EP0045034B1 - Einrichtung zur Vermeidung von Rissbildungen an den Innenflächen von in Druckbehälter mündenden Speisewasserleitungsstutzen - Google Patents

Einrichtung zur Vermeidung von Rissbildungen an den Innenflächen von in Druckbehälter mündenden Speisewasserleitungsstutzen Download PDF

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Publication number
EP0045034B1
EP0045034B1 EP81105706A EP81105706A EP0045034B1 EP 0045034 B1 EP0045034 B1 EP 0045034B1 EP 81105706 A EP81105706 A EP 81105706A EP 81105706 A EP81105706 A EP 81105706A EP 0045034 B1 EP0045034 B1 EP 0045034B1
Authority
EP
European Patent Office
Prior art keywords
feed water
water
piping section
steam
pressure container
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
EP81105706A
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German (de)
English (en)
French (fr)
Other versions
EP0045034A1 (de
Inventor
Hans Dipl.-Ing Mayer
Zvonimir Dipl.-Ing. Sterk
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.)
Kraftwerk Union AG
Original Assignee
Kraftwerk Union AG
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 Kraftwerk Union AG filed Critical Kraftwerk Union AG
Publication of EP0045034A1 publication Critical patent/EP0045034A1/de
Application granted granted Critical
Publication of EP0045034B1 publication Critical patent/EP0045034B1/de
Expired legal-status Critical Current

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Classifications

    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22STEAM GENERATION
    • F22BMETHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B37/00Component parts or details of steam boilers
    • F22B37/02Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
    • F22B37/22Drums; Headers; Accessories therefor
    • F22B37/228Headers for distributing feedwater into steam generator vessels; Accessories therefor

