EP0015191A1 - Wärmetauscher - Google Patents

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Publication number
EP0015191A1
EP0015191A1 EP80400200A EP80400200A EP0015191A1 EP 0015191 A1 EP0015191 A1 EP 0015191A1 EP 80400200 A EP80400200 A EP 80400200A EP 80400200 A EP80400200 A EP 80400200A EP 0015191 A1 EP0015191 A1 EP 0015191A1
Authority
EP
European Patent Office
Prior art keywords
tubes
exchanger
parts
access
exchanger according
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
EP80400200A
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English (en)
French (fr)
Other versions
EP0015191B1 (de
Inventor
Marcel Robin
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.)
Filing date
Publication date
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First worldwide family litigation filed litigation Critical https://patents.darts-ip.com/?family=9221961&utm_source=***_patent&utm_medium=platform_link&utm_campaign=public_patent_search&patent=EP0015191(A1) "Global patent litigation dataset” by Darts-ip is licensed under a Creative Commons Attribution 4.0 International License.
Application filed by Commissariat a lEnergie Atomique CEA filed Critical Commissariat a lEnergie Atomique CEA
Publication of EP0015191A1 publication Critical patent/EP0015191A1/de
Application granted granted Critical
Publication of EP0015191B1 publication Critical patent/EP0015191B1/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
    • F22B37/00—Component parts or details of steam boilers
    • F22B37/02—Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
    • F22B37/10—Water tubes; Accessories therefor
    • F22B37/12—Forms of water tubes, e.g. of varying cross-section
    • F22B37/125—Bifurcates
    • 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
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B37/00—Component parts or details of steam boilers
    • F22B37/02—Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
    • F22B37/22—Drums; Headers; Accessories therefor
    • F22B37/221—Covers for drums, collectors, manholes or the like
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B37/00—Component parts or details of steam boilers
    • F22B37/02—Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
    • F22B37/38—Determining or indicating operating conditions in steam boilers, e.g. monitoring direction or rate of water flow through water tubes
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B37/00—Component parts or details of steam boilers
    • F22B37/02—Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
    • F22B37/42—Applications, arrangements, or dispositions of alarm or automatic safety devices
    • F22B37/421—Arrangements for detecting leaks
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B37/00—Component parts or details of steam boilers
    • F22B37/62—Component parts or details of steam boilers specially adapted for steam boilers of forced-flow type
    • F22B37/70—Arrangements for distributing water into water tubes
    • F22B37/74—Throttling arrangements for tubes or sets of tubes
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F28—HEAT EXCHANGE IN GENERAL
    • F28F—DETAILS OF HEAT-EXCHANGE AND HEAT-TRANSFER APPARATUS, OF GENERAL APPLICATION
    • F28F27/00—Control arrangements or safety devices specially adapted for heat-exchange or heat-transfer apparatus
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
    • Y10S—TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y10S165/00—Heat exchange
    • Y10S165/001—Heat exchange with alarm, indicator, recorder, test, or inspection means
    • Y10S165/006—Temperature

