EP0089869B1 - Dispositif de production de vapeur par échange de chaleur entre un métal liquide caloporteur et de l'eau alimentaire comportant plusieurs interfaces métal liquide-gaz neutre - Google Patents

Dispositif de production de vapeur par échange de chaleur entre un métal liquide caloporteur et de l'eau alimentaire comportant plusieurs interfaces métal liquide-gaz neutre Download PDF

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Publication number
EP0089869B1
EP0089869B1 EP83400494A EP83400494A EP0089869B1 EP 0089869 B1 EP0089869 B1 EP 0089869B1 EP 83400494 A EP83400494 A EP 83400494A EP 83400494 A EP83400494 A EP 83400494A EP 0089869 B1 EP0089869 B1 EP 0089869B1
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EP
European Patent Office
Prior art keywords
compartments
compartment
tubes
casing
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.)
Expired
Application number
EP83400494A
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German (de)
English (en)
French (fr)
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EP0089869A1 (fr
Inventor
Georges Jullien
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.)
Novatome SA
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Novatome SA
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Filing date
Publication date
Application filed by Novatome SA filed Critical Novatome SA
Publication of EP0089869A1 publication Critical patent/EP0089869A1/fr
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Publication of EP0089869B1 publication Critical patent/EP0089869B1/fr
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
    • 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

