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WO1995033267A1 - Dispositif et procede destines a traiter ou a tester un composant immerge - Google Patents

Dispositif et procede destines a traiter ou a tester un composant immerge Download PDF

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Publication number
WO1995033267A1
WO1995033267A1 PCT/DE1995/000681 DE9500681W WO9533267A1 WO 1995033267 A1 WO1995033267 A1 WO 1995033267A1 DE 9500681 W DE9500681 W DE 9500681W WO 9533267 A1 WO9533267 A1 WO 9533267A1
Authority
WO
WIPO (PCT)
Prior art keywords
processing
testing
processing chamber
component
opening
Prior art date
Application number
PCT/DE1995/000681
Other languages
German (de)
English (en)
Inventor
Bruno Dippel
Herbert Schramm
Richard Ruf
Original Assignee
Siemens Aktiengesellschaft
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 Siemens Aktiengesellschaft filed Critical Siemens Aktiengesellschaft
Publication of WO1995033267A1 publication Critical patent/WO1995033267A1/fr

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Classifications

    • 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
    • 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 invention relates to a device for processing or testing a component located under water, in particular an annular weld seam of a core jacket of a nuclear reactor.
  • the part of the plant to be checked or processed is generally under water in order to avoid high exposure to the service personnel.
  • not all testing and machining processes can be carried out under water without problems. This applies in particular to welding work and thermal post-treatment. In these cases, in spite of the associated high radiation exposure of the service personnel, the water level must be lowered to the processing point in order to enable the surface to be processed or checked properly.
  • a repair aid for the replacement of the first shut-off valves for the feed water of a boiling water reactor in which a sealing box is applied in a liquid-tight manner to the inner wall of the reactor pressure container via the feed water distributors located under water inside the reactor pressure vessel.
  • the first shut-off valves arranged outside the reactor pressure vessel can then be exchanged without the reactor pressure vessel having to be emptied.
  • CH 683574 A5 discloses a method for underwater welding a control rod drive housing in the core of a boiling water reactor, in which a cylinder is pushed over the control rod drive housing. There is a welding machine in this cylinder. The interior of the cylinder is flooded with gas, the pressure of which corresponds to the hydrostatic pressure of the water in the reactor pressure vessel at the lower edge of the cylinder.
  • the invention is based on the object of specifying a device for machining or testing a component, in particular for machining an annular weld seam of a core jacket of a nuclear reactor, which enables dry machining of the component even under water.
  • the invention is based on the object of specifying a method for machining or testing a component which enables dry machining of the component even under water.
  • a device for processing or testing an underwater component in particular an annular weld seam of a core jacket of a nuclear reactor, contains a) a processing chamber for receiving a processing or testing device, which has a processing opening and a seal surrounding this processing opening and can be placed liquid-tight on a surface which surrounds a part of the component to be processed or tested.
  • a processing chamber that can be placed on this surface, which contains circular guide rails and a carriage that can be moved thereon and which receives the processing or testing device.
  • the carriage contains a lifting device.
  • the supply shaft preferably has a guide rail for transporting the processing or testing device.
  • means are provided for fastening the device to the component.
  • supports are in particular provided which contain an extendable opening element which is supported on the inner surface of the component opposite the processing chamber and presses the processing chamber against the inner surface facing it.
  • the following method steps are provided in a method for processing or testing a component located under water, in particular an annular weld seam of a core jacket of a nuclear reactor:
  • the processing or testing device is introduced into the processing chamber through a supply shaft opening into the processing chamber and provided with a loading opening and
  • FIG. 1 a device according to the invention is schematically illustrated in a longitudinal or cross section.
  • FIG. 3 shows a further advantageous embodiment of the invention, likewise in a section.
  • the open reactor pressure vessel 2 of a nuclear reactor for example a boiling water reactor, is filled with water up to a water level 4 near its upper edge.
  • a core jacket 6 from which an upper core grid serving to hold the fuel elements is removed.
  • This hollow cylindrical core jacket 6 is composed of several segments, which with ring weld seams 8 and in the figure invisible longitudinal welds are welded together.
