EP0719441A1 - Procede de demantelement et de recyclage d'un generateur de vapeur usage d'un reacteur nucleaire a eau sous pression - Google Patents
Procede de demantelement et de recyclage d'un generateur de vapeur usage d'un reacteur nucleaire a eau sous pressionInfo
- Publication number
- EP0719441A1 EP0719441A1 EP94925531A EP94925531A EP0719441A1 EP 0719441 A1 EP0719441 A1 EP 0719441A1 EP 94925531 A EP94925531 A EP 94925531A EP 94925531 A EP94925531 A EP 94925531A EP 0719441 A1 EP0719441 A1 EP 0719441A1
- Authority
- EP
- European Patent Office
- Prior art keywords
- steam generator
- tubes
- cutting
- elements
- bundle
- 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- Withdrawn
Links
Classifications
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B37/00—Component parts or details of steam boilers
- F22B37/002—Component parts or details of steam boilers specially adapted for nuclear steam generators, e.g. maintenance, repairing or inspecting equipment not otherwise provided for
- F22B37/007—Installation or removal of nuclear steam generators
-
- 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
- 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
- G21F9/28—Treating solids
- G21F9/30—Processing
-
- 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
Definitions
- the present invention relates to a method for dismantling a used steam generator of a pressurized water nuclear reactor.
- the generator 'highly radioactive steam is subject to periodic radiation monitoring.
- the object of the invention is to avoid storing and monitoring the steam generator out of service and to propose a method of dismantling the steam generator producing a reduced volume of waste and making it possible to recover or recycle certain noble materials contained in the steam generator, in particular the Inconel used for the manufacture of certain elements of the primary part of the steam generator.
- the invention relates to a process for dismantling a used steam generator of a pressurized water nuclear reactor, comprising a primary part connected to the primary circuit of the reactor, this primary part comprising elements
- LOCATION SHEET metallic contaminated by contact, in operation, with a coolant of the reactor core, characterized in that:
- the internal surface of the metal elements of the primary part is decontaminated by circulation of a hard acid decontamination solution comprising valence cerium IV in contact with this surface,
- the steam generator is cut so as to separate the decontaminated metal elements from the rest of the steam generator
- the decontaminated metallic elements are remelted and treated so as to form new metallic elements.
- the invention applies in particular to a steam generator whose primary part comprises a bundle of U-shaped tubes of nickel alloy fixed at their ends in a tubular steel plate delimiting with a substantially spherical steel bottom a box coolant, connected to U-shaped tubes, comprising two compartments separated by a nickel alloy partition, this steam generator further comprising an external envelope comprising a lower ferrule containing the bundle of tubes, connected at one end to the plate tubular and at the other end to an upper shell containing a steam drying assembly.
- the steam generator is cut so as to separate the tubular plate, the bundle tubes, the bottom of the water box and the partition separating them from the water box,
- the upper shell is separated from the rest of the steam generator by cutting out the outer casing in a plane transver ⁇ sal substantially at the junction between the lower shell and the upper shell,
- the steam generator is positioned substantially vertically and the lower shell is filled with water up to a predetermined height measured from the tube plate, - the water contained in the lower shell is frozen,
- the bundle of tubes is separated from the tube plate by cutting in a transverse plane of the steam generator at the level of the mass of ice, - the tubes are extracted from the lower shell,
- the tubular plate is separated from the water box by cutting in a transverse plane of this water box near its junction edge with the tubular plate
- the partition is separated from the bottom of the water box by cutting of this partition near its junction edge with the bottom.
- the steam generator is cut at the level of the ice mass by means of a band saw
- the water box is cut close to its junction edge with the tube plate by means of a band saw
- - flame cutting is carried out by means of a carriage, carrying a cutting torch, guided along the junction edge of the partition with the bottom of the water box,
- the steam generator is positioned substantially horizontally so that the U-tubes of the bundle are substantially parallel to a horizontal plane, then the U-tubes are extracted from the ferrule lower by horizontal translation,
- the predetermined height of water in the lower shell, measured from the tube plate, is approximately 1 meter
- the outer surface of the lower shell is insulated and its open end is closed after separation from the upper shell with a heat-insulating plug
- the tubular plate - re, the bottom and the partition of the water box are cut by flame cutting, the decontaminated metal elements are remelted in an electric induction heating oven,
- the bundle tubes and the partition are melted and treated by adding alloying elements so as to obtain new elements made of nickel alloy chosen from the Inconel 690, the Incoloy 800 and the Hastelloy C22 or stainless steel according to the American standard AISI 316,
- the new nickel alloy elements are used to manufacture tubes for the steam generator of a nuclear installation
- the new steel or cast iron elements are used to manufacture shielded enclosures for the packaging of nuclear waste.
