EP0011834B1 - Flüssigmetall-beheizter Dampferzeuger mit integrierter Zwischenüberhitzung - Google Patents

Flüssigmetall-beheizter Dampferzeuger mit integrierter Zwischenüberhitzung Download PDF

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Publication number
EP0011834B1
EP0011834B1 EP79104671A EP79104671A EP0011834B1 EP 0011834 B1 EP0011834 B1 EP 0011834B1 EP 79104671 A EP79104671 A EP 79104671A EP 79104671 A EP79104671 A EP 79104671A EP 0011834 B1 EP0011834 B1 EP 0011834B1
Authority
EP
European Patent Office
Prior art keywords
steam generator
pipe
tube
steam
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
EP79104671A
Other languages
German (de)
English (en)
French (fr)
Other versions
EP0011834A1 (de
Inventor
Walter Jansing
Kurt Dr. Vinzens
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.)
Interatom Internationale Atomreaktorbau GmbH
Original Assignee
Interatom Internationale Atomreaktorbau GmbH
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 Interatom Internationale Atomreaktorbau GmbH filed Critical Interatom Internationale Atomreaktorbau GmbH
Priority to AT79104671T priority Critical patent/ATE389T1/de
Publication of EP0011834A1 publication Critical patent/EP0011834A1/de
Application granted granted Critical
Publication of EP0011834B1 publication Critical patent/EP0011834B1/de
Expired legal-status Critical Current