  • a device 12 for processing or testing the inner surface of the core shell 6 is lowered into the interior of the core shell 6, starting from a control and operating level 10 located above the reactor pressure vessel 2.
  • the device 12 comprises a processing chamber 14 which receives a processing or testing device 18.
  • the processing chamber 14 has a U-shaped cross section with two legs 141 and 142 and has a processing opening 20 located between the free ends of these legs 141 and 142. This is surrounded by an undulating seal 24, preferably an inflatable double seal, with which the processing chamber 14 with its processing opening 20 is placed on the inner surface of the core jacket 6 in a liquid-tight manner. The resulting sealing surface surrounds the point to be machined and seals it off in a liquid-tight manner with respect to the water located outside the machining chamber 14.
  • a support 30 is arranged on the processing chamber 14, which contains a radially extendable raising element 32, which can be raised against the inner surface of the core shell 6 opposite the processing opening 20, so that the processing chamber 14 with its seal 24 on it facing inner surface of the core jacket 6 is pressed.
  • the pressure developed by the deployment element 32 is sufficient to allow the water in the processing chamber 14 to be pumped out.
  • the processing chamber 14 is connected to a pump 22. By pumping off this water and the high water pressure of the water in the reactor pressure vessel 2, the force with which the seal 24 is pressed against the core jacket 6 is additionally increased and a liquid-tight seal is supported.
  • the surface surrounding the processing point against which the processing chamber 14 is pressed is at the same time the surface of the component to be tested, in the example the core jacket 6 itself.
  • the component to be tested partly protrudes beyond the surface provided for sealing, as is the case, for example, with the feed water distributor nozzle in the reactor pressure vessel of a boiling water reactor (see, for example, EP 0 179 168 AI).
  • a tubular supply shaft 40 opens into the processing chamber 14 and is provided at its upper end with a loading opening 42 located above the water level 4.
  • the supply shaft 40 is hooked into the upper edge of the core jacket 6 with a fastening hook 43 and additionally screwed there to a flange of the core jacket 6.
  • the processing or testing device 18 is lowered from the control and operating level 10 through the supply shaft 40 into the processing chamber 14 and rests there on a carriage 50.
  • a guide rail 44 is provided within the supply shaft 40, along which the processing or testing device 18 can be moved up and down in the supply shaft 40.
  • the reference numbers 46 denote the lines required for the control and power supply of the processing or testing device 18.
  • the processing or testing devices 18 are interchangeable modules, so that when the device 12 is fixed, different testing or working processes, for example eddy current and ultrasonic testing or welding and thermal treatment, can be carried out in succession.
  • the carriage 50 travels on arcuate rails 52 which are arranged in the processing chamber 14 in the circumferential direction of the core shell 6.
  • the carriage 50 comprises a lifting table 54 on which the processing or testing device 18 is placed.
  • the processing device 18 carries a processing or test head 182, for example a TIG welding torch, by means of which the annular weld seam 8 is re-welded.
  • the radial feed movement of the processing or testing head 182 is carried out by the processing or testing device 18 with the carriage 50 and the lifting table 54 at rest.
  • the adjustment to the height of the weld seam 8 takes place with the lifting table 54 and the feed movement along the weld seam is carried out by the carriage 50 which can be moved on the rails 52.
  • a carriage 50 which can be moved on rails 52 and which has a lifting table 54
  • a protective chamber 15 drawn in dashed lines can be arranged opposite the processing chamber 14 on the outer surface of the core jacket 6, which surrounds the core jacket 6 completely or on part of its circumference and is located on the inner wall of the reactor pressure vessel 2 supported and in analogy to the inner processing chamber 14 can also be coupled tightly to the surface of the core shell and pumped out.
  • the additional attachment of a protective chamber 15 is expedient when welding through the weld seam 8 is required for the post-weldings.
  • the processing chamber 14 is composed of a plurality of ring segments 143 which are attached to the curvature of the core jacket 6. are fit.
  • the ring segments 143 are also provided with stiffening ribs 144 to increase their stability.
  • annular processing chamber 16 is provided which bears against the inner wall of the core shell 6 via a seal 25 and rests on the upper edge surface of the core shell 6 via a further seal 26 and is fixed there by means of a flange connection 146.