- FIG. 1 is an elevational view, with a partial longitudinal section, of a used steam generator of a nuclear reactor pressurized water, in vertical position, intended to be dismantled by the method according to the invention
- - Figure 2 is a view similar to Figure 1 in which the upper shell has been separated from the rest of the steam generator and the lower shell has been insulated
- - Figure 3 is an elevational view of an installation for extracting the tubes from the bundle of the lower shell, and for cutting these tubes, the steam generator being in the horizontal position and being shown diagrammatically;
- FIG. 4 is a top view of the installation of Figure 3, in which the steam generator has not been shown;
- FIG. 5 is a perspective view of the water box separated from the rest of the steam generator intended to be dismantled according to the method of the invention.
- FIG. 1 shows a steam generator of a pressurized water nuclear reactor, designated by the general reference 10, of generally cylindrical shape, in a substantially vertical position corresponding to its usual position when it is in operation. .
- the steam generator 10 comprises an outer casing 12, of steel, comprising a lower ferrule 14 connected at its lower end to a tubular plate 15 of very thick, made of steel, and at its upper end to an upper ferrule 16 via of a frustoconical connection part 18.
- the upper shell 16 contains a steam drying assembly (not shown in the figures) and the lower shell 14 contains a vaporizer assembly comprising a bundle 20 of tubes 22 bent into a U , arranged in successive layers and comprising upper parts in the form of semi-circular hangers 22A forming a bun of the bundle 20.
- the bundle 20 usually comprises several thousand tubes of which only a few have been shown in Figure 1, for reasons of clarity.
- the straight parts 22B of the tubes of the bundle 20 are crimped at their ends in the tubular plate 15, so as to open into a water box 24 delimited by this tubular plate 15 and a substantially spherical bottom 26 of steel comprising two compartments separated by a partition 28.
- the tubes of the bundle 20 and the partition wall 28 of the water box are made of a nickel alloy of the Inconel 600 type.
- the tubes 22 of the bundle and the water box 24 form the primary part of the steam generator 10, this being connected to the primary circuit of the reactor in which circulates, in operation, a coolant for cooling the reactor core, by two openings 30, 32 upstream and downstream respectively provided in the two compartments of the water box 24.
- FIG. 1 also shows plates 34 for bracing the rectilinear parts of the tubes 22, anti-vibration bars 36 disposed on the curved parts of the tubes 22, and an internal ferrule 38 surrounding the bundle 20, intended to channel the edible water circulating in the steam generator 10.
- These various elements are made of steel.
- the steam generator 10 is isolated from the primary circuit, then the internal surface of the tubes 22 of the bundle and of the water box 24 is decontaminated, in contact with the coolant of the reactor core when the generator steam is in operation, by circulation of a solution of hard acid decontamination comprising valence IV cerium in contact with this surface.
- a solution of hard acid decontamination comprising valence IV cerium in contact with this surface.
- the steam generator 10 is cut so as to separate the lower 14 and upper 16 ferrules 16, the tube plate 15, the tubes 22 of the harness, the bottom 26 and the partition wall 28 of the water box, as will be described below.
- the upper shell 16 and the drying assembly are separated from the rest of the steam generator by cutting out the external envelope 12 in a transverse plane H1, substantially at the junction between this upper shell and the connecting part 18, with mechanical means of known type (see Figure 1).
- the lower shell 14 is filled with water to a predetermined height of approximately 1 meter from the tubular plate 15. Then the external surface of the lower shell 14 with a coating 40 of known type, and the end of this open shell 14 is closed after separation from the upper shell 16 by a heat-insulating plug 42, as shown in FIG. 2.
- the water is frozen by circulation of cold air in the tubes 22 of the bundle and in the water box 24.
- the cold air is produced by a refrigeration unit 44 connected by a duct 46 to the upstream opening 30 of the water box.
- the downstream opening 32 of the water box is connected to a duct 48 for evacuating the heated air.
- the water is frozen to a temperature of about -20 "C.
- the mass of ice obtained makes it possible to join together the lower ends of the lower ferrule 14, of the tubes 22 of the bundle and of the internal ferrule 38.