Definitions

  • the invention relates to an exchanger designed in particular to ensure heat transfer between two circuits of a nuclear power plant.
  • the invention relates in particular to an exchanger such as a steam generator comprising an envelope in which the heat conveyed by a primary fluid is transferred to a secondary fluid so as to heat and, optionally, to vaporize the latter, the circulating secondary fluid in tubes whose opposite ends open into inlet and outlet manifolds arranged outside the generator casing.
  • Steam generators of this type are used in particular, although not exclusively, in the circuits of nuclear reactors with liquid metal cooling to ensure heat transfer between a cooling circuit in which a liquid metal such as sodium and a circuit supplying an electricity production installation in which a liquid such as water circulates.
  • the length of the tubes in which the secondary fluid generally consisting of water circulates is adapted to the quality of steam to be produced and often of the order of a hundred meters and the number of these tubes is relatively large, so as to allow a heat exchange as complete as possible between the liquid sodium which generally constitutes the primary fluid and the water or the vapor circulating in the tubes, the latter bathing in the liquid sodium.
  • each box and its cover which is usually achieved by means of an autoclave seal, the diameter of which can reach approximately 420 mm, risks presenting defects during operation.
  • the dimensions of the box which has a relatively large length compared to its diameter, make it quite difficult to locate the tubes and access to a well-defined orifice.
  • the exchanger and the collectors are generally arranged inside an insulating material which it is necessary to dismantle before having access to the tubes.
  • the subject of the invention is an exchanger making it possible to eliminate the drawbacks mentioned above by eliminating the thick tubular plates and large diameter seals, while facilitating access to the orifices of each of the tubes in order to check the condition of the wall of the tubes, as well as their tightness, carry out the necessary measurements or check the condition of a flow stabilization device (diaphragm).
  • an exchanger comprising a casing in which the heat conveyed by a primary fluid is transferred to a secondary fluid so as to heat up the latter, the secondary fluid flowing in tubes, the opposite ends of which open into tubular inlet and outlet manifolds disposed outside the casing of the exchanger and surrounding it at least in part, is characterized in that each of the tubes comprises two access devices each closed by a removable plug, each of the access devices being arranged in a part of the tube located between the shell of the exchanger and the corresponding collector.
  • collectors of tubular shape makes it possible to substantially reduce the thickness of the walls compared to the cylindrical boxes because of the reduction in stresses which results at the level of the walls for a given internal pressure.
  • realization at each end of the tubes, between the manifold and the shell of the exchanger, of an access device closed by a removable plug avoids the sealing problems associated with the large dimensions of the orifice to be closed and to facilitate individual access to each of the tubes, in particular by arranging the access devices outside the insulation, when the shell of the exchanger and the collectors are in an insulation.
  • each of said parts of the tubes has a first straight portion ending in the access device, and a second portion forming a T with the straight portion and connecting the latter to the corresponding collector.
  • each of said parts of the tubes then extends in a direction substantially normal to the shell of the exchanger.
  • the second portion of each of said parts of the tubes is preferably connected to the straight portion near the corresponding access device.
  • the plug closing the access device arranged in the part of each of the tubes situated between the envelope of the exchanger and the inlet manifold can then carry a tubular member which extends in the rectilinear portion of said part of the tubes beyond the connection of the second portion of said portion of the tubes, the tubular member being perforated laterally at the level of the second portion and supporting a diaphragm or more generally a device creating a similar pressure drop beyond the latter.
  • the second portion of each of said parts of the tubes forms a dilatation lyre.
  • This characteristic advantageously limits the reaction exerted by each of the tubes on the thermal sleeve which connects the latter to the shell of the exchanger during variations in temperature of the fluid flowing in the tubes.
  • the rectilinear portion of each of said parts of the tubes is surrounded by an anti-torsion device, one end of which is fixed to the shell of the exchanger and the other end of which has, for example at least one longitudinal notch into which a finger integral with the rectilinear portion penetrates in the vicinity of the access device, the anti-twist device further comprising a longitudinal slot through which the second portion of the corresponding tube portion passes.
