EP0206921A1 - Wärmetauscher mit koaxialen U-Rohren und Zwischenkreislauf von neutralem Gas und schneller Neutronenreaktor mit solchem Wärmetauscher - Google Patents

Wärmetauscher mit koaxialen U-Rohren und Zwischenkreislauf von neutralem Gas und schneller Neutronenreaktor mit solchem Wärmetauscher Download PDF

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Publication number
EP0206921A1
EP0206921A1 EP86401303A EP86401303A EP0206921A1 EP 0206921 A1 EP0206921 A1 EP 0206921A1 EP 86401303 A EP86401303 A EP 86401303A EP 86401303 A EP86401303 A EP 86401303A EP 0206921 A1 EP0206921 A1 EP 0206921A1
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EP
European Patent Office
Prior art keywords
fluid
tubes
gas
transfer fluid
heat exchanger
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
EP86401303A
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English (en)
French (fr)
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EP0206921B1 (de
Inventor
Zéphyr Tilliette
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.)
Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
Original Assignee
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.)
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Publication date
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Publication of EP0206921A1 publication Critical patent/EP0206921A1/de
Application granted granted Critical
Publication of EP0206921B1 publication Critical patent/EP0206921B1/de
Expired legal-status Critical Current

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Classifications

    • 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
    • F28D7/14—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 both tubes being bent
    • 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
    • F28D7/06—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 having a single U-bend
    • 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
    • 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
    • F28F9/005—Other auxiliary members within casings, e.g. internal filling means or sealing means
    • 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 heat exchanger comprising coaxial U-shaped tubes between which a neutral gas such as helium flows.
  • the invention also relates to the application of such an exchanger, in the form of steam generators, to different types of fast neutron nuclear reactors cooled by a heat transfer fluid which may be liquid sodium.
  • sodium / water vapor generators are "critical" components, due to the violent chemical reaction that can occur if sodium and water come into contact and the severity of the exchanges sodium / water-steam thermal.
  • the present invention specifically relates to a sodium / water heat exchanger having both a mechanical reliability and a functional reliability high enough that one can fearlessly consider the possible establishment of this heat exchanger, in the form of a steam generator, directly in the tank of an integrated type fast neutron nuclear reactor.
  • the application of the heat exchanger according to the invention is however not limited to reactors of this type and can in particular extend to fast neutron reactors of the loop type, in which the steam generators are placed in tanks separate from the main tank containing the reactor core.
  • this heat exchanger is characterized by its great simplicity and by the absence of a rigid connection between the internal tubes and the external tubes of the bundle of U-shaped tubes. This provides high mechanical reliability since the stresses due to differential expansions are avoided.
  • the ferrules surrounding the vertical branches of the bundle have main sodium entry windows placed above a normal level of sodium in the tank and auxiliary entry windows of sodium placed below a minimum level of ⁇ sodium in the tank, each ferrule being provided with a bell fixed above the main entry windows and immersed in sodium to a level below said minimum level , to constitute a sodium supply siphon for this shell.
  • the outer tubes are smooth, the inner tubes being provided on their outer surface with centering lugs and, in the ascending branch of the bundle, longitudinal or helical fins ensuring both an increase in heat exchange in this branch in order to compensate for the decrease in the temperature difference between heating and heated fluids and to distribute the boiling of water between the two branches and the maintenance of the inner tubes in the outer tubes.
  • the water inlet and outlet chambers are placed laterally with respect to the gas inlet and outlet chambers and separated from the latter by plates with water tubes / substantially vertical gases, the ends of the inner tubes fixed to these water / gas tube plates comprising horizontal parts, the gas inlet and outlet chambers being closed at their upper end by removable covers and the inlet chambers and water outlet being closed by removable covers placed opposite the water / gas tube plates.
