention relates to a method of repairing a reactor vessel such as a pressurized water reactor (PWR), for example, repairing an inner surface of a nozzle.
  • PWR pressurized water reactor
  • UT ultrasonic non-destructive testing
  • Patent Document 1 since the procedure is to install the gantry after the water level of the reactor vessel is lowered in advance, the cooling water in the reactor vessel is at least lower than the nozzle. It was necessary to drain in advance. That is, paragraph [0005] of Patent Document 1 states that “a reactor vessel for performing UT inspection on a welded portion between a nozzle provided on the side surface of the reactor vessel and an outlet and an inlet pipe connected to the nozzle.
  • a pedestal having an opening on the side according to the position of the nozzle is installed, Next, after inserting and installing a cylindrical shielding body in the nozzle from the opening, a UT inspection device is inserted in the nozzle and the welded portion is subjected to UT inspection. It is described.
  • the present invention has been made in view of the above-described circumstances, and can drain the cooling water in the reactor vessel without draining the cooling water in the cavity, and can perform repair work in the air environment.
  • the purpose is to provide a container repair method.
  • Reactor vessel repair method that solves the above-described problems is directed to a reactor vessel covered with cooling water.
  • the lower part of the gantry is suspended and installed in the reactor vessel, an air environment is created inside the bottomed tubular gantry, and the reactor vessel is repaired.
  • the reactor vessel repair method according to claim 2 of the present invention for solving the above-mentioned problem is the reactor vessel repair method according to claim 1, wherein the gantry is provided with a counterweight that counteracts buoyancy generated when the gantry is suspended in the cooling water. It is characterized by being.
  • a reactor vessel repair method according to claim 3 of the present invention for solving the above-mentioned problems is the reactor vessel repair method according to claim 1 or 2, wherein the gantry is connected to the platform installed inside the reactor vessel, and the platform. And a cylindrical vessel erected above the reactor vessel.
  • the platform includes a substantially cylindrical vessel-shaped side wall having an outer diameter smaller than the inner diameter of the reactor vessel, An access window communicating with a nozzle provided on a side surface of the reactor vessel is formed on the side wall, and the access window can be sealed by attaching a lid. It is characterized by.
  • a reactor vessel repair method that solves the above-mentioned problems is that, in claim 4, the platform extends from the upper end of the side wall to the outer peripheral side and is supported by the upper edge of the reactor vessel.
  • a flange is provided, and a double O-ring is interposed between the upper edge of the reactor vessel and the flange.
  • a reactor vessel repair method that solves the above-described problem is that, in claim 5, an underwater fastening portion is provided for tightly fastening the flange to the upper edge of the reactor vessel. It is a feature.
  • the reactor vessel repair method according to claim 7 of the present invention for solving the above-mentioned problems is characterized in that, in claim 4, a nozzle shielding means for closing a gap between the access window and the nozzle is provided. .
  • the reactor vessel repair method according to claim 8 of the present invention for solving the above-mentioned problems is characterized in that, in claim 4, a shielded seal plug for closing the nozzle is provided.
  • the nuclear reactor vessel repair method according to claim 9 of the present invention for solving the above-mentioned problem is that in claim 3, an earthquake-resistant support is attached to the uppermost portion of the cylindrical vessel, and the earthquake-proof support is surrounded by a connecting jig. It is combined with a structure.
  • a reactor vessel repair method that solves the above-mentioned problems is that in claim 3, the platform includes a pump for discharging cooling water in the reactor vessel to the outside of the reactor vessel, and For this purpose, piping is provided.
  • the bottomed cylindrical gantry is suspended in the cooling water while the inside is in an air environment, and the lower part of the gantry is installed in the reactor vessel.
  • the aerial environment can be achieved inside the vessel, and the reactor vessel is repaired using the gantry while the inside is in the aerial environment, leading to prevention of contamination and improving workability, for example, prevention of dust generation Reduction of decontamination work can be achieved.
  • the gantry is provided with a counterweight that counteracts the buoyancy generated when the gantry is suspended in the cooling water. We were able to solve the obstacle caused by buoyancy.