  • each of said parts of the tubes comprises a threaded portion surrounding the access device, onto which is screwed a nut by means of which the corresponding plug is normally pressed in a sealed manner against the device. 'access.
  • At least one of the plugs blocking the access devices carries a temperature measurement device and all can be replaced by a leak test device.
  • the steam generator shown diagrammatically in FIG. 1 is a known generator, designed to be placed between a cooling circuit of a nuclear reactor cooled by liquid metal, and a circuit supplying an installation for producing electricity.
  • a steam generator of this type comprises a casing 10, of generally cylindrical shape, arranged vertically and inside which circulates a primary fluid 12, constituted in particular by a liquid metal such as sodium, which penetrates at the upper end of the casing 10 by inlet orifices 14 and which emerges from the steam generator by an outlet orifice 16 formed at the base of the casing 10.
  • sodium 12 circulates in a circuit of a nuclear reactor and carries the heat coming from the reactions occurring in the core of this reactor.
  • the envelope 10 is sealed and the sodium 12 is placed under an argon atmosphere 18.
  • a number of tubes 20, of appropriate section, are arranged in a helical winding inside the envelope 10, where they are immersed in sodium 12, so as to transfer to a volatile secondary fluid, such as water, circulating in the tubes 20, the greatest possible thermal power compatible with the good behavior of the tubes. Due to the volatile nature of the secondary fluid circulating in the tubes 20, the length and the section of the tubes 20 are chosen so that the fluid entering through the lower end of the tubes in the liquid state leaves at their upper end at l state of superheated steam under the effect of the heat given off by liquid sodium 12.
  • a volatile secondary fluid such as water
  • the lower and upper ends of the tubes 20 are connected respectively to four inlet water boxes 22 and four outlet steam boxes 24, only two of each of these boxes being shown in FIG. 1.
  • the inlet 22 and outlet 24 boxes are substantially identical and each have a cylindrical wall with an axis vertical, made in one piece with an upper end wall into which the corresponding ends of the tubes 20 open, and their lower end is closed by a removable cover 23, 25, allowing access to the openings of the facing tubes vis-à-vis, in particular in order to proceed to the inspection of the latter.
  • at least one inlet pipe 26 and at least one outlet pipe 28 open into the tubular wall of each of the boxes 22 and 24 respectively.
  • the pipes 26 and 28 make it possible to connect each of the boxes to water and steam collectors respectively, each rectilinear collector receiving the output of two boxes.
  • the collectors are themselves connected to the electricity production installation.
  • the plates constituting the walls of the boxes must be relatively thick to resist the pressure of the secondary fluid and the seal between the removable cover and the box is ensured by an autoclave seal d 'a relatively large diameter, up to for example 420 mm, so that leaks can occur during operation.
  • a steam generator substantially of the same type as that shown in FIG. 1 and comprising in particular a substantially cylindrical sealed envelope with a vertical axis 110, orifices inlet 114 and outlet 116 of the primary fluid 112 formed respectively at the upper part and at the base of the casing 110, the primary fluid 112 being in an argon atmosphere 118, while the secondary fluid circulates in tubes 120 arranged for example in a helical winding inside the envelope 110, so that the secondary fluid circulates between the lower end 130 and the upper end 132 of these tubes 120.
  • the lower ends 130 and upper 132 120 tubes lead to annular parts of the cylindrical wall of the envelope 110 and extend outside of the latter by parts 134 and 136, the ends of which open respectively into a tubular inlet manifold 138 and into a tubular outlet manifold 140 at least partially surrounding the envelope. 110 of the steam generator.
  • the collectors 138 and 140 are arranged below the ends 130 and 132 of the tubes 120, so that the parts 134 and 136 disposed OUTSIDE - laughing envelope 110 open into the upper part of manifolds 138 and 140.
  • the inlet manifold 138 is supplied with secondary liquid such as water through at least one inlet pipe 142, for example by means of a pump (not shown) and the manifold outlet 140 delivers water vapor through at least one outlet line 144 to one or more known devices (not shown) making it possible to transform the energy stored by the water vapor into energy that can be used industrially, and in particular energy electric.
  • the tubes 120 constitute a part of a closed circuit generally constituting the supply circuit of the installation for producing electricity in a nuclear reactor cooled by liquid metal, and in which the volatile secondary liquid circulates such as the water.
  • the tubular shape of the collectors 138 and 140 makes it possible to substantially reduce the thickness of the walls which constitute them due to the reduction of the stresses generated in the wall by a given internal pressure, compared to the box-shaped collectors formed by a flat plate into which open the tubes and a cover.
