EP0070775B1 - Wasser-Natrium Dampferzeuger - Google Patents

Wasser-Natrium Dampferzeuger Download PDF

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Publication number
EP0070775B1
EP0070775B1 EP82401331A EP82401331A EP0070775B1 EP 0070775 B1 EP0070775 B1 EP 0070775B1 EP 82401331 A EP82401331 A EP 82401331A EP 82401331 A EP82401331 A EP 82401331A EP 0070775 B1 EP0070775 B1 EP 0070775B1
Authority
EP
European Patent Office
Prior art keywords
sodium
steam generator
liquid sodium
reservoir
elongated 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
EP82401331A
Other languages
English (en)
French (fr)
Other versions
EP0070775A1 (de
Inventor
André Baudoin
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
Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
Original Assignee
Novatome SA
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 Novatome SA, Commissariat a lEnergie Atomique CEA filed Critical Novatome SA
Publication of EP0070775A1 publication Critical patent/EP0070775A1/de
Application granted granted Critical
Publication of EP0070775B1 publication Critical patent/EP0070775B1/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
    • 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
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F28—HEAT EXCHANGE IN GENERAL
    • F28F—DETAILS OF HEAT-EXCHANGE AND HEAT-TRANSFER APPARATUS, OF GENERAL APPLICATION
    • F28F2265/00—Safety or protection arrangements; Arrangements for preventing malfunction
    • F28F2265/12—Safety or protection arrangements; Arrangements for preventing malfunction for preventing overpressure

