EP0117191A1 - Dampferzeuger für einen flüssigmetallgekühlten nuklearen Reaktor - Google Patents

Dampferzeuger für einen flüssigmetallgekühlten nuklearen Reaktor Download PDF

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Publication number
EP0117191A1
EP0117191A1 EP84400260A EP84400260A EP0117191A1 EP 0117191 A1 EP0117191 A1 EP 0117191A1 EP 84400260 A EP84400260 A EP 84400260A EP 84400260 A EP84400260 A EP 84400260A EP 0117191 A1 EP0117191 A1 EP 0117191A1
Authority
EP
European Patent Office
Prior art keywords
steam generator
tubes
envelope
tube
double
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.)
Granted
Application number
EP84400260A
Other languages
English (en)
French (fr)
Other versions
EP0117191B1 (de
Inventor
Michel Soucille
Laurent Castelnau
René Marcel Traiteur
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.)
Framatome Te Courbevoie Frankrijk
Original Assignee
Novatome SA
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 Novatome SA filed Critical Novatome SA
Publication of EP0117191A1 publication Critical patent/EP0117191A1/de
Application granted granted Critical
Publication of EP0117191B1 publication Critical patent/EP0117191B1/de
Expired legal-status Critical Current

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    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F28—HEAT EXCHANGE IN GENERAL
    • F28F—DETAILS OF HEAT-EXCHANGE AND HEAT-TRANSFER APPARATUS, OF GENERAL APPLICATION
    • F28F1/00—Tubular elements; Assemblies of tubular elements
    • F28F1/003—Multiple wall conduits, e.g. for leak detection
    • 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
    • F22B1/06—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being molten; Use of molten metal, e.g. zinc, as heat transfer medium
    • F22B1/063—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being molten; Use of molten metal, e.g. zinc, as heat transfer medium for metal cooled nuclear reactors
    • F22B1/066—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being molten; Use of molten metal, e.g. zinc, as heat transfer medium for metal cooled nuclear reactors with double-wall tubes having a third fluid between these walls, e.g. helium for leak detection
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F28—HEAT EXCHANGE IN GENERAL
    • F28D—HEAT-EXCHANGE APPARATUS, NOT PROVIDED FOR IN ANOTHER SUBCLASS, IN WHICH THE HEAT-EXCHANGE MEDIA DO NOT COME INTO DIRECT CONTACT
    • F28D7/00—Heat-exchange apparatus having stationary tubular conduit assemblies for both heat-exchange media, the media being in contact with different sides of a conduit wall
    • F28D7/10—Heat-exchange apparatus having stationary tubular conduit assemblies for both heat-exchange media, the media being in contact with different sides of a conduit wall the conduits being arranged one within the other, e.g. concentrically
    • F28D7/106—Heat-exchange apparatus having stationary tubular conduit assemblies for both heat-exchange media, the media being in contact with different sides of a conduit wall the conduits being arranged one within the other, e.g. concentrically consisting of two coaxial conduits or modules of two coaxial conduits
    • 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
    • F28F9/26—Arrangements for connecting different sections of heat-exchange elements, e.g. of radiators
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F28—HEAT EXCHANGE IN GENERAL
    • F28D—HEAT-EXCHANGE APPARATUS, NOT PROVIDED FOR IN ANOTHER SUBCLASS, IN WHICH THE HEAT-EXCHANGE MEDIA DO NOT COME INTO DIRECT CONTACT
    • F28D21/00—Heat-exchange apparatus not covered by any of the groups F28D1/00 - F28D20/00
    • F28D2021/0019—Other heat exchangers for particular applications; Heat exchange systems not otherwise provided for
    • F28D2021/0054—Other heat exchangers for particular applications; Heat exchange systems not otherwise provided for for nuclear applications

