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EP0780019A1 - Procede et dispositif de controle non destructif de l'enveloppe du c ur de reacteurs nucleaires a eau bouillante - Google Patents

Procede et dispositif de controle non destructif de l'enveloppe du c ur de reacteurs nucleaires a eau bouillante

Info

Publication number
EP0780019A1
EP0780019A1 EP95928979A EP95928979A EP0780019A1 EP 0780019 A1 EP0780019 A1 EP 0780019A1 EP 95928979 A EP95928979 A EP 95928979A EP 95928979 A EP95928979 A EP 95928979A EP 0780019 A1 EP0780019 A1 EP 0780019A1
Authority
EP
European Patent Office
Prior art keywords
telescopic boom
core jacket
guide rod
pressure vessel
swivel arm
Prior art date
Legal status (The legal status 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 status listed.)
Withdrawn
Application number
EP95928979A
Other languages
German (de)
English (en)
Inventor
Roland Gottfried
Franz Dirauf
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Siemens AG
Siemens Corp
Original Assignee
Siemens AG
Siemens Corp
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 AG, Siemens Corp filed Critical Siemens AG
Publication of EP0780019A1 publication Critical patent/EP0780019A1/fr
Withdrawn legal-status Critical Current

Links

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
    • 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 and a method for the non-destructive testing of the core jacket of boiling water nuclear reactor plants with jet pumps in an annular space between the core jacket and a reactor pressure vessel surrounding the outside.
  • the core jacket in boiling water nuclear reactor plants encloses the fuel elements and serves mainly to guide the circulated water flow, which is directed upwards inside the core jacket and downwards outside the core jacket.
  • the core jacket is usually composed of several cylindrical parts, which consist of austenitic sheets and are welded together. Annular flanges are welded between these cylinders, which serve as a support for an upper and a lower core lattice and thus also for fixing the fuel elements.
  • cracks can form in the core jacket near weld seams.
  • non-destructive material tests are to be carried out with the aid of ultrasound test heads or eddy current probes.
  • a manipulator for checking the inner circumference of a reactor pressure vessel of a boiling water reactor which comprises an upper mast guided between two ring rails. On this mast, a test system can be moved in the longitudinal direction, with which the area above the core jacket can be checked.
  • a lower mast composed of several members is fixed to this upper mast and protrudes into the space between jet pumps and reactor pressure vessel. This lower mast carries a test system with which the reactor pressure vessel can be tested in the area of the core jacket. It is not possible to test the core shell itself with the known manipulator.
  • the invention is therefore based on the object of providing a device which enables remote-controlled, largely automated testing of the core casing without requiring the complete removal of the core.
  • the invention is based on the object of specifying a method for testing the core jacket.
  • the first-mentioned object is achieved for boiling water nuclear reactor plants of the type mentioned at the outset in that a test head can be moved horizontally on a telescopic arm which is adapted to the curvature of the core jacket and which is carried by a vertical guide rod between the jet pumps on one The weld seam of the core jacket can be positioned.
  • the vertical guide rod can preferably be supported at its end facing the telescopic boom via a swivel arm on the reactor pressure vessel.
  • a holding element that can be fixed to the reactor pressure vessel is provided at the free end of the swivel arm, which in a further advantageous embodiment is vertically displaceable to the guide Rod is stored. This displaceable mounting of the holding element enables the test area to be displaced vertically during a test process, even when the holding element is fixed to the reactor pressure vessel.
  • the telescopic boom can be placed against the core jacket either via an upper or a lower parallel guide. This enables the lowest weld seam of the core jacket, which is particularly difficult to access, to be checked.
  • the telescopic boom is arranged on the guide rod so as to be pivotable about a horizontal axis.
  • the telescopic boom can also be moved to the outer wall of the core jacket in the case of closely adjacent jet pumps.
  • the second object is achieved with the features of claim 12.
  • According to the invention is carried by a vertical guide rod to the curvature of the
  • test head is guided along a meandering path along the core jacket during a test process and that the telescopic boom, which extends essentially horizontally during a test process, is moved from one test position to another in a test process a vertical position is pivotable.
  • the device according to the invention can be used very advantageously because it enables a large-area inspection of the core jacket, even in areas under built-in groups in the annular space between the core jacket and a reactor pressure vessel.
  • FIG. 1 shows a half of a section through an open reactor pressure vessel with a device according to the invention, which has been introduced for the non-destructive testing of a core jacket and which is illustrated in different test positions A, B and C of the telescopic boom.
  • 3 to 5 show the device in working positions A, B and C, each on an enlarged scale.