  • the gantry includes a platform installed inside the reactor vessel, and a cylindrical vessel connected to the platform and standing above the reactor vessel. Therefore, the gantry can be divided into a platform and a cylindrical container, and can be easily carried into the storage container (CV). Furthermore, when the platform is divided and the cylindrical container is divided, the carrying-in becomes easier.
  • the platform includes a substantially cylindrical vessel-shaped side wall having an outer diameter smaller than the inner diameter of the reactor vessel, and a bottom plate closing the lower end of the side wall.
  • the platform includes a flange that protrudes from the upper end of the side wall to the outer peripheral side and is supported by the upper edge of the reactor vessel. Since a sealing is interposed between the two, a watertight state is maintained and water leakage is prevented.
  • the reactor vessel repair method according to claim 6 of the present invention is provided with an underwater fastening portion for tightly fastening the flange to the upper edge of the reactor vessel, so that vibration is suppressed when an earthquake occurs. There is also a dampening effect. That is, there is an effect of preventing leakage from the cavity when the cylindrical container is lifted when an earthquake occurs.
  • a shielded seal plug for closing the nozzle is provided, so that foreign matters can be prevented from entering the nozzle.
  • an earthquake-resistant support is attached to the uppermost portion of the cylindrical vessel and the earthquake-resistant support is coupled to surrounding structures by a connecting jig, so that an earthquake has occurred. In this case, the vibration is suppressed or attenuated.
  • the platform is provided with a pump for discharging the cooling water in the reactor vessel to the outside of the reactor vessel, and piping for the pump.
  • the cooling water can be drained to make the cooling water level below the nozzle.
  • a reactor vessel repair method according to an embodiment of the present invention will be described with reference to FIGS.
  • the reactor vessel repair method of the present embodiment uses a bottomed cylindrical gantry 10 shown in FIG. 1, and this gantry 10 includes an earthquake-resistant support 11 shown in FIG. 2 and a cylindrical vessel 12 shown in FIG. 4 and an upper platform 13 shown in FIG. 4 and a lower platform 14 shown in FIG.
  • the upper platform 13 and the lower platform 14 are installed inside the reactor vessel 20 and connected to each other as shown in FIG.
  • a cylindrical container 12 is connected to the upper platform 13 in a plurality of stages.
  • the five-stage cylindrical vessel 12 has a slightly smaller diameter than the platforms 13 and 14 and is erected vertically above the reactor vessel 20.
  • the cylindrical container 12 is set in five stages.
  • the cylindrical container is not limited to this as long as it is composed of a plurality of cylindrical containers.
  • An earthquake-resistant support 11 is attached to the uppermost cylindrical container 12.
  • the seismic support 11 is provided with a plurality of hanging hooks 11a at equal intervals in the circumferential direction.
  • FIG. 6 shows a reactor vessel 20 in which the upper wall, which is an upper structure, and the core structure, which is an inner structure, are removed and the upper part is opened inside the nuclear reactor 1. The in-furnace structure is temporarily placed in the cavity.
  • FIG. 6 shows a state where the cavity is full, and the reactor vessel 20 is covered with the cooling water 2.
  • the gantry 10 can be integrated into the cooling water by the crane 8 through the rod 7, and the platforms 13 and 14 that are the lower part of the gantry 10 can be installed in the reactor vessel 20. . That is, an air environment can be achieved in the reactor vessel 20 in the cavity full state. Since the uppermost cylindrical container 12 is higher than the water level of the cooling water 2 and the cooling water 2 gets over the uppermost cylindrical container 12 and does not flow into the gantry 10, the air environment is maintained.
  • the lower platform 14 is provided with a counterweight 80 that counteracts buoyancy generated in the gantry 10 when the gantry 10 is suspended in an air environment, and suspends the gantry 10 in cooling water. There is no obstacle due to buoyancy.
  • At least one set of an inlet nozzle 21 and an outlet nozzle 22 is provided on the side surface of the reactor vessel 20, and the cooling water 2 can be taken into the inside from the inlet nozzle 21 and cooled from the outlet nozzle 22. Water 2 can be discharged.
  • the upper platform 13 includes a substantially cylindrical side wall 13a having an outer diameter smaller than the inner diameter of the reactor vessel 20, and an upper edge of the reactor vessel 20 (hereinafter referred to as a flange seat surface) projecting outward from the upper end of the side wall 13a. And flange 13b supported in close contact with 20a.
  • a double O-ring 3 is interposed between the flange sheet surface 20a of the reactor vessel 20 and the flange 13b.
  • the underwater fastening portions 40 for tightly fastening the flanges 13b are provided at the positions of a plurality of screw holes for the upper lid in the circumferential direction. The underwater fastening portion 40 will be described later.