  • the heat exchanger according to the invention comprises at least one tube opening into the water inlet chamber and at least one tube opening into the water outlet chamber, these tubes being able to be connected to a circuit. of external water by means of closing means making it possible to isolate the exchanger with respect to this circuit and comprising means for injecting a drain gas capable of driving the water out of the exchanger.
  • the gas / sodium tube plates are preferably fixed on a horizontal support piece surrounding said ferrules, this support piece being suitable to rest on a slab closing the tank, to ensure the support of the exchanger.
  • a subject of the invention is also the application of such a heat exchanger, in the form of a steam generator, to a fast-type nuclear reactor of integrated type and to a fast-type neutron reactor of the loop type.
  • the heat exchanger 10 shown in FIG. 1 comprises a bundle of double U-shaped tubes 12, only one of these double tubes being shown on a larger scale.
  • Each of the double U-shaped tubes 12 comprises an inner tube 14 inside which circulates water, then steam, and an outer tube 16 delimiting with the inner tube 14 an annular space 18 in which circulates a neutral gas such than helium.
  • the appreciable play existing between the interior and exterior tubes and the absence of concentricity requirement allows the bending of these double tubes.
  • Each of the double tubes 12 of the bundle comprises a vertical branch with descending heated fluid 12a, a vertical branch with ascending heated fluid 12b and a lower curved part 12c joining the vertical branches.
  • the upper ends of the descending and ascending branches of the outer tubes 16 are tightly fixed on two horizontal tube plates 20a and 20b, called gas / sodium tube plates, located side by side and at the same level.
  • These tube plates 20a and 20b rest on a horizontal support plate 22, respectively by means of two skirts 24a and 24b.
  • the support plate 22 itself rests, by means of a part 26, on a closing slab 28 of a tank 30, in which the double tubes 12 plunge. More specifically, the part 26 rests on the slab 28 at the periphery of an opening 32 formed therein and through which the double tubes 12 of the exchanger plunge into the liquid sodium 34 contained in the tank 30.
  • the tube plates 20a and 20b constitute the lower walls of a gas inlet chamber 36a and a gas outlet chamber 36b respectively.
  • a gas inlet pipe 38a and a gas outlet pipe 38b open into the chambers 36a and 36b respectively.
  • each of the chambers 36a and 36b is closed by a removable cover 40a and 40b respectively. The dismantling of these covers makes it possible to inspect the tube plates 20a and 20b.
  • the upper ends of the descending and ascending branches of the inner tubes 14 freely pass through the tube plates 20a and 20b and are folded at 90 ° inside the chambers 36a and 36b, to end in substantially horizontal parts 14a and 14b.
  • the ends of these horizontal parts 14a and 14b of the inner tubes 14 are tightly fixed on vertical tube plates 42a and 42b, called water / gas tube plates, constituting a part of the side wall of the chambers 36a and 36b respectively. .
  • the inner tubes 14 open respectively into a water inlet chamber 44a and into a water-vapor outlet chamber 44b.
  • a water inlet pipe 46a equipped with a valve 48a opens into the chamber 44a.
  • a water-vapor outlet pipe 46b equipped with a valve 48b opens into the steam outlet chamber 44b.
  • Pipes 50a and 50b are connected to the pipes 46a and 46b, between the valves 48a and 48b and the chambers 44a and 44b respectively. These pipes 50a and 50b are used to connect the steam generator to a circuit making it possible to inject a drain gas into the interior tubes 14.
  • Each of the chambers 44a and 44b is closed off by a removable cover 52a and 52b respectively, placed opposite the corresponding tube plate 42a, 42b.
  • each of the ferrules 54a and 54b comprises main entry windows 56a and 56b. These windows are placed at a level as close as possible to the tube plates 20a and 20b, so that the heat exchange between the liquid sodium circulating around the bundle of double tubes 12 and the steam water circulating in the internal tubes 14 s' performs over as large an area as possible.
  • the windows 56a and 56b are placed just below an adaptation piece 58 surrounding the ferrules 54a and 54b at the level of the slab 28, this piece 58 being suspended from the plate support 22.
  • the rise of liquid sodium 34 to the main entry windows 56a and 56b is obtained by creating around each of the ferrules 54a and 54b a siphon effect, by means of two bells 60a and 60b respectively fixed to the ferrules 54a and 54b just above windows 56a and 56b.