- the bundle 20 of tubes is separated from the tube plate 15 by cutting the steam generator in a transverse plane H2 at the level of the frozen body of water, at a height of approximately between 60 and 80cm above the tube plate 15, using a band saw 50 of known type (see Figure 2).
- the metallic elements embedded in the ice have very different thicknesses.
- the lower ferrule 14 has a thickness of approximately 80mm and the tubes 22 of the bundle have a thickness of approximately 1mm.
- the steam generator 10 is positioned substantially horizontally, on cradles 53, so that the U-shaped tubes 22 of the bundle are substantially parallel to a horizontal plane.
- the installation 52 for extracting and cutting the tubes 22 comprises a substantially horizontal platform 54 carried by uprights 56 so as to be adjustable in height.
- the platform 54 is arranged in the extension of the bun of the bundle 20 of tubes.
- the installation 52 further comprises means for hooking and extracting the tubes 22, of known type, comprising in particular a winch 58, intended to move the tubes 22 in horizontal translation by sliding them on the platform 54.
- the tubes 22 are extracted one by one or preferably by sheet.
- the height of the platform 54 is adjusted as a function of the height of the successive layers of tubes which it is desired to extract.
- disc saws 60 slidably mounted on guides 62 perpendicular to the rectilinear branches 22B of the tubes 22, spaced longitudinally between them at distances equal to the length of the sections of tubes which it is desired to obtain.
- the tubes 22 can be cut elsewhere than on the platform 54 with other cutting means than disc saws 60, for example with shears.
- the length of the tube sections is between approximately 0.8 and 1 m.
- the tubular plate 15 is separated from the water box 24 by cutting out this water box 24 in a transverse plane H3, near its junction edge with the tubular plate 15 (see FIG. 2).
- this cutting is carried out by means of the band saw 50 used beforehand to separate the tube plate 15 from the tubes 22 of the bundle.
- this water box 24 is placed on supports 64 so that its open face is substantially horizontal (see FIG. 5), and the partition is separated 28 from the bottom 26 of the water box by cutting this partition near its junction edge with the bottom.
- this cutting is carried out by flame cutting with means as shown in FIG. 5.
- 1Oxycutting is carried out by means of a carriage 66, of known type (shown diagrammatically in FIG. 5) carrying a cutting torch, not shown in this figure, guided along the junction edge of the partition 28 with the bottom 26 by means of a rack 67 fixed near this junction.
- the partition 28 is attached to a bracket 68 of known type, carried by the edge of the bottom 26, so as' to be maintained during the operation oxycou ⁇ page.
- these elements After cutting up the decontaminated metallic elements of the primary part of the steam generator, these elements are remelted, preferably in an electric furnace with induction heating, and they are treated so as to form new metallic elements.
- the fumes leaving the electric furnace are treated and filtered by known means so as to avoid the rejection to the atmosphere of contaminated particles contained in these fumes.
- the sections of tubes 22 and of partition wall 28 which are made of Inconel 600, are remelted and treated by adding an alloy element so as to obtain new elements made of a nickel alloy chosen for example from the Inconel 690, Incoloy 800, Hastelloy C22 or stainless steel according to American standard AISI 316.
- the sections of tubular plate 15 and bottom 26 which are made of steel are remelted and optionally treated by adding alloying elements so to obtain new steel or cast iron elements.
- the new metallic elements obtained by reflow of the decontaminated metallic elements of the primary part of the steam generator have activities such that they can be used in nuclear installations.
- the new elements in nickel alloy preferably in Inconel 690
- the new elements in steel or cast iron are used to manufacture enclosures shielded for the conditioning of nuclear waste.
- the lower 14 and upper 16 ferrules of the external envelope of the steam generator and the internal ferrule 38 surrounding the bundle 20 of tubes, are not contaminated and can be reused at least partially in nuclear installations.
- the spacer plates 34, the anti-vibration bars 36 and the various elements attached to the lower and upper ferrules are recovered after dismantling the steam generator and sectioned so as to be treated like ordinary uncontaminated scrap elements.
- the invention is not limited to the embodiment described.
- it can be applied to any used steam generator of a pressurized water nuclear reactor, comprising a primary part comprising metallic elements in which circulates, in operation, a coolant for cooling the reactor core, for example a bundle of straight, vertical primary water tubes connected at each of their ends to a tubular plate and a water box, or else a bundle of horizontal primary water tubes, the ends of which are connected to primary water inlet and outlet spaced apart.