Definitions

  • the invention relates to a device for producing steam by heat exchange between a heat-transfer liquid metal and drinking water comprising several liquid metal-neutral gas interfaces.
  • the fast neutron nuclear reactors cooled by a liquid metal constituting the primary fluid of the reactor most often include intermediate heat exchangers in which the heating of a liquid metal constituting the intermediate fluid is produced which is itself used for the spraying of drinking water into steam generators.
  • These steam generators comprise a cylindrical envelope with a vertical axis closed by domed bottoms inside which the tubular bundle is arranged.
  • This bundle generally constituted by tubes wound in a helix, occupies only part of the cross section of the internal volume of the envelope and extends only over a part of the height of the envelope.
  • the secondary liquid sodium circulates, between its entry and exit from the envelope of the steam generator, in contact with the external surface of the tubes of the tube bundle inside which circulates food water which is vaporized by heat exchange with secondary liquid sodium.
  • One end of the bundle tubes is connected to a water supply device while the other end of the bundle tubes is connected to a vapor collecting device.
  • the central part of the internal volume of the envelope is occupied by a central cylindrical body coaxial with the envelope of the steam generator, from the lower part of the steam generator to 'to the upper zone into which the secondary liquid sodium arrives.
  • the tubular bundle occupies the peripheral part of the internal volume of the envelope, around the central body, over the entire height thereof, with the exception of its lower part in which openings allow the recovery of the secondary liquid sodium after its beam crossing.
  • the supply of secondary sodium and the circulation thereof in the steam generator are adjusted so that the upper level of this secondary sodium in the envelope of the generator is a little above the sodium inlet, at the top of the envelope.
  • the space between the upper sodium level and the upper bottom of the steam generator is filled with a neutral gas such as argon.
  • a sodium-water steam generator comprising a hollow cylindrical envelope disposed at the central part of the bundle, closed at its upper part and communicating at its lower part, by openings, with the internal volume of the steam generator in which the liquid sodium circulates.
  • This cylindrical envelope is supplied with pressurized neutral gas and placed in communication with the upper part of the steam generator containing neutral gas overcoming the liquid sodium, by a vertical tube whose lower end is situated at a sufficiently low level in the cylindrical shell, so that a neutral sodium-gas interface is created in the vicinity of the lower part of the central cylindrical shell.
  • Such an interface makes it possible to better absorb the pressure waves that may appear in the event of water leaking into the tube bundle. However, there is no guarantee that the pressure waves would very quickly find a sodium-gas interface in their path inside the steam generator.
  • At least two compartments are provided inside the envelope in an area not occupied by the tube bundle, placed one above the other, delimited by walls providing a passage for the molten metal between the compartment and the internal volume of the envelope, at the bottom of each compartment and placed in communication with one the other by a substantially vertical tube opening at a certain height in each of the two successive compartments, the highest located compartment being placed in communication by a substantially vertical tube opening at a certain height in this compartment with the upper part of the envelope filled with neutral gas and the lower compartment with a reserve of pressurized neutral gas for the introduction into the compartments, of neutral gas creating a liquid metal-neutral gas interface in each of them, each of the compartments, with the exception of the lower compartment, containing one end of two substantially vertical tubes putting it in communication with the compartment just above or with the upper part of the envelope and with the compartment situated just below respectively, so that the lower end of the communication tube with the compartment situated above is at a level lower than the upper end of the tube for communication with the compartment below.
  • the steam generator comprises a cylindrical envelope 1 of great length with respect to its diameter arranged with its vertical axis.
  • This envelope 1 is closed by two curved bottoms 2 and 3 at its upper end and at its lower end, respectively.
  • a hollow cylindrical central body 4 is fixed coaxially to the envelope 1.
  • This central body 4 is open at its lower part and passes through the lower curved bottom 3 of the steam generator. Openings 6 are made in the lower part of the central body to make the internal part of the latter communicate with the peripheral part of the steam generator arranged around the central body 4.
  • peripheral part is arranged the tubular bundle 8, and wound in a helix in the annular space existing between the central body 4 and the casing 1 of the steam generator.
  • the tubes are connected to a distributor 12 making it possible to send the drinking water into each of the tubes of the bundle and at their other end these tubes are connected to a vapor collector 13 making it possible to recover the vapor produced in the tubes brought into contact by their external surface with hot liquid sodium.
  • the liquid sodium is introduced through pipes 14 into the casing 1 at a distributor 15 which allows a homogeneous distribution of the hot sodium introduced through the pipes 14 throughout the section of the bundle 8.
  • the sodium introduced into the lines 14 comes from the intermediate exchangers of a fast neutron nuclear reactor cooled by primary liquid sodium itself serving to heat the secondary liquid sodium in the intermediate exchangers, this heated secondary sodium being sent to the generator. steam.
  • the hot secondary sodium descends along the bundle 8 inside the steam generator, produces the evaporation of the drinking water inside the bundle tubes, then is evacuated inside the central body 4 by the openings 6, at the base of the beam and out of the device through the bottom bottom.
  • the space between level 17 and the upper bottom 2 is filled with neutral gas, for example argon.
  • the central body 4 is divided over part of its height, at the level of the beam 8, into a certain number of superimposed compartments 18, by means of horizontal partition walls 19.
  • the side wall of the cylindrical central body 4 is pierced with openings 20 bringing the interior space of the central body 4 into communication with the peripheral zone of the envelope containing the bundle 8.
  • Each of the vertical tubes such as 21 and 23 has at its lower part a closing member comprising a calibrated orifice such as 24 or 26 to increase and adjust the pressure drop in the vertical tube.
  • the compartment 18e disposed at the upper part of the central body 4 is placed in communication with the compartment 18d located immediately below as well as with the space between the level 17 and the upper bottom 2 filled with argon via a very long vertical tube 27.