  • the bells 60a and 60b immerse in the liquid sodium 34 to a level below the minimum level N2 of the sodium in the tank.
  • each of the ferrules 54a and 54b further comprises auxiliary calibrated entry windows 62a and 62b allowing downward circulation of sodium inside the ferrules by natural convection if the circulation pumps stop.
  • the ferrules 54a and 54b are open at their lower ends, which are situated at the junction of the vertical branches 12a and 12b of the double tubes with the curved lower part 12c.
  • the ferrules 54a and 54b are tightly fixed to a transition piece 64.
  • the periphery of this piece 64 cooperates by a system of sealing 66 with a gas bell with a step 68 separating inside the tank 30 the hot sodium admitted into the exchanger 10 through the inlet windows 56a and 56b from the cold sodium exiting from the lower end of the ferrules 54a and 54b.
  • the double tubes 12 Due to their U-shape, the double tubes 12 easily absorb the consequences of small temperature differences between the descending and ascending branches.
  • the temperatures of tubes 1-2 of each branch are in fact very similar due to the moderate exchange coefficient by gas convection.
  • the outer tubes 16 are smooth and expand freely in the vertical direction from the tube plates 20a and 20b.
  • the descending branches and the curved lower parts of the inner tubes 14 are also smooth, and only have spaced centering lugs 70 which allow the inner tubes to be held correctly in the outer tubes.
  • the inner tubes 14 can also be smooth and provided with centering lugs on their outer faces. However, they preferably have on their outer faces longitudinal or helical fins 72 simultaneously ensuring the centering of the inner tubes in the outer tubes and a more efficient heat exchange, in order to balance the heat powers exchanged and distribute the boiling of the on both branches.
  • the inner tubes 14 are of small diameter and moderate thickness, which gives them good flexibility. This flexibility as well as the annular space which they have inside the external tubes also allows them to escape the transverse or horizontal stresses of expansion.
  • the vertical differential expansion between the branches of the inner tubes is absorbed by the horizontal parts 14a and 14b of the inner tubes 14.
  • the positioning of the double tubes 12 of the bundle is ensured in a conventional manner by horizontal grids 74.
  • the grids 74 located at the bottom of the ferrules 54a and 54b provide a lateral guidance of the tubes 12, while allowing a certain transverse flexibility of the tubes, that is to say a deformation of the latter in the plane passing through the axes of the descending 12a and rising 12b branches of the tubes 12.
  • This configuration allows take into account possible differences in transverse expansion between the branches of the tubes at the bottom of the exchanger.
  • one or more devices 76 are provided inside the tank 30 for guiding the ferrules 54a and 54b, that is to say preventing their horizontal displacement, while allowing the vertical expansion of these ferrules by compared to the tank.
  • the sodium 34 circulates from bottom to top inside the ferrules 54a and 54b, between the inlet windows 56a and the lower ends. Ferrules. It enters at a temperature of around 550 ° C and comes out at a temperature of around 400 ° C.
  • the water constituting the secondary fluid of the generator enters the internal tubes 14 through the inlet chamber (s) 44a, to exit through the chambers 44b in the vapor state.
  • the inlet and outlet temperatures of water and steam are approximately 250 ° C and approximately 500 ° C, respectively.
  • the pressure of the steamer is also slightly lower than that of helium, so that the inner tubes are stressed only by a very small pressure difference. This characteristic virtually eliminates any possibility of water / vapor leakage to sodium and therefore constitutes a guarantee of high functional reliability.
  • the helium of the intermediate circuit enters the inter-tube space 18 through the chamber 36a at a temperature close to 250 ° C, to exit through the chamber 36b at a temperature of about 520 ° C. Its pressure is moderate and is limited to approximately 7 MPa. The flow of helium is therefore in the same direction as that of water.
  • the heat exchange between water and sodium is therefore carried out cocurrently in the descending branches 12a of the tubes and countercurrently in the ascending branches 12b.
  • the presence of the intermediate gas makes it possible to admit much greater temperature differences than in two-fluid heat exchangers since the intermediate gas then serves as a thermal buffer.
  • the helium circulating in the inter-tube space 18 constitutes an effective means of controlling the tubes of the bundle, all the more so since its volume is low due to a possible concept of a loop. compact helium located near the reactor and associated with each steam generator.
