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WO1999041753A1 - Procede et dispositif pour separer par fractionnement un composant radioactif d'un reacteur nucleaire - Google Patents

Procede et dispositif pour separer par fractionnement un composant radioactif d'un reacteur nucleaire Download PDF

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Publication number
WO1999041753A1
WO1999041753A1 PCT/EP1999/000972 EP9900972W WO9941753A1 WO 1999041753 A1 WO1999041753 A1 WO 1999041753A1 EP 9900972 W EP9900972 W EP 9900972W WO 9941753 A1 WO9941753 A1 WO 9941753A1
Authority
WO
WIPO (PCT)
Prior art keywords
suspension
component
water
reactor
abrasive material
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.)
Ceased
Application number
PCT/EP1999/000972
Other languages
German (de)
English (en)
Other versions
WO1999041753B1 (fr
Inventor
Hans Heinrich Brehmer
Mike John Yeomans
Werner Reiter
Horst Kalwa
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.)
ALBA INDUSTRIES GmbH
Versuchsatomkraftwerk Kahl GmbH
Original Assignee
ALBA INDUSTRIES GmbH
Versuchsatomkraftwerk Kahl GmbH
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 ALBA INDUSTRIES GmbH, Versuchsatomkraftwerk Kahl GmbH filed Critical ALBA INDUSTRIES GmbH
Priority to DE29920718U priority Critical patent/DE29920718U1/de
Priority to AU28339/99A priority patent/AU2833999A/en
Publication of WO1999041753A1 publication Critical patent/WO1999041753A1/fr
Publication of WO1999041753B1 publication Critical patent/WO1999041753B1/fr
Anticipated expiration legal-status Critical
Ceased legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/001—Decontamination of contaminated objects, apparatus, clothes, food; Preventing contamination thereof
    • G21F9/005—Decontamination of the surface of objects by ablation
    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B24—GRINDING; POLISHING
    • B24C—ABRASIVE OR RELATED BLASTING WITH PARTICULATE MATERIAL
    • B24C1/00—Methods for use of abrasive blasting for producing particular effects; Use of auxiliary equipment in connection with such methods
    • B24C1/04—Methods for use of abrasive blasting for producing particular effects; Use of auxiliary equipment in connection with such methods for treating only selected parts of a surface, e.g. for carving stone or glass
    • B24C1/045—Methods for use of abrasive blasting for producing particular effects; Use of auxiliary equipment in connection with such methods for treating only selected parts of a surface, e.g. for carving stone or glass for cutting
    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B24—GRINDING; POLISHING
    • B24C—ABRASIVE OR RELATED BLASTING WITH PARTICULATE MATERIAL
    • B24C3/00—Abrasive blasting machines or devices; Plants
    • B24C3/02—Abrasive blasting machines or devices; Plants characterised by the arrangement of the component assemblies with respect to each other
    • B24C3/06—Abrasive blasting machines or devices; Plants characterised by the arrangement of the component assemblies with respect to each other movable; portable
    • B24C3/065—Abrasive blasting machines or devices; Plants characterised by the arrangement of the component assemblies with respect to each other movable; portable with suction means for the abrasive and the waste material
    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B24—GRINDING; POLISHING
    • B24C—ABRASIVE OR RELATED BLASTING WITH PARTICULATE MATERIAL
    • B24C9/00—Appurtenances of abrasive blasting machines or devices, e.g. working chambers, arrangements for handling used abrasive material
    • B24C9/006—Treatment of used abrasive material
    • 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
    • Y02P—CLIMATE CHANGE MITIGATION TECHNOLOGIES IN THE PRODUCTION OR PROCESSING OF GOODS
    • Y02P70/00—Climate change mitigation technologies in the production process for final industrial or consumer products
    • Y02P70/10—Greenhouse gas [GHG] capture, material saving, heat recovery or other energy efficient measures, e.g. motor control, characterised by manufacturing processes, e.g. for rolling metal or metal working