  • the lower platform 14 includes a substantially cylindrical side wall 14a having an outer diameter smaller than the inner diameter of the reactor vessel 20, and a bottom plate 14b that closes the lower end of the side wall 14a.
  • a circular access window 14 c communicating with the nozzle 22 is formed. Although the circular access window 14c is omitted in FIGS. 1 and 5, as shown in FIG. 6, when the mount 10 is suspended in the cooling water, the substantially plate-like lid 23 is opened and closed. The device 24 is attached and sealed from the inside.
  • the thicknesses of the side walls 13a and 14a of the platforms 13 and 14 are both several times the thickness of the cylindrical container, the thickness of the bottom plate 14b of the lower platform 14 is several times the thickness of the cylindrical container, and the cylindrical container 12 Compared with a thickness of about 25 mm, the structure is thicker, and the radiation from the surrounding area is blocked, and repair work in the reactor vessel 20 is possible.
  • a sealing such as an O-ring is interposed between the lower platform 14 and the upper platform 13 to maintain a watertight state. The same applies between the upper platform 13 and the cylindrical container 12 and between the cylindrical containers 12.
  • flange portions 12 a projecting to the outer peripheral side are provided at the upper and lower ends of the cylindrical containers 12 connected in a plurality of stages, and these flange portions 12 a overlap each other and are bolts 4. Is passed through and fastened with a nut 5, and a double O-ring 6 is interposed inside thereof. Therefore, even if the gantry 10 formed by connecting the platforms 13 and 14 and the plurality of stages of cylindrical containers 12 is immersed in the cooling water, the cooling water 2 filled in the periphery leaks into the gantry 10 from the connection portion. There is nothing.
  • the seismic support 11 attached to the uppermost stage of the gantry 10 is coupled to the cavity wall (peripheral structure) 9 at a plurality of locations at equal intervals in the circumferential direction by a connecting jig 30 capable of adjusting tension.
  • the connecting jig 30 will be described later.
  • a pump 50 is installed on the flange 13 b of the upper platform 13, and a pipe 51 is disposed downward from the pump 13 between the platform 13 and the reactor vessel 20. Therefore, the cooling water 2 accumulated in the reactor vessel 20 can be pumped up by the pump 50 via the pipe 51 and discharged to the outside of the reactor vessel 20. As a result, the water level in the reactor vessel 20 can be lowered from the nozzles 21 and 22.
  • a water level sensor (not shown) for detecting the water level in the reactor vessel 20 is provided, and when the water level sensor detects a certain water level, the pump 50 is automatically operated to keep the water level in the reactor vessel 20 below a certain level. You may make it lower. It should be noted that by integrating the cylindrical vessel and the drainage / water level gauge equipment in the reactor vessel, when the cylindrical vessel / platform is installed in the reactor vessel, the reactor can be drained immediately. In addition, the cooling water to the inner diameter lower end of the nozzles 21 and 22 can be drained by an existing system.
  • the underwater fastening portion 40 that tightly fastens the flange 13b to the flange seat surface 20a of the nuclear reactor vessel 20 will be described with reference to FIGS.
  • the underwater fastening portion 40 includes a pin 41 that is fixed vertically upward from the flange seat surface 20 a of the reactor vessel 20, and a large-diameter head portion 41 a is formed at the upper end portion of the pin 41.
  • This pin 41 is attached using a screw hole (stud bolt hole plug) for fixing the upper lid to the reactor vessel 20 with a bolt after the upper lid is opened.
  • a wedge portion 43 formed on the upper surface of the flange 13b, a taper key 44 slidably disposed on the taper surface of the wedge portion 43, one end side is connected to the taper key 44, and the other end side is a flange.
  • the underwater fastening part 40 is comprised from the clamp cylinder 45 connected with 13b.
  • a hole 46 thicker than the head 41a of the pin 41 is formed in the flange 13b and the wedge 43 so as to communicate with each other. As shown in FIG. The head 41a of the pin 41 penetrates upward.
  • the taper key 44 is formed with a groove 44c that is narrower than the head 41a of the pin 41 and wider than the main body of the pin 41 itself.
  • the method of fixing the gantry 10 to the reactor vessel 20 uses the stud bolt hole plug of the reactor vessel 20, but it may be fastened with bolts and nuts.
  • the cylindrical container 12 adopts a clamp cylinder system, and can shorten the fixing work time and reduce the exposure.
  • the connecting jig 30 includes a body 31 having opposite threads cut at both ends, and rods 32 and 33 screwed at both ends of the body 31. 9, the other rod 33 is pin-coupled via a mounting bracket 35 of the seismic support 11. Accordingly, when the body 31 is rotated, the rods 32 and 33 screwed to both ends of the body 31 move in the approaching direction or the separating direction, so that the cavity wall 9 and the seismic support 11 are connected via the turnbuckle 30. The tension acting between the two can be adjusted.