  • the arrangement of the chambers 44a and 44b laterally with respect to the assembly, of the heat exchanger avoids the presence of a large volume of water directly above the bundle of tubes, this which is more satisfactory from a safety point of view.
  • the water inlet and outlet chambers could be placed immediately above the helium inlet and outlet chambers, by fitting these chambers with access covers placed laterally.
  • the inner tubes 14 should have a helical shape in the gas inlet and outlet chambers, in order to compensate for the vertical differential expansions.
  • heat exchange modules such as the module described above with reference to FIG. 1 can be placed side by side to constitute the exchanger itself.
  • the sodium / water exchanger with double U-tubes described above with reference to FIGS. 1 and 2 can in particular be used as a steam generator and placed either in a satellite tank of the main tank of a fast neutron nuclear reactor of the type loop, either directly in the main reactor vessel. This latter use simplifies the installation and makes it more compact.
  • FIG. 3 The installation of a steam generator of the type described above with reference to FIGS. 1 and 2 directly in the main tank of an integrated type fast neutron nuclear reactor is illustrated in FIG. 3.
  • the vessel 30 constitutes the main vessel of an integrated type fast neutron nuclear reactor.
  • the core 78 of the reactor, the primary pumps 82 and the heat exchangers constituted here by steam generators 10 produced in accordance with the invention are placed directly inside the vessel 30.
  • the latter is also filled with liquid sodium 34 and closed at its upper end by the closing plate 28 to which the steam generators 10 are suspended.
  • the core 78 of the reactor rests in a known manner on the bottom of the tank 30 by a supply and support base 80.
  • the seal between the collectors 34a and 34b is obtained at the steam generators 10 by transition pieces 64 fixed in leaktight manner around the ferrules 54a and 54b and cooperating with the internal tank 68 by gas bell sealing systems 66.
  • At least one device 76 is provided in the vicinity of the lower end of each of the steam generators, for horizontally holding the ferrules 54a and 54b, while leaving them free to expand vertically.
  • the sodium 34 crosses from bottom to top the core 78 of the reactor, to take part of the heat released by the fission reaction.
  • the sodium thus heated enters the steam generators 10 through the inlet windows 56a and 56b (FIGS. 1 and 2) and circulates from bottom to top inside the ferrules 54a and 54b, around the double tubes of the beam.
  • the cooled sodium exits into the cold collector 34b through the lower end of the ferrules 54a and 54b, before being taken up by the pumps, which discharge it into the supply bed 80 by pipes 84.
  • Each steam generator 10 can be in the form of separate modules, or in groups of two modules, which makes it possible to make the crossings of the slab 28 circular.
  • auxiliary inlet windows 62a and 62b (FIGS. 1 and 2) on the steam generators 10 enables them to perform the functions of cooling exchangers of the reactor when stopped, which allows to do without the specialized loops usually used.
  • the reduction in reactor cost brought about by the elimination of the sodium intermediate circuit is further increased by this disappearance.
  • FIG 4 shows another .application of the heat exchanger described above with reference to Figures 1 and 2, in the case where it constitutes a steam generator 10 placed in an annex tank 30 'separate from the main tank (not shown) containing the core of a fast neutron nuclear reactor.
  • the tank 30 ' is suspended from a slab 28 on which the steam generator 10 also rests. More precisely, the slab 28 has an opening 32 at the periphery of which bears an annular piece 26 to which the tank 30 is suspended '.
  • the plate 22 of the steam generator rests directly on the part 26.
  • the transition piece 64 is tightly connected to the vertical wall of the tank 30, by means of a gas bell sealing system 66.
  • a sodium inlet pipe 90 coming from the main tank of the reactor opens into the tank 30 above the transition piece 64 and a return pipe 92 opens into the tank 30 below the transition piece, to bring the sodium back to the main tank, under the action of a pump (not shown).
  • connecting pipes 86 pass through the plate 22 to open into the atmosphere of neutral gas overhanging the sodium inside the tank 30 '. These pipes 86 allow this atmosphere to be controlled.
  • a drain pipe 88 can also be provided at the bottom of the tank 30 '.
  • At least one guide device 76 is fixed to the wall of the tank 30 'to horizontally hold the lower part of the ferrules 54a and 54b.