Definitions

  • the invention relates to a steam generator for a nuclear reactor cooled by liquid metal, such as a fast neutron nuclear reactor cooled by sodium.
  • Such a reactor comprises a tank containing the core of the reactor constituted by fuel assemblies immersed in liquid sodium filling the tank called primary sodium.
  • the heat taken from the reactor core by the primary sodium which comes into direct contact with the fuel assemblies is used to vaporize drinking water, the vapor then being sent to the turbine of the nuclear power plant.
  • the heat transfer between this sodium and the drinking water can be done using an intermediate exchange fluid which is often liquid sodium called secondary sodium.
  • the primary sodium coming into contact with the reactor core raises the temperature of the secondary sodium in sodium-sodium heat exchangers called intermediate exchangers.
  • the nuclear reactor therefore generally comprises a secondary circuit comprising at least one intermediate exchanger, a pump, a steam generator for the pipes and various control devices.
  • This secondary circuit is therefore complex and costly, whether it is partially integrated into the reactor vessel or whether it is entirely disposed outside of this vessel.
  • the intermediate circuit avoids direct heat exchange between the primary sodium contaminated by radioactive products and drinking water.
  • sodium and water can come into contact, which causes the appearance of a violent chemical reaction which can eventually lead to a leak in the sodium outwards.
  • the spaces between internal and external tubes constituting the double-walled tubes are placed in communication with a leakage control space making it possible to detect, for example by pressure measurement, a possible leak in the wall of one of the tubes, during the operation of the steam generator.
  • the steam generator consists of a bundle of tubes contained in an envelope, each of the internal tubes of the double-walled tubes being placed in communication at one of its ends with a water distribution system and at its other end with a vapor collection system.
  • the liquid sodium heated up in contact with the reactor core is brought into the envelope of the steam generator, at its upper part, and flows in this envelope from top to bottom in contact with the external tubes of the double-walled tubes constituting the beam.
  • annular chambers arranged outside the envelope of the steam generator, through which pass the portions of internal tubes allowing the connection of the double-walled tubes, by sealed crossings in the envelope of the steam generator.
  • Such a device is complex and requires particular manufacturing operations which are difficult to implement.
  • the object of the invention is therefore to provide a steam generator for a nuclear reactor cooled by liquid metal comprising a generally cylindrical envelope disposed with its vertical axis, enclosing a bundle of double-walled tubes each consisting of two coaxial tubes of which an internal tube communicating at one of its ends with a water distribution device or collector and at its other end with a vapor collector and an external tube in contact by its external wall with the liquid metal circulating from bottom to up in the casing of the steam generator, said steam generator having no pla - a double tubular connecting chamber or tubes outside of the shell and enabling a highly sensitive and reliable detection of leaks of double-walled tubes, while being of a design allowing a simplified and relatively inexpensive construction.
  • FIG. 1 we see the envelope of a steam generator 1 constituted by a cylindrical bundle envelope over the greatest height of the steam generator and by two enlarged zones, also of cylindrical shape, 2 and 3 each. of the ends of the beam.
  • the envelope 1 also comprises an enlarged central zone 4 of toroidal shape.
  • the upper enlarged zone 3 communicates with the sodium inlet 5 in the steam generator and the lower enlarged zone 2 communicates with the sodium outlet 6. Between these two ends, the sodium circulates from top to bottom in contact with the tubes of the bundle 10 arranged inside the bundle envelope la-over the entire height of the envelope of the steam generator.