Definitions

  • the present invention relates to an improvement to sodium-water type steam generators used in particular in nuclear power plants.
  • a boiler In power plants, a boiler provides heat to the fluid in a closed loop circuit, this heated fluid then circulates in a steam generator in order to transfer its heat to water which is transformed into steam, this steam being then sent to the power station turbines.
  • liquid sodium as a fluid for transporting calories from the boiler to the steam generator.
  • the steam generator consists of a heat exchanger, the primary circuit of which contains liquid sodium and the secondary circuit of which contains water transformed into vapor.
  • a primary circuit containing liquid sodium includes a steam generator, the upper part of which encloses a gas pocket and also includes an expansion tank connected to the circuit by large-diameter piping, located at a certain distance of the steam generator, a mass oscillation phenomenon has been observed between the two gas pockets during accidental sodium-water reactions or during the simultaneous reactions which are carried out to test the installation.
  • a steam generator comprising an internal expansion tank constituted by a hollow internal cylinder provided with a non-return valve.
  • the present invention aims mainly to overcome the various drawbacks of known steam generators.
  • the reservoir permanently forms a total passage in the elongated enclosure. slightly free without any restriction in both directions favoring the propagation of an acoustic wave towards the free level of liquid-gas sodium where it is reflected with a significant loss of energy, in order to avoid in the whole of the steam generator the propagation of this acoustic wave resulting from a brutal accidental chemical reaction between sodium and water, a tube bringing in the upper part of the tank the inert gas and a tube extending vertically inside the tank, its end lower being located relatively low in said tank, so that the level of the free surface of the liquid sodium does not fall below the lowest point of the tube at the time of introduction of the neutral gas through the tube into the tank.
  • a secondary cooling circuit for nuclear power plants can be distinguished, the general diagram of which is entirely conventional.
  • a set of pipes 1, 2, 3 which transport liquid sodium in a closed circuit.
  • the liquid sodium circulates so as to take the calories in the intermediate exchanger 5 to give them to the steam generator 6 by causing, in this steam generator, the transformation of water into steam in the secondary circuit, this steam being used to conventional way to turn the power station turbines.
  • the liquid sodium After passing through the steam generator, the liquid sodium returns via line 3 to the circulation pump 4, before starting its cycle again.
  • the steam generator 6 is therefore a heat exchanger, the primary circuit of which contains liquid sodium and the secondary circuit of which contains water. If a rupture occurs in this steam generator causing a mixture of a certain quantity of sodium with water, it follows a violent chemical reaction which has the effects of an explosion inside the steam generator, and which causes a sudden rise in pressure in the sodium circuit. On a conventional installation, the pressure wave which results from this explosion can propagate through line 3 then through line 1, arrive in the intermediate exchanger 5 and cause it to break. To protect this intermediate exchanger 5 which constitutes a barrier between the radioactive liquid sodium passing through the reactor core and the uncontaminated liquid sodium passing through the steam generator, it has already been proposed to have a bypass on the pipe bringing the sodium to the intermediate exchanger 5 an expansion tank of large size.
  • the present invention aims to overcome these drawbacks by designing a steam generator 6 comprising certain new provisions which make it possible to avoid the connection of the expansion tank 7 to the circuit by means of a large diameter pipe 24 intended to limit the propagation of a pressure wave.
  • FIG. 2 The steam generator specific to our invention, making it possible to avoid such a connection, is shown in FIG. 2 in more detail.
  • This steam generator comprises a cylindrical enclosure 1 of elongated shape and arranged vertically, filled with circulating liquid sodium constituting the primary circuit. Liquid sodium arrives at the steam generator 6 through the pipes 2, is introduced into the inlet chamber 8 located at the top of the steam generator, flows from top to bottom inside the cylindrical enclosure 1, reaches to the outlet zone 9 located at the bottom of the steam generator from where it is discharged via the pipe 11.
  • the steam generator shown in this exemplary embodiment comprises a secondary circuit consisting of a multitude of tubes arranged helically 12 and in which circulates water introduced by the lower part 13 of the tubes and emerging from the upper part 14 of the tubes in the form of vapor.
  • the cylindrical casing 15 is arranged longitudinally in the center of the steam generator, vertically, is closed at its upper part 16 and has openings 17 at its lower part.
  • the interior of this envelope 15 is filled with a certain amount of an inert gas 18 which forms a pocket at the upper part of the envelope 15 and which defines a free surface 19 of the liquid sodium.
  • a tube 20 brings the necessary inert gas into the upper part of the envelope 15, and a tube 21 extends vertically inside the enclosure 15, its lower end being situated relatively low in the envelope 15, so that, when the inert gas is introduced into the chamber 18 through the tube 20, the level of the free surface 19 of the liquid sodium does not drop below the lowest point of the tube 21.
  • the resulting pressure wave is considerably damped, inside the steam generator, due to the elasticity of the pocket gas 18, thus preventing this pressure wave from propagating in significant proportions through the sodium outlet pipe 11, towards the other devices located in this circuit, that is to say mainly the circulation pumps and especially the intermediate exchangers.
  • the volume occupied by the cylindrical envelope 15 which sometimes exists in certain known steam generators is arranged according to the present invention so as to constitute an expansion tank inside the steam generator, produced economically since it is made up largely of elements that exist anyway, which takes no additional space, and which strictly limits the steam generator mechanical stress caused by an accidental sodium-water reaction therein.
  • the heat transfer circuit comprising a steam generator in accordance with the present invention, as shown in FIG. 1, can advantageously be supplemented by a deviation, close to the outlet of liquid sodium from the steam generator, this deviation being closed in regime normal by a rupture membrane intended to rupture when the liquid sodium pressure at the outlet of the steam generator exceeds a predetermined value, in order to put this outlet of the steam generator into communication with the storage tank 30.
  • this arrangement of rupture membrane and storage tank is known per se and plays here a role entirely identical to that which it plays in installations comprising a conventional steam generator. It can also be noted that it is known that such a rupture membrane 31 only partially attenuates the amplitude of the pressure wave during a possible sodium-water reaction in the steam generator.

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Thermal Sciences (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Sustainable Development (AREA)
  • Sustainable Energy (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Mechanical Engineering (AREA)
  • General Engineering & Computer Science (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)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Claims (1)

  1. Natrium-Wasser-Dampferzeuger, insbesondere für Kernkraftzentralen, mit
    - einem Primärkreis in Form eines mit flüssigem Natrium gefüllten, länglichen umschlossenen Raums (1),
    - einem Eintrittsbereich (8) des länglichen umschlossenen Raums, in den das flüssige Natrium eingeführt wird,
    - einem Austrittsbereich (9) des länglichen umschlossenen Raums (1), aus welchem das flüssige Natrium abgeführt wird,
    - einem teilweise mit einem inerten Gas gefüllten Behälter (15), welcher an seinem unteren Teil mit dem länglichen umschlossenen Raum (1) strömungsverbunden ist, um einen freien Spiegel (19) des flüssigen Natriums zu bilden, und
    - einem Sekundärkreis aus einer Anzahl von Wasser-Umlaufrohren (12), welche sich im Inneren des länglichen umschlossenen Raums erstrecken,