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Classifications

    • 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
    • F28F9/0236—Header boxes; End plates floating elements
    • F28F9/0239—Header boxes; End plates floating elements floating header boxes
    • 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
    • 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
    • F28D7/02—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 helically coiled
    • F28D7/024—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 helically coiled the conduits of only one medium being helically coiled tubes, the coils having a cylindrical configuration
    • 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
    • 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 present invention relates to a steam generator according to the preamble of claim 1.
  • reheating In order to increase the overall efficiency of steam power plants, it is advisable to reheat the steam which has already relaxed and cooled in the high and medium pressure section of a steam turbine by so-called reheating.
  • liquid metal e.g. Sodium-cooled nuclear reactors, which have significantly higher requirements with regard to safety and reliability than conventionally heated steam power plants, have so far either avoided this intermediate overheating or have been installed in separate apparatuses which are connected in parallel with the superheaters on the side of the hot liquid metal.
  • Nuclear reactor plants which often have significantly higher outputs than conventionally heated plants, should not only generate electricity with high availability and high overall efficiency; in the event of a possible accident, the heat emitted by the nuclear reactor should be able to be dissipated without the nuclear reactor substantially exceeding the operating temperatures suitable for it. Therefore, efforts have so far been made to use different types of apparatus, e.g. Separate superheaters and intermediate superheaters so that they do not affect each other in the event of a malfunction and can be operated independently of one another.
  • this separate design leads to a considerable outlay for pipelines, insulation and safety devices, especially in the case of liquid metal-cooled nuclear power plants, quite apart from the additional space requirement, which is associated with high costs especially in the case of nuclear power plants.
  • DE-A 24 48 832 has already described a liquid metal / water heat exchanger as a steam generator for nuclear power plants.
  • the steam generator according to claim 2 brings two further advantages for operation and monitoring.
  • the proposed arrangement of several support structures between the individual tube bundles initially ensures that each individual support structure is significantly less stressed because it only has to carry part of the overall tube bundle.
  • the reliability of the overall construction is increased by the proposed double function of a supporting structure, namely, on the one hand, in the normal case, on the one hand, to hold the tube bundle underneath and, on the other hand, in the event of failure of an overlying supporting structure, also the overlying tube bundle.
  • the distributor construction proposed in claim 3 avoids inadmissible tensions on the one hand due to different expansion of the downpipe and central tube with the tube sheets, and on the other hand brings about a uniform flow against all spiral tubes distributed over the circumference of the container.
  • the eccentric arrangement of the single downpipe and the helical shape of the distributor pipes keep the center of the central pipe free for remote-controlled inspection and repair devices.
  • the arrangement according to claim 4 fulfills two conflicting requirements.
  • the sub-distributors and the space underneath should be accessible for remote-controlled inspection and repair devices;
  • the subdistributors which are evenly distributed over the circumference, should support one another in the event of one of them tearing off, so that no secondary damage to other components can occur.
  • the support structure according to the invention which is arranged at a short distance from the floors of the sub-distributors, is open at the top and bottom and is therefore freely accessible for devices. In addition, it can also be removed with a simple device upwards, if necessary also downwards.
  • the arrangement proposed in claim 5 is also intended to avoid major consequential damage after damage to the downpipe.
  • the proposed double pipe is intended to hold the lower end of this down pipe in case it starts to move due to recoil forces from its bottom or from a completely torn distribution pipe.
  • the collector proposed in claim 6 is intended to summarize numerous coiled tubes. Since these long spiral tubes have to be checked at regular intervals from the inside with long flexible probes, the spiral tubes should be accessible from above with a manipulator. So that such a manipulator can now reach all pipe ends from one point in the direction of the pipe axis, it is proposed according to the invention not to weld these pipe ends into a flat pipe plate as before, but into part of a spherical surface. In this way, all the pipe ends lying on a circular path can be reached simply by rotating the corresponding manipulator and reaching the respectively adjacent circular path of pipe ends by changing the angle between the manipulator axis and the collector axis.
  • the arrangement according to claim 7 proposes a construction that avoids inadmissible thermal stresses due to different expansion of the container and central tube, which nevertheless allows the central tube with the spiral tubes attached to it to be easily removed and which protects the lower end of the central tube against impermissible horizontal loads , for example in the event of an earthquake.
  • the embodiment according to claim 8 allows repair work by subjecting the helical tubes to a low pressure to remove the water completely from them and from the sub-distributors located at the lowest point.
  • the steam generator is arranged in a container 1, through which liquid secondary sodium flows, which is heated in a sodium / sodium intermediate heat exchanger (not shown here) by the primary sodium used as a coolant for a nuclear reactor and by a nozzle 2 and by a further nozzle 3 emerges.
  • a sodium / sodium intermediate heat exchanger (not shown here)
  • the primary sodium used as a coolant for a nuclear reactor and by a nozzle 2 and by a further nozzle 3 emerges.
  • a central tube 4 closed at the bottom, and between them a number of heat exchanger tubes combined into bundles 5, of which the lower ones are used in a known manner for steam generation and the upper ones for overheating and each occupying a sector of the intermediate space.
  • the feed water is fed through a downpipe 6, which is arranged inside the central tube 4 filled with air or an inert gas, thereby eliminating the risk of a reaction between water and sodium in the event of leaks in the downpipe is switched.
  • the downpipe 6 ends in a distributor 7, of which in the example four pipes 8 coiled to compensate for thermal expansion lead to sub-distributors 9 with an approximately hemispherical bottom and a tube plate 10, into which the individual steam generator tubes 11 are welded.
  • the recoil forces occurring when one of the pipes 8 is torn off from the distributor 7 are absorbed by a double pipe 12 surrounding the latter.
  • Blockable drain lines 30 lead from the sub-distributors 9 to an annular collecting line 31; Via a further line 32 guided in the central tube 4, all tube bundles 5 can be emptied of water.
  • the central tube 4 is slidably supported at its lower end in a centering 14 fastened to the container 1; it also has an inner tube 34 and an opening which is closed during operation by a rupture disk 15, through which the excess pressure which occurs in the steam generator during a sodium-water reaction is reduced and the reaction products can pass through the central tube 4 to a separating device (not shown) .
  • a connecting piece 35 also shown with a rupture disc
  • FIG. 1 shows a connecting piece 35 arranged if it is possible to blow off the reaction products into the inertized space around the steam generator.
  • the individual tube bundles 5 are separated from one another in height by short sections 16 in which the tubes run straight, as a result of which better inspection and repair options are created; the necessary welded connections between individual parts of the tubes 11 are placed in these sections.
  • a jacket 17 with thermal insulation which serves to protect the former from the flame occurring during a sodium-water reaction and to guide the flow.
  • the tube bundles 5 with the jacket 17 can be removed from the container upwards (after loosening the connections to the tube plate 10), just as the downpipe 6, distributor 7, pipes 8 and sub-distributor 9 can be removed through the central tube 4.
  • a honeycomb-like structure which prevents convection, is attached between it and the jacket 17, via which the temperature range between sodium entry and exit is reduced. This can be dispensed with if the sodium inlet and outlet are sufficiently far apart, as indicated in FIG. 4 with the alternative position of the outlet nozzle 3 shown in dashed lines.
  • the superheater tubes end in further tube plates 19, from each of which a steam line 20 begins.
  • the tube bundles 5 are designed by increasing their tubes 11 so that space is created on the outside for further tube bundles 21 which are constructed from additional tubes 22 in which the steam is reheated.
  • the reheater tube bundles 21 can also extend over the entire height of the steam generator. They are designed so that the sodium temperatures in these bundles are as similar as possible to those prevailing in the steam generators / superheater bundles located at the same level.
  • the steam line is designated 23, the steam line 24. Both end in a tube plate 25 in a distributor or collector 27, which is part of a spherical surface, so that a probe (not shown here) which can be pivoted about point 26 is easily inserted into the individual tubes 22 with a minimum of movement can.
  • the individual tube bundles 5 and 21 are suspended in a known manner on rods 33 from brackets 28 on the jacket 17 (see FIG. 6).
  • the brackets 28 are designed such that when the rods 33 of a tube bundle are torn off, the bundle is supported on the next lower bracket.