  • the casing 1 is connected to a tubular plate 11 secured to a water collector 12 supplied with water by a pipe 13.
  • the casing 1 is connected to a tubular plate 14 secured to a vapor collector 15 comprising an outlet pipe 16.
  • the water collectors 12 and the steam collectors 15 are hemispherical in shape.
  • the tubular plates 11 and 14 are crossed by the tubes of the bundle 10 inside which circulates the food water supplied by the tubing 13 of the water collector 12, this food water gradually vaporizes during its circulation from bottom to high inside the bundle tubes in thermal contact with the hot sodium arriving in the steam generator via the sodium inlet pipe 5.
  • the very high beam consists of substantially straight and parallel tubes, the spacing of which is maintained by spacer plates such as 18 and 19. At each of the ends of the beam inside the enlarged zones 2 and 3 are arranged heat shields 21 and 22 respectively protecting the tubular plates against the heat flow from the sodium.
  • a leak detection chamber 25 At the central part of the bundle 10 is disposed a leak detection chamber 25, the structure of which will be described in more detail with reference to FIG. 2.
  • the internal volume of this collecting and leak detection chamber is connected by a tube 26 passing through the casing 1 at the level of the toric widening 4 to a pressure measuring device.
  • the tubes 20 of the bundle are double-walled and constituted by two successive sections 20a and 20b connected at the level of the leakage collecting chamber 25.
  • the upper section 20a of the tube 20 is itself constituted by an external tube 27a and an internal tube 28a coaxial and threaded one on the other with very little play, without metallurgical connection between the internal surface of the tube 27a and the external surface of the tube 28g.
  • a space of very small width therefore exists between the tubes over the entire length of the section 20 a.
  • the internal surface of the tube 27a is also machined to form therein longitudinal grooves allowing the pressurization of the space between the two tubes.
  • the lower section 20b of the tube 20 is also constituted by an outer tube 27 b and an inner tube 28 b identical to the tubes 27a and 28a respectively.
  • the upper section 20a of the tube crosses the tubular plate 14 at its upper part so that the inner tube 28a opens into the vapor collector 15.
  • a weld 29 inside the collector 15, on the outlet face of the tubular plate 14, allows to close her metric the space between the tubes 27a and 28a.
  • the lower section 20 b of the tube crosses at its lower part the tubular plate 11, so that the inner tube 28 b opens into the water collector 12.
  • a weld 30 on the entry face of the tubular plate 11 makes it possible to hermetically seal the leakage space between the tubes 28b and 27b .
  • the outer tubes 20a and 20b are also fixed by welds on the other faces of the tubular plates 11 and 14.
  • the collecting chamber leak 25 is constituted by two circular plates 25a and 25b having a ring edge following which they are connected by a weld 32.
  • Each of the half-walls 25a and 25 b comprises a large number of pipe penetrations such as 34a and 34 b for the passage sections 20a and 20b of the tube 20 respectively.
  • the two sections 28a and 28b of the inner tube are connected via a solder 35.
  • the two sections of the outer tube 27a and 27 b are not connected and simply open into the internal volume of the leakage collector box 25, on either side of the connection weld 35 between the two sections of the internal tube 28.
  • the leakage collecting chamber 25 is disposed entirely inside the casing 1 - of the steam generator, at the level of the toric enlargement 4. This collecting chamber 25 is not fixed inside the generator. steam only by the double-walled tubes 20 on which it is welded.
  • the internal volume of the chamber 25 and all of the spaces between the two walls of the tubes 20 are filled with helium at a pressure intermediate between the pressure of the sodium circulating in the steam generator in contact with the external wall of the tubes 20 and the water or steam circulating inside the tubes 28.