Definitions

  • the invention relates to a method for separating a radioactive component of a nuclear reactor according to claim 1 and claim 2, and an apparatus for carrying out the method according to claim 8, wherein the component to be separated is at least temporarily in contact with the reactor water located in the nuclear reactor.
  • a number of dismantling techniques are known for dismantling nuclear power plants.
  • a mechanical disassembly technique a radioactive component to be disassembled is disassembled by applying mechanical forces.
  • Mechanical dismantling technology however, has its limits with large material thicknesses. It also has the disadvantage that a high level of equipment technology is required.
  • Thermal separation processes are therefore also used to separate a radioactive component of a nuclear reactor. But thermal separation processes are also associated with a high outlay on equipment.
  • a water-abrasive suspension blasting method is known from conventional, non-reactor-technical applications, in which an abrasive material is mixed with a high-pressure water stream, which is directed through a nozzle against a component to be separated and cuts it with the detachment of solid components.
  • the object of the invention is to create a method for separating a radioactive component of a nuclear reactor and a device for carrying out this method, in which the component can be at least temporarily in contact or wetted with the reactor water in the nuclear reactor and radioactive Components of large material thickness can be separated while largely avoiding secondary materials, without requiring a great deal of equipment technology.
  • a suitable abrasive material By selecting a suitable abrasive material, a suitable high pressure and a suitable volume flow applied to the component to be cut, it is possible to cut components of great material thickness, in particular composite materials, in one cut.
  • the method according to the invention permits simple monitoring of the interior of the nuclear reactor in situ, in particular by means of a surveillance camera, since the formation of turbidity in the reactor water and / or dust in the part not at least wetted by the reactor water is avoided.
  • the images recorded by the surveillance camera can be transmitted to a location distant from the nuclear reactor, in particular a control center of a nuclear power plant, so that for the purpose of wachung advantageously no person has to stay near the component to be cut.
  • the device according to the invention has the advantage that it can be operated and monitored safely even in highly radioactive reactor water. Due to the manipulator which can be moved in any direction, the device according to the invention is advantageously not bound locally in a nuclear reactor.
  • the construction of the device according to the invention makes it possible to cut thick material thicknesses, in particular composite materials, by setting the parameters already described.
  • Fig. 1 shows a first embodiment of the present invention
  • Fig. 1 shows the lower part of a reactor pressure vessel 1, which is filled with reactor water 2 up to the reactor water level 3.
  • a radioactive component 4 to be separated in the reactor water 2.
  • the component 4 can be any activated and / or contaminated equipment part in the reactor pressure vessel 1, for example a thermal shield, a core enclosure, a core support structure or a part of the reactor pressure vessel itself, especially its inner and outer walls, as will be described below.
  • a manipulator 5 On the left wall of the reactor pressure vessel 1 shown in FIG. 1 there is a manipulator 5 which can be moved in any direction, in particular in the direction of the reactor water level 3 and the bottom of the reactor pressure vessel 1, as indicated by the direction of movement arrow 6.
  • a holder 7 is movably attached to the manipulator 5.
  • the holder 7 carries a nozzle 8 and a line 9 for transporting a suspension, one end of which is connected to the nozzle 8.
  • the other end of the line 9, referred to below as the suspension line is connected on the one hand to a fresh water line 10 and on the other hand to an abrasive material line 11.
  • fresh water is pumped from a fresh water supply (not shown) via the fresh water line 10 into an abrasive supply 13 and into the suspension line 9.
  • fresh water and abrasive material combine to form the suspension, which is likewise fed to the nozzle 8 by the high-pressure pump 12.
  • the suspension emerging from the nozzle 8 flows in the direction of component 4 and separates it into two parts at a parting line 14.
  • the width of the parting line can be, for example, one millimeter and is particularly dependent on the pressure, the volume flow and the proportion of abrasive with which the suspension strikes the component 4. This pressure is so high that the suspension passes through the component 4 and cuts it into two parts. In the separation process, the suspension passing through the component 4 entrains solid components which consist of chips or the like from the material of the component 4.
  • the suspension and solid components which have passed through the component 4 are sucked off from the separated component 4 by means of a suction device 15.
  • the suction device 15 for example coated with an oxide ceramic, has a cover in the form of a hood 16 which bears against the component 4 and covers the parting line 14 downstream of the component 4.
  • a suction line 17 is connected to the hood 16, through which the waste water consisting of the suspension and the solid components is sucked off by means of a pump 18.
  • the pump 18 Before the wastewater sucked off by the pump 18 reaches the pump 18 itself, it flows through a separator 19 in which the solid components contained in the wastewater are largely separated. These can be returned to the abrasive agent supply 13 by means of an abrasive material return line 20 and / or fed to a solid waste container 21.
  • the solid waste container 21 filled with abrasive agent can be disposed of, as indicated by the arrow 22. The disposal can take place, for example, in the form of a landfill of the solid waste container 21.