Definitions

  • the invention relates to a device for avoiding the formation of cracks on the inner surfaces of feed water line nozzles opening into pressure vessels, in particular nuclear reactor pressure vessels or steam generators, according to the preamble of claim 1.
  • Such a device is known for steam generators of nuclear reactors from US-A-3661 123.
  • cooler medium is replenished in a system (container, pipeline) that is filled with an elevated temperature medium, i.e. a feed water pipe socket
  • the horizontal connecting piece will be stratified by colder and warmer medium if the Feeding with low throughput in relation to the size of the connection cross-section, d. H. small flow velocities.
  • the respective temperature differences of the two media lead to thermal stresses in the connecting piece or in the connecting line, which are usually already highly stressed by the internal pressure of the system, so that material fatigue and thus crack formation can occur with a sufficiently high number of cycles of the feeding processes.
  • the phenomenon of temperature stratification could be demonstrated by temperature measurements on the feed water pipe socket of a steam generator for pressurized water reactors.
  • the thermal voltage problems mentioned at the outset can still occur in partial areas of the feed water line connecting piece. Decisive for this is - as was found - a certain dimensioning of the feed water pipe socket, namely its horizontal distance An from the pressure vessel inner wall to the overflow edges, and its inside diameter D i , whereby the ratio A i / D i should be as small as possible.
  • the invention has for its object to provide the device of the type mentioned in such a way that with weak feeding of the feed water pipe connection, as occurs in part-load or no-load operation of a system, material fatigue and thus crack formation on the load cycles even under higher load cycles Trim is excluded with certainty.
  • the object is achieved by the features listed in the characterizing part of claim 1.
  • An advantageous further development of the subject matter of claim 1 is described in dependent claim 2.
  • the advantages achievable with the invention can be seen above all in the fact that a backflow of the specifically lighter medium in the fed system against the heavier (still cold) medium to be fed in is prevented.
  • the invention solves not only the problems of thermal stresses and cracking that occur in particular under no-load and low-load operation, but also the problems that arise during start-up and shutdown operation.
  • the steam generator DE for pressurized water reactors according to FIG. 1 has a pressure vessel housing 1 with a primary chamber region 1.1, an evaporator region 1.2 with the U-shaped heat-exchanging tubes 2 and a conically widening housing - Transition area 1.3 adjoining separator area 1.4.
  • the tube sheet 3 welded into the housing 1 and the heat exchanger tubes 2 welded into it and held by it separate the primary chamber I from the secondary chamber 11 in a gas-tight manner.
  • the primary chamber is formed by a base cap 4 welded to the tube sheet 3 and having an inlet connection E and an outlet connection A, whereby the inflow space e1 of the primary chamber is separated from the outflow space a1 by an arched partition 5.
  • the tubes 2 of the tube bundle 2 ' only the outer and inner are indicated by lines; the pipe bends are marked 2.1, the inner pipe lane is marked 2.2.
  • the primary medium (water) heated in the core of the pressurized water reactor, not shown is supplied to the primary chamber 1 via the inlet connection E at a temperature of approx. 316 ° C. and under a pressure of 155 bar, flows through the heat-exchanging pipes 2 and is discharged via the outlet chamber a1 and the outlet connection A at a temperature of approx. 290 ° C. fed back to the reactor pressure vessel.
  • the tube bundle from the heat-exchanging tubes 2 is held in a vibration-proof manner by means of tube holding grids 6 spaced axially from one another; it is surrounded by a hollow cylindrical jacket 7 which, together with the wall 1, forms an annular fall space 8. Since the jacket 7 is arranged at a distance a2 from the tube sheet 3, the drop chamber 8 has a flow connection at its lower end via the flow passages 8.1 with the evaporation chamber inside the jacket 7. The jacket 7 is closed at its upper end by an attachment 9, which carries on its top a battery of water separators 10, into which the water-steam mixture from the evaporation chamber II enters through appropriate flow channels. The ejected water, the water level of the circulating water is indicated at 11, is fed directly to the drop room 8.
  • the ring line 12 which is arranged at the upper end of the drop space, is used via openings (not shown) for introducing the feed water from a feed water line connection piece 13 via a substantially perpendicular connecting pipeline 14.
  • the largely dewatered steam emerging from the water separators 10 on the upper side then passes still in fine separator 15 and from these via the live steam line connector 16 of the steam dome 17 to the steam turbines, not shown.
  • the DE works according to the natural circulation principle.
  • the feed water and the separated water flow mixed in the fall chamber 8 down into the evaporation chamber II and rise in this under evaporation (wet steam).
  • the water-steam mixture then passes into the coarse separator 10 and then into the fine separator 15, as already explained.
  • a very specific flow guide is provided, which is explained in more detail with reference to FIGS. 2 and 3.
  • the feed water is introduced into the water-steam space of the DE via an essentially horizontally running line part 140 and a subsequent rising line part 141, which is designed as a pipe bend, up to overflow edges Ü at the end of the flow path of the rising line part 141. From there the feed water, see flow arrows f1, via a downward line piece 142 and the feed ring line 12 connected thereto (FIG. 1) to the water-steam space, i. H. in this case, the drop room 8 of the DE, mixed.
  • the line part 142 is dome-shaped and comprises the line part 141 as a kind of bell.
  • the line part 140 can be held in the connection piece 13 (FIG. 1) in the manner of a thermosleeve pipe.
  • the rising line part is formed by a trough 141 'with a rectangular cross section, which is flat and box-shaped, that is to say forms a water box, on the two narrow side upper edges of which the overflow edges U are arranged.
  • This water box 141 ' is surrounded by a likewise box-shaped structure 142, rounded at its upper edge, for the downward line piece, which can also be curved in accordance with the inner circumferential curvature of the pressure vessel, and opens into the ring line 12 at its lower end via a narrowed neck piece 143 .
  • thermosleeve pipe can be of a conventional design or configured in accordance with FIG. 2 of DE-A-2 346 411.
  • Fig. 8 it is also shown that an essentially horizontally extending line part 140 can be followed by a substantially downwardly extending line part 145, which opens into a collecting cup 141 ", which opens the ascending flow paths up to the overflow edges Ü has.
  • a n / D i is maintained.
  • An means the horizontal distance of the pressure vessel inner wall 1i from the center line M ü running through the center of gravity of the cross-sectional area F ü spanned by the overflow edges Ü. D; means the inside diameter of the feed water line 140 opening into the pressure vessel DE.
  • the stated ratio A n / D; should be as small as possible and is within the limits between 0.5 and 2.
  • the embodiment according to FIG. 8 shows in connection with FIG. 9 that the ratio A n / D i is in the range of the upper limit value of 2.
  • An advantage of this example is the relatively high flow cross-section and the cylindrical symmetrical shape, the latter of which is also given in the exemplary embodiment according to FIGS. 2 and 3.
  • cylindrical symmetrical forms allow a higher pressure load; box-shaped cross sections, on the other hand, are lower in the compressive strength for a given wall thickness, but the extension in the direction An is lower. 1 to 3, where a relatively low ratio A n / D i of 1.27 is achieved and a relatively high compressive strength with a sufficient flow cross-section are given.
  • the other exemplary embodiments can be regarded as special designs in which either the ratio A n / D i is kept particularly low (FIGS. 4 to 7) or the flow cross section in the overflow area is particularly large (FIG. 8).
  • the table according to FIG. 9 is based on the cm values for A n and D i , as can be seen from the approximately true-to-scale drawing.
  • the pressure vessel of the steam generator DE according to FIG. 1 has an outer diameter of approximately 4800 mm in its separator area 1.4 (steam dome), so that it can be used for enlargement 2 and 3 entered sizes A, and D i give values of about 500 mm and 400 mm, respectively.
  • the steam generator shown in Fig. 1 serves z. B. together with three other steam generators in a 4-loop arrangement to generate the working steam in a 1200 MW el pressurized water nuclear power plant.