  • the internal diameter of each of the tubular collectors can be around 400 mm.
  • access to the ends 130 and 132 of each of the tubes 120 is carried out by access devices 146 comprising orifices formed in each of the parts 134 and 136 and normally closed by removable plugs 148. It is thus possible to have individual access at the two ends of each of the tubes 120 without the need to provide the collectors 138 and 140 with a large cover whose sealing may prove to be defective during operation of the reactor.
  • the casing 110 and the collectors 138 and 140 are generally disposed inside a thermal insulation (not shown), and the access devices 146 then protrude outside of this thermal insulation.
  • the manifolds 138 and 140 as well as the external parts 134 and 136 of the tubes 120 are symmetrical, so that only the inlet manifold 138 and one of the corresponding external parts 134 of the tubes 120 will be described with reference to the figure. 3, before describing an example of distribution in space of these parts of tubes with reference to FIGS. 4 and 5.
  • Each of the parts 134 has a rectilinear portion 150 which extends in a direction substantially normal to the envelope 110 of the steam generator and a substantially vertical portion 152 forming a T with the rectilinear portion 150 for connecting the latter to the manifold 138.
  • the rectilinear portion 150 of the external part 134 of the tube 120 ends in the access device 146, normally closed by the plug 148 as illustrated in particular in FIG. 6.
  • the vertical portion 152 of the external portion 134 is connected to the rectilinear portion 150 near the access device 146, so that different control, measurement, etc. devices. can be introduced into the external part 134 at the connection between the portions 150 and 152 of each of the external parts of the tubes as will be seen below.
  • the internal section of the tubes 120 is preferably constant, even at the level of the external parts 134 and 136.
  • each tubes comprises at the end of its rectilinear portion 150 surrounding the access device 146 a threaded part 154 on which is screwed a nut 156 by means of which the corresponding plug 148, or any other control or measurement device, is biased against the annular end of the straight portion 150 of the tube, so that an annular seal 158 carried by the plug 148 engages this end in a sealed manner.
  • this portion 150 is provided with an anti-twisting device 160 (see FIG.
  • a tube comprising a tube, one end of which is fixed to the casing 110 of the generator by any suitable means such as, for example, by a weld 162 and the other end of which has two diametrically opposite notches 164 which extend in a longitudinal direction relative to the tube 160 and in which penetrate fingers 166 extending radially outward from the end of the straight portion 150 in which the access orifice 146. is formed.
  • the number of notches 164 and of fingers 166 can be different from two and the fingers 166 can also be attached to the straight portion 150 of the pipe.
  • the anti-twist tube 160 also has in its lower part a longitudinal slot 168 which the vertical portion 152 of the tube 120 crosses.
  • the rectilinear portion 150 of each of the external parts 134 or 136 of the tubes 120 passes through the envelope 110 of the steam generator with a certain jea and it is fixed to this the latter by a thermal sleeve 170 disposed inside the envelope and fixed to the latter by any suitable means such as, for example, by welding.
  • This structure makes it possible to compensate for the deformations resulting from the expansion of the tubes and of the envelope of the steam generator.
  • each of the vertical portions 152 has the shape of a lyre as shown in dashed lines in FIG. 3 and as shown more precisely in FIG. 4.
  • each of the bypass portions 152 is fixed to the wall of the corresponding collector by any suitable means such as , for example, by welding and communicates with the interior of this collector by a radial opening 172 formed in the wall of the latter.
  • the spatial distribution of the external parts 134 of the tubes 120 requires special care due to the large number of tubes opening out of the casing 110 of the exchanger and the shape particular of the external parts 134 imposed by the invention.
  • the tubes 120 pass through the envelope 110 in a number of superimposed plies (five in the figures) and form rows regularly distributed over the circumference of the envelope, each row being constituted by a tube of each layer and the tubes of each row being aligned along a generatrix of the envelope.
  • the rectilinear portions 150 of each of the tubes protrude radially outside the casing 110 of the exchanger, so that they are distributed in five superposed plies defining rows of five rectilinear portions regularly distributed at the periphery of the envelope.
  • the portions 152 open laterally on the portions 150, as shown in FIG. 5, so as to be able to descend vertically between the rows formed by the tubes, the mouth of the portion 152 in the portion 150 being all the more distant from the envelope 110 as the portion 150 is located in a sheet closer to the collector 138 (see FIG. 4).