  • the waste water cleaned in the separator 19 and from the solid components can be fed to a further separator 23. Solid constituents still contained are separated in the separator 23 and fed to a further solid waste container 24 which, as indicated by the arrow 22, can also be disposed of by landfill.
  • the waste water freed from further solid components by the separator 23 is fed to a filter 25 by means of the pump 18.
  • the wastewater cleaned in the filter 25 can be passed through a filter 26, so that it achieves a quality which enables the water emerging from the filter 26 to be fed to the reactor water 2 and / or the fresh water line 10 via a water return line 27 becomes.
  • the filter units contained in the filters 25, 26 are interchangeable and can be disposed of, as indicated by the arrows 28.
  • New filter units can then be inserted into the filters 25, 26, as indicated by the arrows 29.
  • FIG. The lower part of the reactor pressure vessel 1 shown here has an inner wall 30 which is provided with an austenitic cladding.
  • the outer wall of the reactor pressure vessel 1 is ferritic.
  • the reactor pressure vessel 1 itself is located in a concrete envelope 32, a gap 33 being present between the outer wall 31 of the reactor pressure vessel 1 and the concrete envelope 32.
  • the reactor pressure vessel 1 is filled up to the reactor water level 3 with radioactive reactor water.
  • a manipulator 5 which has a frame 34 which is arranged horizontally in the reactor pressure vessel 1 and which bears with its left and right ends in FIG. 2 against the inner wall 30 of the reactor pressure vessel 1.
  • a connecting member 35 is arranged in the center on the top of the frame 34, so that the manipulator 5 on a crane (not shown) in the reactor can be moved into and out of the reactor pressure vessel 1 by means of a cable 36, as by the arrows 37 indicated.
  • a manipulator arm 38 is arranged on the right side of the frame 34 in FIG. 2 and extends from the frame 34 in the direction of the reactor water level 3.
  • a holder 7 is arranged on the manipulator arm 38 and can be moved on the manipulator arm 38 in the vertical direction, indicated by the direction arrow 6.
  • the holder 7 carries a nozzle 8 and a suspension line 9 which is connected to the nozzle 8.
  • the outlet of the nozzle 8 is aligned in the direction of the inner wall 30 of the reactor pressure vessel 1, so that the inner wall 30 and the outer wall 31 of the reactor pressure vessel 1 can now be dismantled as component 4.
  • the nozzle 8 must be movable about an axis formed by the cable 36.
  • the frame 34 rotates about the axis formed by the cable 36 and that, alternatively or cumulatively, the manipulator arm 38 can be moved radially on the frame 34 about the axis formed by the cable 36.
  • the suction device 15 known from FIG. 1 also has a hood 16 in this case. However, this is not arranged inside the reactor pressure vessel 1, but outside in the gap 33 between the concrete casing 32 and the outer wall 31 of the reactor pressure vessel 1.
  • An annular seal 39 is provided between the outer wall 31 of the reactor vessel 1 and the hood 16.
  • This seal 39 can be an annular tube that can be expanded by means of a fluid.
  • a further line can be attached to the hood 16, with which a fluid in the space 40 is facilitated for the purpose of supporting the removal of the waste water in the space 40 (not shown).
  • a further suction device 41 in the reactor pressure vessel 1 This is also arranged on the holder 7 and can be moved with it, parallel to the nozzle 8. With this device shown in FIG. 2, the inner wall 30 and outer wall 31 of the reactor pressure vessel 1 can be cut in a horizontal direction be severed while reactor water 2 is in the reactor pressure vessel 1. Here, the resulting wastewater is sucked off by the suction devices 15 and 41. In connection with the seal 39, the hood 16 prevents the strongly radiocative reactor water 2 from escaping into the gap 33.
  • the inner wall 30 and outer wall 31 of the reactor pressure vessel 1 are cut in two successive steps:
  • a jet of the suspension is directed under high pressure onto the inner wall 30 of the reactor vessel 1 in such a way that a notch is formed on the inner wall 30 and possibly on the outer wall 31 with the detachment of solid components.
  • the notch can have a geometrically determined or undetermined surface, as long as the wall of the reactor vessel 1 is not completely severed as seen in the flow direction of the suspension.
  • the notch is located below the reactor water level 3.
  • the waste water resulting from the notching, consisting of the suspension and the solid components, is sucked off by means of the suction device 41.
  • the suction is carried out by means of a pump 18, the waste water being fed to a filter 25.
  • the wastewater cleaned in the filter 25 can be disposed of (as shown by arrow 22) or fed to the reactor water 2 by means of a water return line 27.
  • the solid components contained in the waste water are retained in the filter, which can be disposed of, as indicated by arrow 28.
  • a replacement filter can be used again, as indicated by arrow 29.
  • the reactor water level 3 is now lowered to the reactor water level 3, so that the notch above the reactor gate water level 3 '. Then the notch created in the first step is completely severed by means of the suspension emerging through the nozzle 8.
  • Any wastewater located within the reactor pressure vessel 1 is drawn off by the suction device 41 in the manner described above.
  • the wastewater flowing through the separation point is sucked out of the space 40 by means of the suction device 15.
  • the water sucked out of the space 40 via the suction line 17 passes into a separator 19 which is designed as a water-air-solid separator.
  • the separated air can be fed to a preparation by means of a suction blower 43.
  • the separated water and the separated solid components can be fed via a separator line 44 to the suction line 42 and the pump 18, and thus to the filter 25.
  • Suitable abrasives can be silicon carbide, corundum or the like.
  • the fresh water provided in the process can consist of tap water and / or deionized water. The latter advantageously leads to an increase in the rate of expansion of the suspension.