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Thermal Sciences (AREA)
  • Mechanical Engineering (AREA)
  • General Engineering & Computer Science (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
EP81105706A 1980-07-21 1981-07-20 Einrichtung zur Vermeidung von Rissbildungen an den Innenflächen von in Druckbehälter mündenden Speisewasserleitungsstutzen Expired EP0045034B1 (de)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE3027630 1980-07-21
DE3027630 1980-07-21

Publications (2)

Publication Number Publication Date
EP0045034A1 EP0045034A1 (de) 1982-02-03
EP0045034B1 true EP0045034B1 (de) 1983-04-13

Family

ID=6107750

Family Applications (1)

Application Number Title Priority Date Filing Date
EP81105706A Expired EP0045034B1 (de) 1980-07-21 1981-07-20 Einrichtung zur Vermeidung von Rissbildungen an den Innenflächen von in Druckbehälter mündenden Speisewasserleitungsstutzen

Country Status (5)

Country Link
US (1) US4462340A (es)
EP (1) EP0045034B1 (es)
JP (1) JPH0147681B2 (es)
ES (1) ES8704251A1 (es)
WO (1) WO1982000330A1 (es)

Families Citing this family (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4579088A (en) * 1984-04-09 1986-04-01 Westinghouse Electric Corp. Open channel steam generator feedwater system
ES2001332A6 (es) * 1985-07-02 1988-05-16 Framatome Sa Generador de vapor
FR2617570B1 (fr) * 1987-06-30 1989-12-01 Framatome Sa Dispositif anti-stratification thermique pour tuyau d'alimentation de generateur de vapeur
US5698390A (en) * 1987-11-18 1997-12-16 Chiron Corporation Hepatitis C immunoassays
CZ288U1 (cs) * 1992-04-03 1993-04-28 Vítkovice, A.S. Napájecí soustava tepelného výměníku, zejména parogenerátoru
FR2700383B1 (fr) * 1993-01-11 1995-02-10 Framatome Sa Echangeur de chaleur dans lequel l'alimentation en fluide secondaire s'effectue en partie haute par un boîtier d'alimentation ouvert vers le bas.
JP2013160695A (ja) * 2012-02-07 2013-08-19 Mitsubishi Heavy Ind Ltd 蒸気発生器用給水管

Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3661123A (en) * 1970-12-31 1972-05-09 Combustion Eng Steam generator feedwater preheater

Family Cites Families (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2210273A5 (es) * 1972-12-06 1974-07-05 Gutehoffnungshuette Sterkrade
DE2346411A1 (de) * 1973-09-14 1975-04-03 Kraftwerk Union Ag Dampferzeuger
US3991720A (en) * 1975-01-29 1976-11-16 Westinghouse Electric Corporation J tube discharge or feedwater header
FR2425611A1 (fr) * 1978-05-12 1979-12-07 Commissariat Energie Atomique Generateur de vapeur surchauffee

Patent Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3661123A (en) * 1970-12-31 1972-05-09 Combustion Eng Steam generator feedwater preheater

Also Published As

Publication number Publication date
WO1982000330A1 (en) 1982-02-04
US4462340A (en) 1984-07-31
ES504105A0 (es) 1987-03-16
EP0045034A1 (de) 1982-02-03
JPH0147681B2 (es) 1989-10-16
JPS57501143A (es) 1982-07-01
ES8704251A1 (es) 1987-03-16

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