    dadurch gekennzeichnet, daß der Behälter (15) in dem länglichen umschlossenen Raum (1) ständig einen vollständig freien Durchlaß ohne jede Behinderung in beiden Richtungen bildet, welche die Fortpflanzung einer akustischen Welle zur freien Grenzfläche (19) zwischen dem Natrium und dem Gas begünstigt, an welcher sie mit einem erheblichen Energieverlust reflektiert wird, um die Fortpflanzung der akustischen Welle im gesamten Dampferzeuger und die dabei bestehende Gefahr einer plötzlichen chemischen Reaktion zwischen dem Natrium und dem Wasser zu vermeiden, wobei ein Rohr (20) das inerte Gas in das obere Teil des Behälters (15) leitet und ein Rohr (21) sich senkrecht im Inneren des Behälters (15) erstreckt, so daß sein unteres Ende relativ tief in den Behälter hineinreicht, zu dem Zweck, daß der freie Spiegel (19) desflüssigen Natriums bei der Zufuhr des inerten Gases durch das Rohr (20) in den Behälter (15) nicht bis unter den tiefsten Punkt des Rohrs (21) absinkt.
EP82401331A 1981-07-17 1982-07-16 Wasser-Natrium Dampferzeuger Expired EP0070775B1 (de)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
FR8113941 1981-07-17
FR8113941A FR2509841B1 (fr) 1981-07-17 1981-07-17 Perfectionnement aux generateurs de vapeur du type sodium-eau

Publications (2)

Publication Number Publication Date
EP0070775A1 EP0070775A1 (de) 1983-01-26
EP0070775B1 true EP0070775B1 (de) 1985-12-27

Family

ID=9260597

Family Applications (1)

Application Number Title Priority Date Filing Date
EP82401331A Expired EP0070775B1 (de) 1981-07-17 1982-07-16 Wasser-Natrium Dampferzeuger

Country Status (5)

Country Link
US (1) US4452182A (de)
EP (1) EP0070775B1 (de)
JP (1) JPS5845401A (de)
DE (1) DE3268118D1 (de)
FR (1) FR2509841B1 (de)

Families Citing this family (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2523268A1 (fr) * 1982-03-11 1983-09-16 Novatome 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
JPS58158498A (ja) * 1982-03-15 1983-09-20 Hitachi Ltd 熱交換器
FR2533355B1 (fr) * 1982-09-22 1988-07-08 Commissariat Energie Atomique Circuit caloporteur secondaire pour un reacteur nucleaire refroidi par un metal liquide et generateur de vapeur adapte a un tel circuit
FR2563895B1 (fr) * 1984-05-04 1986-10-31 Novatome Perfectionnement aux generateurs de vapeur a corps central du type sodium-eau
JPH07116014B2 (ja) * 1985-12-05 1995-12-13 三資堂製薬株式会社 毛髪処理用薬剤及び毛髪処理方法
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
JP4405787B2 (ja) 2003-11-12 2010-01-27 倉敷紡績株式会社 ポリアミド結合を有する有体物の着色方法および該方法で着色された有体物
DE102011005481A1 (de) * 2011-03-14 2012-09-20 Siemens Aktiengesellschaft Wärmetauscher

Family Cites Families (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3187807A (en) * 1961-05-03 1965-06-08 Babcock & Wilcox Co Heat exchanger
US3398789A (en) * 1965-01-25 1968-08-27 Foster Wheeler Corp Heat exchangers for pressure reacting fluids
US3812825A (en) * 1971-03-08 1974-05-28 Foster Wheeler Corp Sodium heated helical coil arrangement
US3888212A (en) * 1972-10-24 1975-06-10 Foster Wheeler Corp Liquid metal steam generator
US3924675A (en) * 1973-05-03 1975-12-09 Us Energy Energy absorber for sodium-heated heat exchanger
JPS5844921B2 (ja) * 1974-08-19 1983-10-06 株式会社日立製作所 ジヨウキハツセイキ
JPS6027492B2 (ja) * 1975-09-04 1985-06-29 斉藤 清徳 茸類の菌糸発育促進法
FR2363772A1 (fr) * 1976-09-03 1978-03-31 Commissariat Energie Atomique Echangeur de chaleur, notamment generateur de vapeur chauffe au sodium liquide
US4284134A (en) * 1978-09-05 1981-08-18 General Atomic Company Helically coiled tube heat exchanger

Also Published As

Publication number Publication date
DE3268118D1 (en) 1986-02-06
JPS5845401A (ja) 1983-03-16
US4452182A (en) 1984-06-05
EP0070775A1 (de) 1983-01-26
FR2509841B1 (fr) 1986-07-18
FR2509841A1 (fr) 1983-01-21

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