  • annular compartments 28 open at their lower part, and communicating with each other by means of a vertical tube 29 provided with a pressure drop device 30.
  • the upper annular compartment 28b is connected by a very long tube 31 to the space of the central body 4 disposed immediately below the compartment 18b and constituting the compartment 18a placed lowest inside the central body 4.
  • the annular lower compartment 28a is connected to a reserve of argon under low pressure by means of a pipe 32.
  • an argon and sodium evacuation tube 33 connected at its lower part to a low pressure sodium capacity by a very long pipe 34 and to its upper part to the argon atmosphere covering the capacity of sodium at low pressure by means of a very long pipe 36.
  • the tube 33 has, in its wall, calibrated orifices 37 at a level below the level of the bottom of the tubes 21.
  • the tube 33 allows the evacuation of argon or sodium during the operation of the steam generator.
  • Argon is then sent inside the lower annular compartment 28a via the pipe 32.
  • the sodium level in the annular compartment is established at the lower part of the tube 29 comprising the calibrated orifice 30.
  • the additional argon sent to the compartment 28a then passes into the upper compartment 28b where the sodium level s' lowers to settle at the bottom of the tube 31.
  • the argon then passes into compartment 18a where the sodium level drops to the lower level of the tube 25.
  • the argon sent into the steam generator via line 32 thus makes it possible to establish, step by step, the liquid sodium-argon interfaces in each of the compartments 18 up to compartment 18e situated at the top of the central body 4.
  • the steam generator can then be put into operation, the pumps of the secondary sodium circuit produce a circulation of sodium inside the steam generator, the upper level of sodium 17 remains above the inlet pipes 14 by a regulation of argon cover.
  • the sodium undergoes a pressure drop which results in a pressure difference between the lower parts of each of the compartments arranged one above the other.
  • the variations in sodium flow in the steam generator and the variations in the temperature of this sodium result in variations in the pressure difference between the lower parts of the different compartments, since the openings 20 put these lower parts of the compartments in communication with the peripheral zone of the steam generator where the secondary sodium circulates in contact with the beam.
  • These tubes are arranged so that the upper end of the tube placing any compartment in communication with the lower compartment, or at an upper level of the lower end of the tube placing this compartment in communication with the compartment arranged above.
  • the upper end of the tube 21 is at a level higher than the lower end of the tube 23 comprising the calibrated orifice 26.
  • the sodium-argon interface in each of the compartments arranged along the height of the steam generator is likely to vary between two limits.
  • the pressure waves are therefore damped very quickly after their appearance, which avoids the possibility of destruction of the steam generator.
  • the argon is evacuated towards the capacity constituted by the cover of low pressure argon of sodium capacity, for example, low pressure capacity of the main circuit of the nuclear reactor.
  • the sodium level in the evacuation device 33 is maintained by placing the lower part of the tube 33 in communication, via a pipe 34, with a capacity of sodium at low pressure, for example the circuit pump. secondary or the storage tank for this secondary sodium.
  • the argon evacuation tube is not essential for ensuring in all if there is a suitable flow of argon between the compartments.
  • the argon evacuation tube 33 can be suppressed when it is assumed that a small amount of gas can be discharged to the bundle 8.
  • compartments 42a, 42b, 42c and 42d Inside the envelope 40 of the steam generator containing liquid sodium up to level 41 and containing the bundle, are arranged, one above the other, compartments 42a, 42b, 42c and 42d. Each of the compartments 42 has openings in its side wall, at the lower part thereof, bringing the interior of the compartment into communication with the internal volume of the envelope 40, enclosing the bundle immersed in the circulating liquid sodium.
  • the compartments 42 are placed in communication with each other by vertical tubes44 as described above.
  • the lower compartment 42a is connected by a pipe 45 to the upper part of the liquid sodium reserve 46 interposed on the secondary circuit (or to the upper part of a secondary pump).
  • the reservoir 46 contains argon at low pressure overcoming the liquid sodium.
  • On the pipe 45 are arranged a valve 47 and a flow limiter 48.
  • the pipe 45 allows the evacuation of argon towards the tank 46.
  • a pipe 50 bypass on the pipe 45, between the compartment 42a and the valve 47 is connected to a source of pressurized argon via a valve 52.
  • An overflow 54 discharging into a pipe 55 allows the collection of sodium or argon from the higher capacity of the steam generator in the tank 46 (level regulation).
  • the evacuation of argon is carried out only by the pipe 45 connected to the lower compartment 42a.
  • the main advantages of the device according to the invention are to allow rapid damping of the pressure waves, after the appearance of these at any point in the steam generator area where the beam is located, to dampen these waves whatever their direction of propagation in the radial or axial directions of the steam generator and to avoid any entrainment of argon by the sodium circulating in the tube bundle.
  • the fact of arranging the compartments in which the sodium-argon interfaces are produced inside the central body and below the upper part of the bundle allows the best use of the dead spaces of the internal volume of the steam generator. .
  • the superimposed compartments can be arranged in other parts of the internal volume of the steam generator and that these compartments can have a shape different from a cylindrical or annular shape.
  • partition walls of these compartments can be flat or, on the contrary, have the form of surfaces of revolution, the meridian of which is, for example, a basket handle curve.
  • the annular compartments arranged at the base of the steam generator can be connected by welded radial ribs, both to the external surface of the central body and to the internal surface of the envelope of the steam generator.
  • the flow restriction devices increasing the pressure drop at the base of the communication tubes between the compartments can be produced in the form of simple calibrated orifices or more complex devices whose pressure drop is different depending on the direction of circulation of the fluid. inside the tube.
  • the invention applies in the case of a steam generator carrying out vaporization by heat exchange with any liquid metal and the neutral gas introduced into the superimposed compartments can be a rare gas such as argon or a simple gas inert such as nitrogen.
  • the device according to the invention applies not only in the case of steam generators of nuclear neutron reactors fast but also in the case of any steam generator using a liquid metal capable of reacting violently with drinking water.