  • a nozzle shielding means 70 is provided to close a gap between the access window 14 c of the lower platform 14 and the nozzles 21 and 22.
  • the nozzle shielding means 70 includes a cylindrical partial shield 71 provided so as to fill a gap between the nozzles 21 and 22 and the access window 14c, and the nozzles 21 and 22 formed inside the partial shield 71. It is composed of a cylindrical nozzle shield 72 having an equal inner diameter. Since the nozzle shielding means 70 is installed between the end faces of the reactor vessel nozzles 21 and 22 and the lower platform 14, it is possible to prevent foreign matter from falling into the reactor, and further, to the nozzles 21 and 22. / Easy device access.
  • the nozzle shield means 70 has a double shield by the partial shield 71 and the nozzle shield 72 in order to ensure a sufficient thickness for shielding against radiation.
  • a seal body 60 having a seal flag 62 that closes the inside is disposed on the nozzles 21 and 22.
  • the seal body 60 includes a substantially disc-shaped seal plug 62 set to an outer diameter smaller than the inner diameter of the nozzles 21 and 22, an inflatate seal 63 fitted on the outer peripheral surface of the seal flag 62, and the seal plug 62. And a plurality of fixing jacks 64 that can be advanced and retracted radially outward and a caster 65 for running the inner surfaces of the nozzles 21 and 22.
  • the fixing jack 64 advances the seal plug 62 toward the outer peripheral side in the radial direction to contact the inner surfaces of the nozzles 21 and 22 located on the outer peripheral side, and fixes the seal flag 62 to the inner surfaces of the nozzles 21 and 22. can do.
  • the inflatate seal 63 has a space between the outer peripheral surface of the seal plug 62 and expands to the outer peripheral side by supplying compressed air, thereby being disposed inside the nozzles 21 and 22. The gap between the sealing plug 62 and the inner surfaces of the nozzles 21 and 22 can be sealed.
  • the seal plug 62 is a shielded seal plug having a function of shielding radioactivity.
  • a guide portion 61 is detachably attached to the seal body portion 60.
  • the guide part 61 is a substantially rod-shaped member that can be inserted into the nozzles 21 and 22, and has a connection part 67 provided at the tip and a caster 68 for running the inner surfaces of the nozzles 21 and 22.
  • the seal body 60 is provided with a connected portion 69 corresponding to the connecting portion 67 of the guide portion 61, and the connecting portion 67 and the connected portion 69 are configured to be detachable from each other.
  • the flange 13 b of the upper platform 13 is tightly fastened to the flange seat surface 20 a of the reactor vessel 20 by the underwater fastening portion 40, and the seismic support 11 is fixed from the cavity wall 9. Since the tension is pulled in the circumferential direction, even when an earthquake occurs, the shaking is effectively suppressed, or the shaking is quickly attenuated, and the gantry 10 does not fall down. There is no water leakage.
  • the platforms 13 and 14 were connected, they could be divided
  • the cylindrical container 12 is also connected to a plurality of stages, the cylindrical container 12 can be divided into a plurality of parts and can be easily carried in.
  • the present invention is not limited to this, and it can be integrated.
  • the platforms 13 and 14 and the cylindrical container 12 are connected to each other and can be divided into each, the carrying-in can be facilitated. However, as long as there is no trouble in carrying into the storage container, it can be integrated. That is, the gantry 10 may be an integrated type.
  • the reactor vessel repair method of this embodiment is performed according to the following procedure. (1) First, the platforms 13 and 14 to be the gantry 10 and the cylindrical container 12 are connected via a sealing such as an O-ring, and the access window 14c of the lower platform 14 is sealed with a lid 23. (2) Next, the counterweight 80 is installed in the lower platform 14. In the reactor vessel 20, the upper wall, which is an upper structure, and the core structure, which is an internal structure, are removed, and the in-core structure is temporarily placed in a cavity. The cavity is full of water, and the reactor vessel 20 is covered with the cooling water 2.
  • the pump 5 is operated to discharge the cooling water 2 in the reactor vessel 20 to the outside of the reactor vessel 20, and the water level in the reactor vessel 20 is set to the nozzles 21 and 22 or less.
  • the lid 23 is removed from the access window 14c of the lower platform 14, and a gap between the access window 14c and the nozzles 21 and 22 is removed.
  • the nozzle block shielding means 70 for closing is attached, and the shield plug 62 with shielding is attached in the nozzles 21 and 22.
  • the present invention is widely industrially applicable as a reactor vessel repair method, and is particularly suitable as a method for repairing the inner surface of a reactor vessel nozzle of a pressurized water reactor, and furthermore, a reactor vessel watertight lid device Can also be diverted.