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Thermal Sciences (AREA)
  • Mechanical Engineering (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (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)
EP79104671A 1978-11-27 1979-11-23 Flüssigmetall-beheizter Dampferzeuger mit integrierter Zwischenüberhitzung Expired EP0011834B1 (de)

Priority Applications (1)

Application Number Priority Date Filing Date Title
AT79104671T ATE389T1 (de) 1978-11-27 1979-11-23 Fluessigmetall-beheizter dampferzeuger mit integrierter zwischenueberhitzung.

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE19782851197 DE2851197A1 (de) 1978-11-27 1978-11-27 Fluessigmetall-beheizter dampferzeuger mit integrierter zwischenueberhitzung
DE2851197 1978-11-27

Publications (2)

Publication Number Publication Date
EP0011834A1 EP0011834A1 (de) 1980-06-11
EP0011834B1 true EP0011834B1 (de) 1981-11-11

Family

ID=6055629

Family Applications (1)

Application Number Title Priority Date Filing Date
EP79104671A Expired EP0011834B1 (de) 1978-11-27 1979-11-23 Flüssigmetall-beheizter Dampferzeuger mit integrierter Zwischenüberhitzung

Country Status (6)

Country Link
US (1) US4446820A (enrdf_load_stackoverflow)
EP (1) EP0011834B1 (enrdf_load_stackoverflow)
JP (1) JPS6122721B2 (enrdf_load_stackoverflow)
AT (1) ATE389T1 (enrdf_load_stackoverflow)
DE (1) DE2851197A1 (enrdf_load_stackoverflow)
WO (1) WO1980001101A1 (enrdf_load_stackoverflow)