  • annular space 6 in which jet pumps 8 are arranged, is located between a core jacket 2 and a reactor pressure vessel 4 of a boiling water nuclear reactor plant. With the reactor pressure vessel 4 open, the annular space 6 is only accessible from above in the angular ranges between the individual jet pumps 8.
  • the telescopic boom 10 is fastened to the free end of a vertical guide rod 14, with which it is in the working position A above the jet pumps 8 and in working positions B and C between the jet pumps 8 at the level of the different welds 261 to 263 of the core jacket 2 can be positioned.
  • the guide rod 14 is carried by the upper part of a so-called "Beltline ID manipulator" 16, as is known, for example, from US Pat. No. 5,303,591 mentioned above for checking the inner circumference of the reactor pressure vessel 4 above the core jacket 2 .
  • the Belt Line ID manipulator 16 comprises an annular rail 18 which is placed on the cover flange 20 of the reactor pressure vessel 4. On this ring rail 20, a carriage is mounted, which carries a vertical mast 24 which projects into the reactor pressure vessel. The mast 24 can be moved with the carriage in the circumferential direction and can reach any position on the circumference of the core jacket 2.
  • the device according to the invention is attached to a bridge of a fuel assembly loading machine with an extended vertical guide rod. With the help of the bridge, the device can be positioned over the desired test area. A linear drive is then attached to the bridge for the vertical movement of the guide rod.
  • the telescopic boom 10 comprises a base 103 in which a first arm 106 is guided, which in turn forms the guide for a second arm 108.
  • Test heads 12 and a video camera 13 are arranged on the second arm 108 of the telescopic boom 10 and can be moved horizontally in the circumferential direction of the core jacket 2 with the telescopic boom 10.
  • the shape of the telescopic boom 10 is adapted for this purpose to the curvature of the core shell 2. Ultrasonic probes and / or current probes are preferably used as test heads 12.
  • the telescopic boom 10 is arranged via a lower swivel arm 32 with a parallel guide at the lower end 36 of the guide rod 14 and can be folded out against the core jacket 2 with this swivel arm 34.
  • the base 103 of the telescopic boom 10 can be pivoted in a preferred embodiment on a bracket 102 articulated on the lower pivot arm 32 arranged.
  • the telescopic boom 10 can then be pivoted about an axis 104 perpendicular to the guide rod 14 with a vertical guide rod 14 into a vertical position.
  • the arms 106, 108 of the telescopic boom 10 can be extended on both sides of the base 103, as is indicated by dash-dotted lines in the figure.
  • the base 103 is preferably mounted centrally on the holder 102, so that the detectable test area is the same size on both sides of the guide rod 34.
  • an upper pivot arm 28 is arranged according to FIG. 3 at the end of the guide rod 14 facing the telescopic boom 10, at the free end of which a holding element 30, in the embodiment - Play a suction cup is arranged.
  • a suction cup is arranged.
  • the free end of the upper swivel arm 28 is slidably mounted in a guide 31 so that the telescopic boom 10 can be moved vertically up and down within the respective test area with the help of the guide rod 14 during the test process.
  • the test procedure is carried out by meandering movement of the test heads 12 on the surface of the core shell 2.
  • the telescopic boom 10 moves the test heads 12 in a horizontal direction, whereby areas behind the jet pumps 8 are also checked.
  • the movement in the vertical direction takes place when the holding element 20 is fixed by displacing the guide rod 14.
  • a middle swivel arm 34 with parallel guide is articulated on the lower free end of the guide rod 14 and carries an arm 36, on the lower end of which the lower swivel arm 32 is articulated.
  • the telescopic boom 10 With the lower and upper swivel arms 32 and 34, the telescopic boom 10 can be folded in the radial direction onto the outer surface of the core shell 2.
  • the pivot arms 32 and 34 are preferably driven pneumatically.
  • the lower swing arm 32 supports the telescopic boom 10. It is used to position the telescopic boom 10 to check the upper weld seams 261, 262 of the core jacket 2 bring. Its arrangement also allows a weld seam 261 to be checked immediately below an annular flange 38 of the core jacket 2.
  • FIG. 4 shows the telescopic boom 10 in working position B at the level of the jet pumps 8 for testing a weld seam 262 above an annular flange 38. In this working position, too, the upper swivel arm 34 need not be folded out.
  • the middle swivel arm 34 is located approximately 400 to 1000 mm above the lower swivel arm 32. According to FIG. 5, it is used to check the lowest circular seam 263 on the core jacket 2 in the working position C.
  • the direct access to this weld seam 263 is provided by permanently installed instrumentation lines - hindered 40, which run in a ring around the core jacket 2 in the lower region of the jet pumps 8 and are led out of the reactor pressure vessel via a common connecting piece.
  • the lower swivel arm 32 is held in a vertical position.
  • the telescopic boom 10 is already folded onto the core jacket 2 above the instrumentation lines 40 and then moved behind these instrumentation lines 40 with the aid of the guide rod 14 down to the height of the weld seam 263 to be tested.
  • the guide rod 14 is then fixed to the wall of the reactor pressure vessel 4 with the holding element 30.