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  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Mechanical Engineering (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

Selon cette invention, dans une cuve (20) de réacteur nucléaire recouverte d'eau de refroidissement (2), un châssis (10) à fond bombé, dont la partie interne est non immergée (à l'air), est plongé dans l'eau de refroidissement, et la partie inférieure du châssis (10) est installée dans la cuve (20) de réacteur nucléaire. Ainsi on peu obtenir un environnement non immergé à l'intérieur de la cuve (20) de réacteur nucléaire. En outre, comme la cuve (20) de réacteur nucléaire peut être réparée au moyen du châssis (10) dont la partie interne est non immergée, la pollution peut être empêchée, la maniabilité améliorée, et par exemple, la production de poussière empêchée et le travail de décontamination réduit. En outre, l'eau de refroidissement (2) située à l'intérieur de la cuve (20) de réacteur nucléaire n'est pas évacuée, et même dans les conditions dans lesquelles la cuve (20) de réacteur nucléaire est recouverte d'eau de refroidissement (2), le travail de réparation peut être effectué dans un milieu non immergé.
PCT/JP2010/071787 2009-12-08 2010-12-06 Procédé de réparation d'une cuve de réacteur nucléaire WO2011070997A1 (fr)

Priority Applications (2)

Application Number Priority Date Filing Date Title
EP10835917.5A EP2511910B1 (fr) 2009-12-08 2010-12-06 Procédé de réparation d'une cuve de réacteur nucléaire
US13/319,773 US9070485B2 (en) 2009-12-08 2010-12-06 Reactor vessel repair method

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
JP2009278516A JP5761909B2 (ja) 2009-12-08 2009-12-08 原子炉容器補修工法
JP2009-278516 2009-12-08

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WO2011070997A1 true WO2011070997A1 (fr) 2011-06-16

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EP (1) EP2511910B1 (fr)
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WO (1) WO2011070997A1 (fr)

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US9324462B2 (en) * 2010-07-13 2016-04-26 Westinghouse Electric Company Llc Reactor head seismic support tie rod system
JP2013040823A (ja) * 2011-08-12 2013-02-28 Mitsubishi Heavy Ind Ltd 原子炉容器の管台処理装置
KR101438108B1 (ko) * 2011-12-16 2014-09-12 두산중공업 주식회사 내진 강화 조립체
JP5852143B2 (ja) * 2012-01-30 2016-02-03 三菱重工業株式会社 原子炉容器蓋のｗｊｐ施工方法および治具
JP5881450B2 (ja) * 2012-02-09 2016-03-09 三菱重工業株式会社 輸送容器及びその解体方法
CN103886924B (zh) * 2014-01-07 2017-03-29 中广核研究院有限公司 屏蔽顶盖

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JP2006349596A (ja) * 2005-06-20 2006-12-28 Mitsubishi Heavy Ind Ltd 原子力容器の管台内面の切削方法および切削装置
JP2007003442A (ja) * 2005-06-27 2007-01-11 Mitsubishi Heavy Ind Ltd 原子炉容器の管台溶接部のｕｔ検査方法および装置

Also Published As

Publication number Publication date
US20120117774A1 (en) 2012-05-17
US9070485B2 (en) 2015-06-30
JP2011122845A (ja) 2011-06-23
EP2511910A1 (fr) 2012-10-17
EP2511910A4 (fr) 2015-03-18
EP2511910B1 (fr) 2016-04-27
JP5761909B2 (ja) 2015-08-12

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