  • FIGS. 3 and 4 an alternative embodiment of the water or vapor collector 15 shown in FIG. 1 is shown.
  • This vapor collector consists of a tubular plate 44, the internal face of which has a concave spherical shape and an envelope in the form of a portion of a sphere 45 which is connected by a weld 46 to the tubular plate 44.
  • the spherical casing 45 is connected to a steam outlet pipe 47.
  • the tubular plate 44 is connected to the enlarged zone 43 of the generator casing corresponding to the enlarged part 2 or 3 shown in the figure 1.
  • FIG. 4 it can be seen that the outer tube 27 of a double-walled tube 20 is welded to the sodium side face 48 and inside the passage hole 49 passing through the tubular plate 44, while the inner tube 28 is welded to the inside of the outer tube 27, which secures it and closes the leakage space between the two tubes 27 and 28.
  • FIGS. 5 and 6 a second alternative embodiment of the water or steam collectors is seen, the collector being constituted, in this alternative, by a very thick spherical envelope 50 completely separated from the envelope 1 of the generator. steam.
  • the envelope 1 is welded at its upper or lower part to a tubular plate 52 allowing the passage through the double-walled tubes 20 for their passage outside the steam generator.
  • the main advantages of the device according to the invention are to allow leakage detection of double-walled tubes by means of a simple device, distinct and distant from the tube plates of the water and steam collectors of the steam generator. There is therefore no presence of a significant weld concentration in the region of the tubular plates.
  • the leak detection chambers allow the connection of successive sections of the tube bundle, inside the envelope of the steam generator but in an area isolated from liquid sodium.
  • the overall structure of the steam generator is extremely simple since it only has straight tubes formed by successive sections whose connection is made inside the leak detection chamber.
  • This leak detection chamber is moreover practically part of the beam structure and has no connection with the envelope of the steam generator.
  • the bundle can be made up of more than two successive sections.
  • the tubes of the central section will be connected at each of their ends to a leakage collecting chamber.
  • n - 1 leakage collecting chambers arranged inside the envelope of the steam generator will be used.
  • Each of these leakage collecting chambers will be associated with a manometric device allowing the monitoring of the corresponding tube sections. It will thus be possible to have redundant data for certain sections connected to two successive chambers by each of their ends.
  • the steel grades chosen for the constitution of the tubes may be different.
  • the shape and arrangement of the leakage collecting chambers may be different from what has been described.
  • an enlarged toric part of the envelope is provided to allow the circulation of sodium around the leakage collecting chamber.
  • the circulation of sodium at the level of the upper face of this leakage collecting chamber becomes radial, which is favorable since the sweeping of the upper face of the leakage detection chamber avoids any deposit of impurities.
  • the enlarged toric portion 4 of the envelope allows longitudinal deformations of the latter making it possible to absorb differential thermal expansions. This is particularly important in the case of very high structures necessary for the constitution of generators of high power.
  • leakage collecting chamber or chambers and the envelope may have different shapes from those which have been described.
  • the water and steam collectors can have a shape not only spherical but also toric or cylindrical, when they are completely independent of the envelope (1) of the steam generator and arranged as shown in FIG. 5.
  • the steam generator according to the invention can be associated with all fast neutron nuclear reactors cooled by a liquid metal whether they are of the semi-integrated or loop type.