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)

Abstract

Dans les réacteurs nucléaires à eau bouillante, des pompes à jet (8) sont souvent montées dans un espace annulaire (6) situé entre l'enveloppe du coeur (2) et une cuve sous pression (4) qui entoure l'enveloppe du coeur (2). Lors de l'inspection de l'enveloppe du coeur (2) pour détecter d'éventuelles fissures, des têtes de contrôle doivent être introduites dans cet espace annulaire (2). Selon l'invention, ces têtes de contrôle peuvent être déplacées horizontalement sur une flèche télescopique (10) adaptée à la courbure de l'enveloppe du coeur. La flèche télescopique (10) est portée par une barre conductrice (14) verticale qui permet de la positionner entre les pompes à jet (8) sur un cordon de soudure (261-263) de l'enveloppe du coeur (2).
EP95928979A 1994-09-06 1995-08-24 Procede et dispositif de controle non destructif de l'enveloppe du c ur de reacteurs nucleaires a eau bouillante Withdrawn EP0780019A1 (fr)

Applications Claiming Priority (3)

Application Number Priority Date Filing Date Title
DE4431625 1994-09-06
DE4431625A DE4431625C1 (de) 1994-09-07 1994-09-07 Vorrichtung zur zerstörungsfreien Prüfung des Kernmantels von Siedewasser-Kernreaktoranlagen
PCT/DE1995/001131 WO1996008018A1 (fr) 1994-09-06 1995-08-24 Procede et dispositif de controle non destructif de l'enveloppe du c×ur de reacteurs nucleaires a eau bouillante

Publications (1)

Publication Number Publication Date
EP0780019A1 true EP0780019A1 (fr) 1997-06-25

Family

ID=6527480

Family Applications (1)

Application Number Title Priority Date Filing Date
EP95928979A Withdrawn EP0780019A1 (fr) 1994-09-06 1995-08-24 Procede et dispositif de controle non destructif de l'enveloppe du c ur de reacteurs nucleaires a eau bouillante

Country Status (3)

Country Link
EP (1) EP0780019A1 (fr)
DE (1) DE4431625C1 (fr)
WO (1) WO1996008018A1 (fr)

Families Citing this family (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE19716281C1 (de) * 1996-12-23 1998-08-13 Bbc Reaktor Gmbh Einrichtung zum zerstörungsfreien Prüfen eines zylindrischen Behälters und/oder mit ihm verbundener Bauteile
US7640810B2 (en) * 2005-07-11 2010-01-05 The Boeing Company Ultrasonic inspection apparatus, system, and method
US7464596B2 (en) 2004-09-24 2008-12-16 The Boeing Company Integrated ultrasonic inspection probes, systems, and methods for inspection of composite assemblies
CN104979026B (zh) * 2015-07-15 2017-12-22 国核电站运行服务技术有限公司 水下维修工艺研究试验平台

Family Cites Families (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE7718641U1 (de) * 1977-06-13 1980-02-14 Kraftwerk Union Ag, 4330 Muelheim Prüfmanipulator zur Außenprüfung von Rohrleitungen, vorzugsweise zum Ultraschall-Priifen bei Reaktordruckbehältern
DE2936660C2 (de) * 1979-09-11 1984-05-10 M.A.N. Maschinenfabrik Augsburg-Nürnberg AG, 8500 Nürnberg Manipulator zur Prüfung von Rohrumfangs- und Rohrlängsschweißnähten
DE3524390A1 (de) * 1985-07-08 1987-01-08 Kraftwerk Union Ag Pruefmanipulator
US4728482A (en) * 1986-04-10 1988-03-01 Westinghouse Electric Corp. Method for internal inspection of a pressurized water nuclear reactor pressure vessel
JPH0612360B2 (ja) * 1987-11-19 1994-02-16 株式会社東芝 原子炉内超音波探傷装置
JP2619020B2 (ja) * 1988-10-27 1997-06-11 株式会社東芝 原子炉圧力容器検査装置
US4966746A (en) * 1989-01-03 1990-10-30 General Electric Company Ultrasonic examination of BWR shroud access cover plate retaining welds
DE9003515U1 (de) * 1990-03-26 1991-04-25 Siemens AG, 8000 München Manipulator für Hantierungsarbeiten, insbesondere für zerstörungsfreie Prüfungen
DE4014161A1 (de) * 1990-05-03 1991-11-07 Man Energie Gmbh Pruefgeraete-manipulator fuer druckbehaelter von kernreaktoren
US5303591A (en) * 1991-05-02 1994-04-19 General Electric Company Ultrasonic inspection system with improved pulser and receiver circuits

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
See references of WO9608018A1 *

Also Published As

Publication number Publication date
WO1996008018A1 (fr) 1996-03-14
DE4431625C1 (de) 1996-03-07

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