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Thermal Sciences (AREA)
- Mechanical Engineering (AREA)
- Plasma & Fusion (AREA)
- Processing Of Solid Wastes (AREA)
Abstract
Description
Claims
Applications Claiming Priority (3)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR9311055A FR2710182B1 (fr) | 1993-09-16 | 1993-09-16 | Procédé de démantèlement d'un générateur de vapeur usagé d'un réacteur nucléaire à eau sous pression. |
FR9311055 | 1993-09-16 | ||
PCT/FR1994/001027 WO1995008173A1 (fr) | 1993-09-16 | 1994-08-29 | Procede de demantelement d'un generateur de vapeur usage d'un reacteur nucleaire a eau sous pression |
Publications (1)
Publication Number | Publication Date |
---|---|
EP0719441A1 true EP0719441A1 (fr) | 1996-07-03 |
Family
ID=9450941
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
EP94925531A Withdrawn EP0719441A1 (fr) | 1993-09-16 | 1994-08-29 | Procede de demantelement et de recyclage d'un generateur de vapeur usage d'un reacteur nucleaire a eau sous pression |
Country Status (7)
Country | Link |
---|---|
EP (1) | EP0719441A1 (fr) |
KR (1) | KR960705326A (fr) |
AU (1) | AU7540194A (fr) |
FR (1) | FR2710182B1 (fr) |
TW (1) | TW247364B (fr) |
WO (1) | WO1995008173A1 (fr) |
ZA (1) | ZA947121B (fr) |
Families Citing this family (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2853129B1 (fr) * | 2003-03-28 | 2005-09-09 | Salvarem | Procede et produit de decontamination radioactive |
FR2917154B1 (fr) * | 2007-06-06 | 2009-10-02 | Areva Np Sas | Procede de demantelement pour la reutilisation des elements de l'enveloppe de pression d'un generateur de vapeur usage d'une centrale nucleaire. |
CN106369886B (zh) * | 2016-11-07 | 2022-07-08 | 珠海格力电器股份有限公司 | 干式蒸发器 |
Family Cites Families (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4199857A (en) * | 1978-05-01 | 1980-04-29 | Westinghouse Electric Corp. | Tube bundle removal method and apparatus |
EP0043394A1 (fr) * | 1980-07-02 | 1982-01-13 | Westinghouse Electric Corporation | Anneau de protection contre les radiations pour démonter des parties d'un générateur de vapeur nucléaire |
DE3331383A1 (de) * | 1983-08-31 | 1985-03-14 | Siempelkamp Gießerei GmbH & Co, 4150 Krefeld | Anlage fuer rueckgewinnung metallischer komponenten von kernkraftwerken |
DE3404106C2 (de) * | 1984-02-07 | 1986-10-02 | Siempelkamp Gießerei GmbH & Co, 4150 Krefeld | Ofenanlage zum Aufschmelzen metallischer Komponenten von Kernkraftwerken |
SE465142B (sv) * | 1988-08-11 | 1991-07-29 | Studsvik Ab | Foerfarande foer dekontaminering av korrosionsprodukter i kaernkraftsreaktorer |
FR2687005B1 (fr) * | 1992-02-03 | 1994-10-21 | Framatome Sa | Procede et installation de decontamination de la partie primaire d'un generateur de vapeur usage d'un reacteur nucleaire a eau ordinaire sous pression. |
-
1993
- 1993-09-16 FR FR9311055A patent/FR2710182B1/fr not_active Expired - Fee Related
-
1994
- 1994-08-29 EP EP94925531A patent/EP0719441A1/fr not_active Withdrawn
- 1994-08-29 WO PCT/FR1994/001027 patent/WO1995008173A1/fr not_active Application Discontinuation
- 1994-08-29 AU AU75401/94A patent/AU7540194A/en not_active Abandoned
- 1994-08-29 KR KR1019960701416A patent/KR960705326A/ko not_active Application Discontinuation
- 1994-09-15 TW TW083108529A patent/TW247364B/zh active
- 1994-09-15 ZA ZA947121A patent/ZA947121B/xx unknown
Non-Patent Citations (1)
Title |
---|
See references of WO9508173A1 * |
Also Published As
Publication number | Publication date |
---|---|
FR2710182A1 (fr) | 1995-03-24 |
TW247364B (fr) | 1995-05-11 |
KR960705326A (ko) | 1996-10-09 |
AU7540194A (en) | 1995-04-03 |
FR2710182B1 (fr) | 1995-12-08 |
ZA947121B (en) | 1996-03-15 |
WO1995008173A1 (fr) | 1995-03-23 |
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