Families Citing this family (12)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
NL187177C (nl) * 1982-07-12 1991-06-17 Stork Ketel & App Vertikale stralingsketel.
FR2557280B1 (fr) * 1983-12-21 1986-03-28 Commissariat Energie Atomique Generateur de vapeur sodium-eau a tubes concentriques droits et a circulation de gaz dans l'espace annulaire
US4644906A (en) * 1985-05-09 1987-02-24 Stone & Webster Engineering Corp. Double tube helical coil steam generator
US4753773A (en) * 1985-05-09 1988-06-28 Stone & Webster Engineering Corporation Double tube steam generator
US4737337A (en) * 1985-05-09 1988-04-12 Stone & Webster Engineering Corporation Nuclear reactor having double tube helical coil heat exchanger
SE465591B (sv) * 1987-05-22 1991-09-30 Asea Atom Ab Aanggenerator med u-formade tubknippen att anvaendas i en tryckvattenreaktor
EP2180250A1 (de) * 2008-09-09 2010-04-28 Siemens Aktiengesellschaft Durchlaufdampferzeuger
US20110203575A1 (en) * 2009-08-24 2011-08-25 Robert Emery Thermodynamic/Solar Steam Generator
GB201008806D0 (en) * 2010-05-26 2010-07-14 Heat Recovery Solutions Ltd Heat exchange unit
DE102012210957A1 (de) 2012-06-27 2014-01-02 Enolcon Gmbh Hochtemperatur-Wärmespeicher mit Induktionsheizung und Metallschmelze und Wärmespeicher-Verbundsystem
DE102013110117A1 (de) * 2013-09-13 2015-04-02 Jess Gmbh Energiespeichersysteme Hochtemperaturwärmespeicher
US20190203614A1 (en) 2017-12-28 2019-07-04 Ge-Hitachi Nuclear Energy Americas Llc Systems and methods for steam reheat in power plants

Family Cites Families (14)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1096388B (de) * 1957-10-03 1961-01-05 Steinmueller Gmbh L & C Waermetauscher mit kugelschaligen Endkammern und Schraubenrohrbuendel
AT289867B (de) * 1967-06-16 1971-05-10 Waagner Biro Ag Wärmetauscher, insbesondere Durchlaufdampferzeuger, nur nukleare Zwecke
GB1236281A (en) * 1968-03-07 1971-06-23 Babcock & Wilcox Ltd Improvements in or relating to heat exchangers
DE1912341C3 (de) * 1969-03-11 1980-03-13 Linde Ag, 6200 Wiesbaden Wärmetauscher mit schraubenförmig gewickelten Rohrlagen und Verfahren zu seiner Herstellung
DE2251396B2 (de) * 1972-10-19 1979-12-06 Borsig Gmbh, 1000 Berlin Brennkammer eines Dampferzeugers
DE2448832C2 (de) * 1974-10-14 1985-03-07 Interatom Internationale Atomreaktorbau Gmbh, 5060 Bergisch Gladbach Flüssigmetall/Wasser-Wärmetauscher mit auswechselbaren Rohrbündeln
DE2522724B1 (de) * 1975-05-22 1976-11-18 Kraftwerk Union Ag Dampferzeuger mit kohlefeuerung und heizflaechen im oberteil des feuerraumes
DE2612081A1 (de) * 1976-03-22 1977-10-20 Kraftwerk Union Ag Dampferzeuger fuer druckwasser- kernreaktoren
FR2363772A1 (fr) * 1976-09-03 1978-03-31 Commissariat Energie Atomique Echangeur de chaleur, notamment generateur de vapeur chauffe au sodium liquide
US4116168A (en) * 1977-04-28 1978-09-26 Foster Wheeler Energy Corporation Vapor generating system utilizing integral separators and angularly arranged furnance boundary wall fluid flow tubes
US4284134A (en) * 1978-09-05 1981-08-18 General Atomic Company Helically coiled tube heat exchanger
US4290388A (en) * 1979-08-03 1981-09-22 Foster Wheeler Limited Vapor generator
US4337827A (en) * 1980-10-01 1982-07-06 The Babcock & Wilcox Company Helical steam generator tube support
US4357907A (en) * 1980-10-27 1982-11-09 Rockwell International Corporation Fluidized bed combustor with improved indirect heat exchanger units

Also Published As

Publication number Publication date
US4446820A (en) 1984-05-08
ATE389T1 (de) 1981-11-15
JPS55501155A (enrdf_load_stackoverflow) 1980-12-18
WO1980001101A1 (en) 1980-05-29
EP0011834A1 (de) 1980-06-11
JPS6122721B2 (enrdf_load_stackoverflow) 1986-06-02
DE2851197A1 (de) 1980-06-12

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