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  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Sustainable Development (AREA)
  • Sustainable Energy (AREA)
  • Thermal Sciences (AREA)
  • Mechanical Engineering (AREA)
  • General Engineering & Computer Science (AREA)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
  • Organic Low-Molecular-Weight Compounds And Preparation Thereof (AREA)
  • Detergent Compositions (AREA)
EP83400494A 1982-03-11 1983-03-11 Dispositif de production de vapeur par échange de chaleur entre un métal liquide caloporteur et de l'eau alimentaire comportant plusieurs interfaces métal liquide-gaz neutre Expired EP0089869B1 (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
FR8204076 1982-03-11
FR8204076A FR2523268A1 (fr) 1982-03-11 1982-03-11 Dispositif de production de vapeur par echange de chaleur entre un metal liquide caloporteur et de l'eau alimentaire comportant plusieurs interfaces metal liquide-gaz neutre

Publications (2)

Publication Number Publication Date
EP0089869A1 EP0089869A1 (fr) 1983-09-28
EP0089869B1 true EP0089869B1 (fr) 1985-07-31

Family

ID=9271854

Family Applications (1)

Application Number Title Priority Date Filing Date
EP83400494A Expired EP0089869B1 (fr) 1982-03-11 1983-03-11 Dispositif de production de vapeur par échange de chaleur entre un métal liquide caloporteur et de l'eau alimentaire comportant plusieurs interfaces métal liquide-gaz neutre

Country Status (5)

Country Link
US (1) US4515109A (enrdf_load_stackoverflow)
EP (1) EP0089869B1 (enrdf_load_stackoverflow)
JP (1) JPS58175701A (enrdf_load_stackoverflow)
DE (1) DE3360456D1 (enrdf_load_stackoverflow)
FR (1) FR2523268A1 (enrdf_load_stackoverflow)

Families Citing this family (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2563895B1 (fr) * 1984-05-04 1986-10-31 Novatome Perfectionnement aux generateurs de vapeur a corps central du type sodium-eau
DE3539481A1 (de) * 1985-11-07 1987-05-21 Steinmueller Gmbh L & C Kohlegefeuerter dampferzeuger fuer kohle-kombiblock
US4983353A (en) * 1989-03-13 1991-01-08 General Electric Company Novel passive approach to protecting the primary containment barrier formed by the intermediate heat exchanger from the effects of an uncontrolled sodium water reaction
RU2379583C1 (ru) * 2008-09-08 2010-01-20 Федеральное государственное унитарное предприятие "Государственный научный центр Российской Федерации-Физико-энергетический институт имени А.И. Лейпунского" Парогенератор натрий-вода-пар с потоками теплоносителя, физически разделенными двумя твердыми стенками (варианты)
PL222997B1 (pl) 2012-08-01 2016-09-30 Biopal Spółka Z Ograniczoną Odpowiedzialnością Korpus kotła  do upłynniania i nagrzewania upłynnionego metalu w układach grzewczych, szczególnie reaktorów chemicznych
CZ305830B6 (cs) * 2014-09-10 2016-03-30 ENERGOVĂťZKUM, spol. s.r.o. Zapojení parního generátoru v sodíkovém okruhu jaderného zařízení s rychlým reaktorem
CN115116638B (zh) * 2021-03-19 2023-10-20 中国核工业二三建设有限公司 一种钠钾合金冷却剂管道系统拆除及后处理方法

Family Cites Families (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR1511662A (fr) * 1966-12-23 1968-02-02 Commissariat Energie Atomique Réacteur nucléaire refroidi par un liquide
US3924675A (en) * 1973-05-03 1975-12-09 Us Energy Energy absorber for sodium-heated heat exchanger
US3930537A (en) * 1974-05-06 1976-01-06 The United States Of America As Represented By The United States Energy Research And Development Administration Heat exchanger
US4083707A (en) * 1976-04-12 1978-04-11 Bivins Jr Henry W Flow stabilizer for tube and shell vaporizer
FR2363772A1 (fr) * 1976-09-03 1978-03-31 Commissariat Energie Atomique Echangeur de chaleur, notamment generateur de vapeur chauffe au sodium liquide
US4296713A (en) * 1979-02-07 1981-10-27 General Atomic Company Vapor generator
FR2509841B1 (fr) * 1981-07-17 1986-07-18 Creusot Loire Perfectionnement aux generateurs de vapeur du type sodium-eau

Also Published As

Publication number Publication date
FR2523268A1 (fr) 1983-09-16
JPS58175701A (ja) 1983-10-15
FR2523268B1 (enrdf_load_stackoverflow) 1985-05-10
US4515109A (en) 1985-05-07
DE3360456D1 (en) 1985-09-05
EP0089869A1 (fr) 1983-09-28

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