Landscapes

  • Engineering & Computer Science (AREA)
  • Mechanical Engineering (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Food Science & Technology (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Environmental & Geological Engineering (AREA)
  • Working Measures On Existing Buildindgs (AREA)
  • Perforating, Stamping-Out Or Severing By Means Other Than Cutting (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Disintegrating Or Milling (AREA)

Abstract

L'invention concerne un procédé permettant de séparer par fractionnement un composant radioactif d'un réacteur nucléaire, ledit composant étant, au moins temporairement, en contact avec l'eau se trouvant dans le réacteur nucléaire. Le procédé présenté comprend les étapes suivantes: production d'une suspension à partir d'eau fraîche et d'au moins un matériau abrasif; projection sur le composant à séparer d'un jet de ladite suspension sous haute pression de façon que cette suspension traverse le composant en détachant les parties constitutives solides et le découpent; et aspiration de l'eau usée formée par la suspension ayant traversé le composant et les parties constitutives solides. L'invention concerne en outre un dispositif permettant la mise en oeuvre du procédé, qui comporte: au moins une conduite d'alimentation en eau fraîche et au moins une conduite d'alimentation en matériau abrasif, lesquelles débouchent dans une conduite servant à la production d'une suspension; au moins un manipulateur pouvant être déplacé dans une direction quelconque, qui présente une buse servant à produire le jet de suspension dirigé contre le composant; et au moins un dispositif d'aspiration qui est placé en aval du composant.
PCT/EP1999/000972 1998-02-16 1999-02-15 Procede et dispositif pour separer par fractionnement un composant radioactif d'un reacteur nucleaire Ceased WO1999041753A1 (fr)

Priority Applications (2)

Application Number Priority Date Filing Date Title
DE29920718U DE29920718U1 (de) 1998-02-16 1999-02-15 Anordnung und Vorrichtung zum Zertrennen eines radioaktiven Bauteils eines Kernreaktors
AU28339/99A AU2833999A (en) 1998-02-16 1999-02-15 Method for cutting up a radioactive component of a nuclear reactor and device for carrying out said method

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE19806278.8 1998-02-16
DE19806278A DE19806278A1 (de) 1998-02-16 1998-02-16 Verfahren zum Zertrennen eines radioaktiven Bauteils eines Kernreaktors und Vorrichtung hierzu

Publications (2)