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  • 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)
EP19860401303 1985-06-19 1986-06-16 Wärmetauscher mit koaxialen U-Rohren und Zwischenkreislauf von neutralem Gas und schneller Neutronenreaktor mit solchem Wärmetauscher Expired EP0206921B1 (de)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
FR8509327 1985-06-19
FR8509327A FR2583865B1 (fr) 1985-06-19 1985-06-19 Echangeur de chaleur a tubes en u coaxiaux a ecoulement intermediaire de gaz neutre et reacteur nucleaire a neutrons rapides comportant des echangeurs de ce type.

Publications (2)

Publication Number Publication Date
EP0206921A1 true EP0206921A1 (de) 1986-12-30
EP0206921B1 EP0206921B1 (de) 1988-12-21

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EP19860401303 Expired EP0206921B1 (de) 1985-06-19 1986-06-16 Wärmetauscher mit koaxialen U-Rohren und Zwischenkreislauf von neutralem Gas und schneller Neutronenreaktor mit solchem Wärmetauscher

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EP (1) EP0206921B1 (de)
DE (1) DE3661490D1 (de)
FR (1) FR2583865B1 (de)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
ITRM20110014A1 (it) * 2011-01-18 2012-07-19 S R S Servizi Di Ricerche E Svilup S R L Sottoassieme modulare msu per la realizzazione di scambiatori di calore di processo e generatori di vapore e relativi accessori

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN113566611B (zh) * 2021-08-12 2023-12-19 上海蓝滨石化设备有限责任公司 一种u形管三股流换热器

Citations (16)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2346104A (en) * 1942-04-04 1944-04-04 American Locomotive Co Heat exchanger
GB575749A (en) * 1944-04-04 1946-03-04 Midland Tar Distillers Ltd Improvements relating to the cooling of viscous liquids and to heat-exchange apparatus suitable for use therein
GB732204A (en) * 1953-08-27 1955-06-22 John Oswald Farrer Improvements in or relating to methods of heat exchange and apparatus therefor
GB748264A (en) * 1951-10-23 1956-04-25 Foster Wheeler Ltd Improvements in and relating to heat exchangers
FR71105E (fr) * 1957-02-05 1959-10-13 Stein & Roubaix Perfectionnement aux échangeurs de chaleur à convection
FR1501741A (fr) * 1965-05-21 1967-11-18 English Electric Co Ltd échangeur de chaleur pour transfert indirect de chaleur
BE710430A (de) * 1968-02-07 1968-08-07
FR2149983A5 (de) * 1971-08-09 1973-03-30 Westinghouse Electric Corp
FR2195822A1 (de) * 1972-08-08 1974-03-08 Commissariat Energie Atomique
FR2288285A1 (fr) * 1974-10-14 1976-05-14 Interatom Echangeur de chaleur metal liquide-eau avec faisceaux tubulaires interchangeables
FR2379881A1 (fr) * 1977-02-04 1978-09-01 Commissariat Energie Atomique Bloc-pompe echangeur de chaleur pour reacteurs nucleaires
US4140176A (en) * 1973-03-26 1979-02-20 The United States Of America As Represented By The United States Department Of Energy Protective tubes for sodium heated water tubes
EP0020265A1 (de) * 1979-05-31 1980-12-10 COMMISSARIAT A L'ENERGIE ATOMIQUE Etablissement de Caractère Scientifique Technique et Industriel Wärmeaustauscher für Kernreaktor
GB1599279A (en) * 1976-12-07 1981-09-30 Babcock International Ltd Steam generator
EP0064920A1 (de) * 1981-04-30 1982-11-17 Novatome Vorrichtung zur Dampferzeugung und zur Ableitung von Wärme in einem schnellen Brüter
GB2117169A (en) * 1982-03-16 1983-10-05 Westinghouse Electric Corp Double-wall tube with tritium barrier