Landscapes

  • 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)
  • Investigating Or Analyzing Materials By The Use Of Ultrasonic Waves (AREA)

Abstract

L'invention concerne un dispositif destiné à traiter ou à tester un composant immergé, notamment un cordon de soudure (8) annulaire d'une enveloppe (6) du c÷ur d'un réacteur nucléaire. Ce dispositif comprend une chambre de traitement (14, 16) destinée à abriter un appareil de traitement ou d'essai (18) présentant une ouverture de traitement (20) entourée par un joint (24) et pouvant être appliquée de façon étanche sur une surface entourant une zone de l'élément à traiter. Une conduite d'amenée (40) pourvue d'une ouverture de chargement (42) et conçue pour introduire l'appareil de traitement ou d'essai (18) dans la chambre de traitement (14) débouche dans cette dernière. La chambre de traitement (14) est en outre raccordée à un dispositif de pompage (22) conçu pour évacuer l'eau se trouvant dans la chambre de traitement (14) et dans la conduite d'amenée (40).
PCT/DE1995/000681 1994-05-26 1995-05-24 Dispositif et procede destines a traiter ou a tester un composant immerge WO1995033267A1 (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DEG9408412.2U 1994-05-26
DE9408412U DE9408412U1 (de) 1994-05-26 1994-05-26 Vorrichtung zum Bearbeiten oder Prüfen einer Oberfläche eines unter Wasser befindlichen Bauteiles

Publications (1)

Publication Number Publication Date
WO1995033267A1 true WO1995033267A1 (fr) 1995-12-07

Family

ID=6908961

Family Applications (1)

Application Number Title Priority Date Filing Date
PCT/DE1995/000681 WO1995033267A1 (fr) 1994-05-26 1995-05-24 Dispositif et procede destines a traiter ou a tester un composant immerge

Country Status (2)

Country Link
DE (1) DE9408412U1 (fr)
WO (1) WO1995033267A1 (fr)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US7754993B2 (en) * 2006-07-10 2010-07-13 General Electric Company Method for providing a dry environment for underwater repair of the reactor bottom head using a segmented caisson

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2123409A1 (fr) * 1971-01-25 1972-09-08 V Trudov
EP0063225A2 (fr) * 1981-04-08 1982-10-27 Westinghouse Electric Corporation Appareil pour la contrôle des plaques à chicanes
EP0179168A1 (fr) * 1984-10-09 1986-04-30 Siemens Aktiengesellschaft Dispositif auxiliaire de réparation
JPH06138281A (ja) * 1992-10-22 1994-05-20 Toshiba Corp 遠隔炉内点検補修装置

Family Cites Families (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE3405851A1 (de) * 1984-02-16 1985-08-29 Kraftwerk Union AG, 4330 Mülheim Manipulator fuer oben offene druckbehaelter
DE3823888C1 (en) * 1988-07-14 1989-12-07 Hochtemperatur-Reaktorbau Gmbh, 4600 Dortmund, De Equipment for working on components in inaccessible places in a nuclear reactor pressure container
US4954311A (en) * 1989-01-10 1990-09-04 General Electric Company Control rod housing alignment
DE3931075A1 (de) * 1989-09-18 1991-03-28 Voest Alpine Mach Const Vorrichtung zur unterwasserbearbeitung eines strahlenden werkstueckes

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2123409A1 (fr) * 1971-01-25 1972-09-08 V Trudov
EP0063225A2 (fr) * 1981-04-08 1982-10-27 Westinghouse Electric Corporation Appareil pour la contrôle des plaques à chicanes
EP0179168A1 (fr) * 1984-10-09 1986-04-30 Siemens Aktiengesellschaft Dispositif auxiliaire de réparation
JPH06138281A (ja) * 1992-10-22 1994-05-20 Toshiba Corp 遠隔炉内点検補修装置

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
PATENT ABSTRACTS OF JAPAN vol. 018, no. 439 (P - 1787) 16 August 1994 (1994-08-16) *

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US7754993B2 (en) * 2006-07-10 2010-07-13 General Electric Company Method for providing a dry environment for underwater repair of the reactor bottom head using a segmented caisson

Also Published As

Publication number Publication date
DE9408412U1 (de) 1995-09-21

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