  • the portions 152 corresponding to the same row of tubes open out alternately on one side and the other of the portions 150 (see FIG. 5), so that the portions 152 corresponding to two adjacent rows are arranged in staggered rows in their vertical parts arranged between these rows.
  • the portions 152 can all open out on the same side of the row of portions 150 which corresponds to them, and the vertical parts of the portions 152 arranged between two adjacent rows then all correspond to the same row of tubes.
  • the portions 152 corresponding to the same row of tubes are brought back in the radial plane passing through the rectilinear portions 150 of this row of tubes, to form nested expansion lyres there (FIG. 4).
  • the portions 152 of each row of tubes are then connected to the manifold 138, at equal distance from each other, on a sector defined at the top of the manifold, in the same radial plane as the portions 150 which correspond to them.
  • the access from each of the openings is particularly easy as illustrated in particular in FIGS. 3 and 4. It is thus possible to use the access orifice formed in each of the rectilinear portions 150 to carry out, when stationary, an inspection of the tube by eddy currents or a control of the etan cheerfulness. Furthermore, it is possible to install, through this orifice, devices for adjusting, measuring or controlling the operation of the generator, as explained below, in the description of FIGS. 7 and 8.
  • FIG. 3 illustrates the replacement of one of the plugs 148 by a device for checking the tightness of the corresponding tube 120, designated by the general reference 174.
  • This device is put in place after the steam generator has cooled and drained. of the secondary circuit. It essentially comprises a tubular end-piece 176 extending beyond the T-shaped connection of the portion 152 to close the latter in leaktight manner by means of two annular seals 178 arranged on either side of the mouth of the portion vertical.
  • the tubular endpiece 176 comprises a collar 180, tightened by means of the nut 156 against the free end of the straight portion 150 of the tube, in which is housed a porous member such as a sponge 182 filled, for example with water soapy.
  • the device 174 thus makes it possible to observe the bubbles which form in the soapy water impregnating the sponge 182 at the outlet of the tubular nozzle. 176 in the event of a leak in the wall of the corresponding tube 120.
  • This leak detection device is only described by way of nonlimiting example and can be replaced by any other known device.
  • the device described can be used differently by impregnating the sponge 182 with a reagent sensitive to a determined gas which is injected into the argon inside the envelope 110 of the steam generator, this gas can for example be ammonia '.
  • thermowell support 186 capable of receiving a temperature measurement device such as a connected thermocouple to a suitable measuring device, the sensitive part of which is preferably arranged at the connection of the vertical portion 152 to the straight portion 150.
  • the thermocouple capable of being received in the support in the thermowell 186 carried by the plug 148 can in particular make it possible to measure the temperature of the superheated steam leaving a certain number of suitably chosen tubes 120.
  • FIG. 8 shows the straight portion 150 of the external part 134 of a tube 120, the end of which opens into the inlet manifold 138, the plug 148 closing the access orifice 146 formed in the portion 150 carrying a diaphragm 188 which makes it possible to stabilize the flow of water circulating in the tubes 120 of the steam generator.
  • the diaphragm 188 is formed at the end of a tubular member 190 carried by the plug 148 and extending beyond the junction between the vertical portion 152 and the straight portion 150 of the portion 134.
  • the tubular member 190 is perforated laterally by means of holes 192 formed at the vertical portion 152 and an annular seal 184 is arranged between the tubular member 190 and the straight portion 150 of the tube between the branch portion 152 and the casing 110 of the steam generator so that the water coming from the inlet manifold 138 and entering the straight portion 150 through the portion 152 must pass through the holes 192 and the diaphragm 188 before entering the interior of the steam generator. Control and possible replacement of diaphragms 188 can thus be performed in a particularly simple manner. Of course, the diaphragm 188 can be replaced by any device creating a similar pressure drop.
  • the measurement and control devices which have just been described by way of example are not limiting of the possibilities of access to the ends of the tubes of the steam generator resulting from the present invention.
  • the dismantling of each of the plugs 148 may allow after cooling and draining of the generator the introduction of any known measurement or control devices such as, for example, an eddy current or ultrasonic probe allowing the inspection of each of the tubes.
  • the invention is not limited to a steam generator and relates to all the exchangers in which the heat conveyed by a primary fluid is used to heat a secondary fluid.

