EP0159232B1 - Dampferzeuger insbesondere für Druckwasserkernreaktor - Google Patents

Dampferzeuger insbesondere für Druckwasserkernreaktor Download PDF

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Publication number
EP0159232B1
EP0159232B1 EP85400504A EP85400504A EP0159232B1 EP 0159232 B1 EP0159232 B1 EP 0159232B1 EP 85400504 A EP85400504 A EP 85400504A EP 85400504 A EP85400504 A EP 85400504A EP 0159232 B1 EP0159232 B1 EP 0159232B1
Authority
EP
European Patent Office
Prior art keywords
tube plate
water box
water
steam generator
conical
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.)
Expired
Application number
EP85400504A
Other languages
English (en)
French (fr)
Other versions
EP0159232A1 (de
Inventor
Jean-Paul Badoux
Jean Edmond Chaix
Michel Metteey
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.)
Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
Original Assignee
Commissariat a lEnergie Atomique CEA
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 Commissariat a lEnergie Atomique CEA filed Critical Commissariat a lEnergie Atomique CEA
Publication of EP0159232A1 publication Critical patent/EP0159232A1/de
Application granted granted Critical
Publication of EP0159232B1 publication Critical patent/EP0159232B1/de
Expired legal-status Critical Current

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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
    • F22B37/02—Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
    • F22B37/22—Drums; Headers; Accessories therefor
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B1/00—Methods of steam generation characterised by form of heating method
    • F22B1/02—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
    • F22B1/023—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers with heating tubes, for nuclear reactors as far as they are not classified, according to a specified heating fluid, in another group
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F28—HEAT EXCHANGE IN GENERAL
    • F28F—DETAILS OF HEAT-EXCHANGE AND HEAT-TRANSFER APPARATUS, OF GENERAL APPLICATION
    • F28F9/00—Casings; Header boxes; Auxiliary supports for elements; Auxiliary members within casings
    • F28F9/02—Header boxes; End plates
    • F28F9/0219—Arrangements for sealing end plates into casing or header box; Header box sub-elements
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F28—HEAT EXCHANGE IN GENERAL
    • F28F—DETAILS OF HEAT-EXCHANGE AND HEAT-TRANSFER APPARATUS, OF GENERAL APPLICATION
    • F28F2275/00—Fastening; Joining
    • F28F2275/20—Fastening; Joining with threaded elements