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  • 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)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Physical Or Chemical Processes And Apparatus (AREA)
EP84400260A 1983-02-10 1984-02-08 Dampferzeuger für einen flüssigmetallgekühlten nuklearen Reaktor Expired EP0117191B1 (de)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
FR8302108 1983-02-10
FR8302108A FR2540971B1 (fr) 1983-02-10 1983-02-10 Generateur de vapeur pour un reacteur nucleaire refroidi par du metal liquide

Publications (2)

Publication Number Publication Date
EP0117191A1 true EP0117191A1 (de) 1984-08-29
EP0117191B1 EP0117191B1 (de) 1986-10-29

Family

ID=9285784

Family Applications (1)

Application Number Title Priority Date Filing Date
EP84400260A Expired EP0117191B1 (de) 1983-02-10 1984-02-08 Dampferzeuger für einen flüssigmetallgekühlten nuklearen Reaktor

Country Status (5)

Country Link
US (1) US4612976A (de)
EP (1) EP0117191B1 (de)
JP (1) JPS59157401A (de)
DE (1) DE3461117D1 (de)
FR (1) FR2540971B1 (de)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN114728337A (zh) * 2019-11-22 2022-07-08 法国电力公司 固体金属部件和用于生产固体金属部件的方法

Families Citing this family (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH063288B2 (ja) * 1984-05-23 1994-01-12 財団法人電力中央研究所 二重管型蒸気発生器
US5048597A (en) * 1989-12-18 1991-09-17 Rockwell International Corporation Leak-safe hydrogen/air heat exchanger in an ACE system
US20050150640A1 (en) * 2004-01-09 2005-07-14 Ranga Nadig Double-tube apparatus for use in a heat exchanger and method of using the same
JP5320010B2 (ja) * 2008-10-07 2013-10-23 三菱重工業株式会社 管寄せ管台の溶接構造
PT2322854E (pt) * 2009-11-17 2013-09-12 Balcke Duerr Gmbh Permutador térmico para a produção de vapor para centrais de energia solar
US9170193B2 (en) 2013-06-06 2015-10-27 General Electric Company Detecting coolant leaks in turbine generators
US9097657B2 (en) 2013-07-23 2015-08-04 General Electric Company Leak detection of stator liquid cooling system

Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2658728A (en) * 1948-06-25 1953-11-10 Lummus Co Method of detecting leakage between heat transfer fluids
GB894883A (en) * 1960-01-08 1962-04-26 Babcock & Wilcox Ltd An improved method of manufacturing heat exchanger tubes and improvements in or relating to heat exchanger tubes and to heat exchangers
FR2371655A1 (fr) * 1976-11-17 1978-06-16 Babcock & Wilcox Co Transfert de chaleur indirect entre fluides reactifs et detection de fuites provoquant un melange entre ces fluides
FR2379881A1 (fr) * 1977-02-04 1978-09-01 Commissariat Energie Atomique Bloc-pompe echangeur de chaleur pour reacteurs nucleaires
EP0013796A1 (de) * 1979-01-19 1980-08-06 Westinghouse Electric Corporation Wärmetauscher mit Doppelwandrohren zur Lecküberwachung

Family Cites Families (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3098023A (en) * 1958-09-15 1963-07-16 Babcock & Wilcox Co Nuclear reactor containment system
US4171014A (en) * 1972-11-28 1979-10-16 Sulzer Brothers Limited Arrangement for mounting tubes in a tank wall
US4237968A (en) * 1979-05-02 1980-12-09 Westinghouse Electric Corp. Heat exchanger with double wall tubes and three tube sheets
DE3027510C2 (de) * 1980-07-19 1987-04-09 Hochtemperatur-Reaktorbau GmbH, 4600 Dortmund Gewölbter Deckel zum Verschließen einer vertikalen Ausnehmung in einem Druckgefäß
US4368694A (en) * 1981-05-21 1983-01-18 Combustion Engineering, Inc. Leak detection system for a steam generator

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2658728A (en) * 1948-06-25 1953-11-10 Lummus Co Method of detecting leakage between heat transfer fluids
GB894883A (en) * 1960-01-08 1962-04-26 Babcock & Wilcox Ltd An improved method of manufacturing heat exchanger tubes and improvements in or relating to heat exchanger tubes and to heat exchangers
FR2371655A1 (fr) * 1976-11-17 1978-06-16 Babcock & Wilcox Co Transfert de chaleur indirect entre fluides reactifs et detection de fuites provoquant un melange entre ces fluides
FR2379881A1 (fr) * 1977-02-04 1978-09-01 Commissariat Energie Atomique Bloc-pompe echangeur de chaleur pour reacteurs nucleaires
EP0013796A1 (de) * 1979-01-19 1980-08-06 Westinghouse Electric Corporation Wärmetauscher mit Doppelwandrohren zur Lecküberwachung

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN114728337A (zh) * 2019-11-22 2022-07-08 法国电力公司 固体金属部件和用于生产固体金属部件的方法

Also Published As

Publication number Publication date
JPH0350161B2 (de) 1991-07-31
JPS59157401A (ja) 1984-09-06
DE3461117D1 (en) 1986-12-04
EP0117191B1 (de) 1986-10-29
FR2540971A1 (fr) 1984-08-17
US4612976A (en) 1986-09-23
FR2540971B1 (fr) 1985-09-27

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