Patent Citations (16)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2346104A (en) * 1942-04-04 1944-04-04 American Locomotive Co Heat exchanger
GB575749A (en) * 1944-04-04 1946-03-04 Midland Tar Distillers Ltd Improvements relating to the cooling of viscous liquids and to heat-exchange apparatus suitable for use therein
GB748264A (en) * 1951-10-23 1956-04-25 Foster Wheeler Ltd Improvements in and relating to heat exchangers
GB732204A (en) * 1953-08-27 1955-06-22 John Oswald Farrer Improvements in or relating to methods of heat exchange and apparatus therefor
FR71105E (fr) * 1957-02-05 1959-10-13 Stein & Roubaix Perfectionnement aux échangeurs de chaleur à convection
FR1501741A (fr) * 1965-05-21 1967-11-18 English Electric Co Ltd échangeur de chaleur pour transfert indirect de chaleur
BE710430A (de) * 1968-02-07 1968-08-07
FR2149983A5 (de) * 1971-08-09 1973-03-30 Westinghouse Electric Corp
FR2195822A1 (de) * 1972-08-08 1974-03-08 Commissariat Energie Atomique
US4140176A (en) * 1973-03-26 1979-02-20 The United States Of America As Represented By The United States Department Of Energy Protective tubes for sodium heated water tubes
FR2288285A1 (fr) * 1974-10-14 1976-05-14 Interatom Echangeur de chaleur metal liquide-eau avec faisceaux tubulaires interchangeables
GB1599279A (en) * 1976-12-07 1981-09-30 Babcock International Ltd Steam generator
FR2379881A1 (fr) * 1977-02-04 1978-09-01 Commissariat Energie Atomique Bloc-pompe echangeur de chaleur pour reacteurs nucleaires
EP0020265A1 (de) * 1979-05-31 1980-12-10 COMMISSARIAT A L'ENERGIE ATOMIQUE Etablissement de Caractère Scientifique Technique et Industriel Wärmeaustauscher für Kernreaktor
EP0064920A1 (de) * 1981-04-30 1982-11-17 Novatome Vorrichtung zur Dampferzeugung und zur Ableitung von Wärme in einem schnellen Brüter
GB2117169A (en) * 1982-03-16 1983-10-05 Westinghouse Electric Corp Double-wall tube with tritium barrier

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
POWER, vol. 104, no. 8, août 1960, pages 78,79,81, New York, US; J.H. AMMON et al.: "Liquid metals show new promise for nuclear plants" *

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
ITRM20110014A1 (it) * 2011-01-18 2012-07-19 S R S Servizi Di Ricerche E Svilup S R L Sottoassieme modulare msu per la realizzazione di scambiatori di calore di processo e generatori di vapore e relativi accessori

Also Published As

Publication number Publication date
EP0206921B1 (de) 1988-12-21
FR2583865A1 (fr) 1986-12-26
FR2583865B1 (fr) 1989-03-31
DE3661490D1 (en) 1989-01-26

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