Definitions

  • the subject of the invention is a steam generator, in particular for a pressurized water nuclear reactor.
  • the enclosure 1 of the reactor in which the core 2 is located is shown and or on the one hand circulates in 3 the ascending hot water leaving the core in the direction of the arrows F and on the other hand, l cold water flowing between the casing 1 and the basket 4 of the reactor.
  • the steam generator 5 comprises, in known manner, a water box 6, in which the water from the reactor 1 circulates, and, above this water box 6, a ferrule 7 traversed by the secondary water which enters at 6 and leaves at 9 from this secondary ferrule 7.
  • a conduit 10 connects the reactor 1 with the water box 6 and in fact comprises two concentric annular passages, namely a central passage 11 through which the hot water enters the water box 6 and a peripheral passage 12 through which comes out the cold water coming from this same water box 6 and returning to the reactor 1 between the basket 4 and the enclosure 1 to be reinjected at the base of the heart.
  • the water box 6 is separated from the secondary shell 7 by a tube plate 13 in which are vertically located a number of heat exchanger tubes 14 in the form of an inverted U and traversed by the primary fluid; this water box 6 is divided into two parts, namely a hot compartment 15 and a cold compartment 16.
  • the secondary water which flows upwardly inside the secondary shell 7, gradually heats up and vaporizes in going up along the previous U-shaped tubes 14 (figs. 1 and 2).
  • the secondary ferrule 7 is welded directly to the tube plate 13 which is fixed by clamping on the water box 6. This is the case, in particular, of the example of implementation described in document DE-U-7 312164 and corresponding to the left half of the single figure.
  • stresses accumulate in the angular zone of connection of this plate 13 with the secondary ferrule 7.
  • the tube plate is tightened, by a system of screws and bolts, between the secondary ferrule and the water box, and any disassembly of this lower part of the installation leads to the complete separation of the three preceding components.
  • the present invention specifically relates to a steam generator, in particular for pressurized water nuclear reactors which allows, by means of simple means to be implemented, to make a connection between the secondary shell and the tube plate without accumulation of lateral constraints and which also makes the steam generator completely removable, without dissociating it from the secondary shell.
  • the handling lugs located at the periphery of the tube plate comprise housings whose conical profile makes it possible to receive the conical collars which equip the studs, thus allowing during a disassembly operation from the single water box, handling of the plate-to-secondary ferrule assembly without breaking their seal.
  • the secondary shell, the tube plate and the water box are therefore independent of each other and perfectly removable assemblies. Furthermore, the closure of the water box and that of the secondary enclosure of the steam generator are carried out in a global manner and by means which are also independent. In the generator that is the subject of the invention, this thus achieves the total removal of the stresses in the angular zone of connection of the tube plate with the secondary ferrule, which makes it possible to increase the number of exchange tubes of heat contained in this shell and, moreover, the complete disassembly of the steam generator makes its use much easier than that of welded generators of the prior art.
  • FIG 3 there is shown the secondary ferrule 7, the tube plate 13 and the water box 6.
  • the secondary ferrule 7 ends in accordance with the invention at its lower part by an annular peduncle 20 having a double conical bearing 21 and 22 at its lower part for connection with the tube plate 13.
  • the latter comprises for this purpose a corresponding female groove 23 also comprising two conical bearing surfaces intended to cooperate with the conical bearing surfaces 21 and 22 of the peduncle 20.
  • Two seals metal toric sealing 24 ensure the sealing between the tube plate 13 and the secondary ferrule 7 when the assembly, as will be seen below, is tightened by the tie rod 25 and the clamping ring 26.
  • the upper part of the peduncle 20 also has a conical bearing 27 cooperating with a corresponding bearing of this clamping ring 26.
  • the water box 6 is provided with a plane connection bearing t 28 with two metal O-rings interposed 29 between the water box 6 and the tube plate 13.
  • Tightening in the vertical direction of the three preceding independent elements is carried out using tie rods 25, nuts 30 and studs 31 installed, in accordance with the invention, in the water box 6.
  • a certain number of handling lugs such as 32 which comprise housings 33 with a conical bearing 34 for the studs 31, which comprise in this case Indeed, a conical collar 35 intended to come into abutment against the corresponding conical part 34.
  • This allows, when it is desired for any reason, for example a maintenance operation, to disassemble the water box 6 without breaking the seal of the tube plate 13 and of the secondary shell 7, of handling this tube plate 13, by means of tie rods 25 passing through the ears 32, while maintaining a tight contact with the secondary shell 7.
  • the sequence of operations is in this case the next.
  • the handling lugs 32 are three in number on the periphery and each comprise two housings 33a and 33b for the studs 31. These housings 33a and 33b make it possible to protect the threads of the studs 31 during handling operations. The number of these studs used for resuming tightening is determined so that we can ward off the possibility of one of them seizing up during maneuver.

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Thermal Sciences (AREA)
  • Mechanical Engineering (AREA)
  • General Engineering & Computer Science (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Sustainable Development (AREA)
  • Sustainable Energy (AREA)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Coupling Device And Connection With Printed Circuit (AREA)
  • Multi-Conductor Connections (AREA)

Claims (2)