Publication Number Publication Date
WO1999041753A1 true WO1999041753A1 (fr) 1999-08-19
WO1999041753B1 WO1999041753B1 (fr) 1999-10-07

Family

ID=7857850

Family Applications (1)

Application Number Title Priority Date Filing Date
PCT/EP1999/000972 Ceased WO1999041753A1 (fr) 1998-02-16 1999-02-15 Procede et dispositif pour separer par fractionnement un composant radioactif d'un reacteur nucleaire

Country Status (3)

Country Link
AU (1) AU2833999A (fr)
DE (2) DE19806278A1 (fr)
WO (1) WO1999041753A1 (fr)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN108655961A (zh) * 2018-04-10 2018-10-16 西安蓝想新材料科技有限公司 核设施水下高压水切割系统

Families Citing this family (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US6402587B1 (en) * 1999-12-22 2002-06-11 General Electric Company Floor mounted ultra high pressure abrasive cutting apparatus
DE102005050942A1 (de) * 2005-10-21 2007-05-03 Areva Np Gmbh Verfahren und Vorrichtung zum Zerlegen eines Einbauteiles eines Kernreaktordruckbehälters
DE102017124738A1 (de) * 2017-10-23 2019-04-25 Nienstedt Gmbh Sammel- und Abfuhrvorrichtung für den Schneidmedienstrahl einer Flüssigkeitsschneidanlage und Flüssigkeitsschneidanlage
DE102019133183A1 (de) * 2019-12-05 2021-06-10 RWE Nuclear GmbH Lastaufnehmende Vorrichtung und entsprechendes Verfahren
US11518058B2 (en) 2019-12-16 2022-12-06 Nienstedt Gmbh Collecting and discharging device for the cutting jet of a liquid cutting system

Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2638671A1 (fr) * 1988-11-10 1990-05-11 Von Laue Paul Langevin Inst Ma Dispositif et procede de decoupe de pieces irradiees par jet d'eau sous pression
US5001870A (en) * 1987-10-05 1991-03-26 Kajima Corporation Method of cutting and disassembling cylindrical structure
EP0520907A1 (fr) * 1991-06-28 1992-12-30 Gec Alsthom Acb Procédé et installation pour le traitement de surface ou la découpe par jet d'eau à haute pression
FR2741991A1 (fr) * 1995-11-30 1997-06-06 Cogema Procede et installation de demantelement a distance de structures irradiees
DE19614614A1 (de) * 1996-04-13 1997-10-16 Preussag Noell Gmbh Verfahren zum Zerlegen und Verpacken eines Reaktordruckbehälters

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2259345A1 (de) * 1972-12-04 1974-06-06 Siemens Ag Verfahren zur reinigung von kernkraftwerksanlagen
EP0234365A1 (fr) * 1986-02-21 1987-09-02 Balduf Verfahrenstechnik GmbH Installation pour le traitement abrasif de surfaces
DE19613466A1 (de) * 1996-04-04 1997-10-09 Gutehoffnungshuette Man Verfahren zum Entsorgen von stillgelegten Reaktor-Druckbehältern in Kernkraftwerken

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5001870A (en) * 1987-10-05 1991-03-26 Kajima Corporation Method of cutting and disassembling cylindrical structure
FR2638671A1 (fr) * 1988-11-10 1990-05-11 Von Laue Paul Langevin Inst Ma Dispositif et procede de decoupe de pieces irradiees par jet d'eau sous pression
EP0520907A1 (fr) * 1991-06-28 1992-12-30 Gec Alsthom Acb Procédé et installation pour le traitement de surface ou la découpe par jet d'eau à haute pression
FR2741991A1 (fr) * 1995-11-30 1997-06-06 Cogema Procede et installation de demantelement a distance de structures irradiees
DE19614614A1 (de) * 1996-04-13 1997-10-16 Preussag Noell Gmbh Verfahren zum Zerlegen und Verpacken eines Reaktordruckbehälters

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN108655961A (zh) * 2018-04-10 2018-10-16 西安蓝想新材料科技有限公司 核设施水下高压水切割系统

Also Published As

Publication number Publication date
AU2833999A (en) 1999-08-30
WO1999041753B1 (fr) 1999-10-07
DE19806278A1 (de) 1999-08-26
DE29920718U1 (de) 2000-03-02

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