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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)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
EP80400200A 1979-02-14 1980-02-08 Wärmetauscher Expired EP0015191B1 (de)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
FR7903746 1979-02-14
FR7903746A FR2449260A1 (fr) 1979-02-14 1979-02-14 Echangeur thermique

Publications (2)

Publication Number Publication Date
EP0015191A1 true EP0015191A1 (de) 1980-09-03
EP0015191B1 EP0015191B1 (de) 1982-12-01

Family

ID=9221961

Family Applications (1)

Application Number Title Priority Date Filing Date
EP80400200A Expired EP0015191B1 (de) 1979-02-14 1980-02-08 Wärmetauscher

Country Status (5)

Country Link
US (1) US4311189A (de)
EP (1) EP0015191B1 (de)
JP (1) JPS55137402A (de)
DE (1) DE3061174D1 (de)
FR (1) FR2449260A1 (de)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0091374A1 (de) * 1982-03-31 1983-10-12 Novatome Behelfsabsperreinrichtung für ein Dampferzeugerrohr im Falle eines Lecks

Families Citing this family (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2509433A1 (fr) * 1981-07-08 1983-01-14 Electricite De France Dispositif de detection de fuites dans un generateur de vapeur
JPS59150202A (ja) * 1983-02-16 1984-08-28 バブコツク日立株式会社 廃熱回収装置
FR2549935B1 (fr) * 1983-07-28 1985-10-25 Novatome Raccord de sortie vapeur pour generateur de vapeur
JPS6081407U (ja) * 1983-11-02 1985-06-06 バブコツク日立株式会社 ボイラ伝熱管構造
DE4225827A1 (de) * 1992-08-05 1994-02-10 Forbach Gmbh Offener Warmwasserspeicher
JP3028941B2 (ja) * 1997-10-22 2000-04-04 核燃料サイクル開発機構 多重シース型ナトリウム漏洩検出装置
US20040069470A1 (en) * 2002-09-10 2004-04-15 Jacob Gorbulsky Bent-tube heat exchanger
US20100258062A1 (en) * 2009-04-14 2010-10-14 Cliff Berry Cold water pre-heater
US9631807B2 (en) 2014-09-22 2017-04-25 University Research Glassware Corporation Continuous ultrapure steam generator

Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR1352958A (fr) * 1963-01-09 1964-02-21 Henri Lardet Atel Perfectionnement aux générateurs de vapeur et d'eau surchauffée
US3319657A (en) * 1964-10-16 1967-05-16 Louis A Nyiri Coil freeze protection device
FR2112007A1 (en) * 1970-04-03 1972-06-16 Edf Tube bundle heat exchanger - has internal reservoir to contain overflow surges due to leaks
FR2149983A5 (de) * 1971-08-09 1973-03-30 Westinghouse Electric Corp
DE2536757A1 (de) * 1974-08-19 1976-03-11 Hitachi Ltd Dampferzeuger
FR2379881A1 (fr) * 1977-02-04 1978-09-01 Commissariat Energie Atomique Bloc-pompe echangeur de chaleur pour reacteurs nucleaires

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2110024A (en) * 1936-08-29 1938-03-01 Gen Electric Heat exchange unit
US3112735A (en) * 1959-03-30 1963-12-03 Babcock & Wilcox Co Liquid metal heated vapor generator
US3941187A (en) * 1971-07-14 1976-03-02 The Babcock & Wilcox Company Consolidated nuclear steam generator

Patent Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR1352958A (fr) * 1963-01-09 1964-02-21 Henri Lardet Atel Perfectionnement aux générateurs de vapeur et d'eau surchauffée
US3319657A (en) * 1964-10-16 1967-05-16 Louis A Nyiri Coil freeze protection device
FR2112007A1 (en) * 1970-04-03 1972-06-16 Edf Tube bundle heat exchanger - has internal reservoir to contain overflow surges due to leaks
FR2149983A5 (de) * 1971-08-09 1973-03-30 Westinghouse Electric Corp
DE2536757A1 (de) * 1974-08-19 1976-03-11 Hitachi Ltd Dampferzeuger
FR2379881A1 (fr) * 1977-02-04 1978-09-01 Commissariat Energie Atomique Bloc-pompe echangeur de chaleur pour reacteurs nucleaires

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0091374A1 (de) * 1982-03-31 1983-10-12 Novatome Behelfsabsperreinrichtung für ein Dampferzeugerrohr im Falle eines Lecks

Also Published As

Publication number Publication date
EP0015191B1 (de) 1982-12-01
DE3061174D1 (en) 1983-01-05
JPS55137402A (en) 1980-10-27
US4311189A (en) 1982-01-19
FR2449260B1 (de) 1982-12-17
FR2449260A1 (fr) 1980-09-12

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