1. Dampferzeuger, insbesondere für Druckwasser-Kernreaktoren, mit einem Wasserkasten (6), wo das den Reaktorkern verlassende, heiße Wasser strömt, um folgend in eine Reihe von Wärmetauscherrohren (14) einzudringen, die in einer Rohrplatte (13) montiert sind und sich im Inneren eines von Sekundärwasser durchströmten Sekundärmantels (7) befinden, wobei der Wasserkasten, der Sekundärmantel und die Rohrplatte drei unabhängige und ausbaubare Einheiten bilden, der Sekundärmantel an seinem unteren Abschnitt mit einer ringförmigen Spindel (20) endet, der Wasserkasten an seinem oberen Abschnitt mit einem Flansch endet, der mit einer ebenen Verbindungsfläche (28) ausgerüstet ist, und ein System von Zugstangen (25) den Zusammenbau und die dichte Klemmung der drei vorhergehenden, unabhängigen Einheiten sicherstellt, dadurch gekennzeichnet, daß
- die ringförmige Spindel (20) einerseits eine doppelte Konusfläche (21, 22), die mit zwei Ringdichtungen (24) mit einer weiblichen Rille (23) mit zwei Konusflächen zusammenarbeitet, die in der oberen Oberfläche der Rohrplatte (13) vertieft ist und andererseits auf ihrem Außenumfang eine Konusfläche (27) aufweist, die einem Klemmring (26) zugeordnet ist;
- die ebene Verbindungsfläche (28) zwei Ringdichtungen (29) umfaßt, die an der unteren Oberfläche der Rohrplatte (13) eingefügt sind;
- das System von Zugstangen (25), von denen gewisse (39,40) Transportösen (32) am Umfang der Rohrplatte (13) durchqueren, von in dem Flansch des Wasserkastens (6) montierten Bolzen (31) und von Muttern (30) mittels eines - Klemmrings (26) den Zusammenbau und die dichte Klemmung der drei vorhergehenden, unabhängigen Einheiten sicherstellt.
2. Dampferzeuger nach Anspruch 1, dadurch gekennzeichnet, daß die Transportösen (32), die am Umfang der Rohrplatte angebracht sind, Aufnahmen (33) aufweisen, deren konisches Profil (34) erlaubt, die konischen Ränder (35), mit denen die Bolzen (31) ausgerüstet sind, aufzunehmen, wodurch somit bei einer Ausbautätigkeit des einzigen Wasserkastens der Transport der Gesamtheit aus Rohrplatte und Sekundärmantel ohne Unterbrechung ihrer Dichtheit möglich ist.
EP85400504A 1984-03-23 1985-03-15 Dampferzeuger insbesondere für Druckwasserkernreaktor Expired EP0159232B1 (de)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
FR8404563A FR2561753B1 (fr) 1984-03-23 1984-03-23 Generateur de vapeur, notamment pour reacteur nucleaire a eau pressurisee
FR8404563 1984-03-23

Publications (2)

Publication Number Publication Date
EP0159232A1 EP0159232A1 (de) 1985-10-23
EP0159232B1 true EP0159232B1 (de) 1988-06-08

Family

ID=9302405

Family Applications (1)

Application Number Title Priority Date Filing Date
EP85400504A Expired EP0159232B1 (de) 1984-03-23 1985-03-15 Dampferzeuger insbesondere für Druckwasserkernreaktor

Country Status (6)

Country Link
US (1) US4683112A (de)
EP (1) EP0159232B1 (de)
JP (1) JPS60213701A (de)
CA (1) CA1225463A (de)
DE (1) DE3563259D1 (de)
FR (1) FR2561753B1 (de)

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US8522729B2 (en) * 2008-07-18 2013-09-03 Babcock & Wilcox Power Generation Group, Inc. Contoured flat stud and stud arrangement for cyclone slag taps
US11901088B2 (en) 2012-05-04 2024-02-13 Smr Inventec, Llc Method of heating primary coolant outside of primary coolant loop during a reactor startup operation
US9892806B2 (en) 2012-05-04 2018-02-13 Smr Inventec, Llc Space saver flanged joint for a nuclear reactor vessel

Family Cites Families (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE7312164U (de) * 1974-04-18 Siemens Ag Dampferzeuger für Kernkraftwerke
US2343502A (en) * 1942-10-12 1944-03-07 David E Fields Follower ring for heat exchanger dome plates
US2807445A (en) * 1954-06-16 1957-09-24 Griscom Russell Co Heat exchanger welded tube joint
FR1228182A (fr) * 1958-03-05 1960-08-26 Superheater Co Ltd Perfectionnements aux échangeurs de chaleur tubulaires
DE1119884B (de) * 1960-09-30 1961-12-21 Licentia Gmbh Rohrbuendel-Waermetauscher
JPS4936279U (de) * 1972-07-06 1974-03-30
JPS5381470U (de) * 1976-12-09 1978-07-06
US4162191A (en) * 1977-04-29 1979-07-24 Alexander Cella Modular steam generator for use in nuclear power plants
FI60441C (fi) * 1977-07-12 1982-01-11 Hans Viessmann Foerbindelseanordning foer vaermepanna
FR2462003A1 (fr) * 1979-07-24 1981-02-06 Commissariat Energie Atomique Chaudiere nucleaire

Also Published As

Publication number Publication date
FR2561753B1 (fr) 1986-07-04
FR2561753A1 (fr) 1985-09-27
DE3563259D1 (en) 1988-07-14
CA1225463A (en) 1987-08-11
JPS60213701A (ja) 1985-10-26
EP0159232A1 (de) 1985-10-23
US4683112A (en) 1987-07-28
JPH0578722B2 (de) 1993-10-29

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