EP0070758A1 - Dampferzeuger mit einer Vorrichtung zur Ermittlung von Undichtheiten - Google Patents
Dampferzeuger mit einer Vorrichtung zur Ermittlung von Undichtheiten Download PDFInfo
- Publication number
- EP0070758A1 EP0070758A1 EP82401251A EP82401251A EP0070758A1 EP 0070758 A1 EP0070758 A1 EP 0070758A1 EP 82401251 A EP82401251 A EP 82401251A EP 82401251 A EP82401251 A EP 82401251A EP 0070758 A1 EP0070758 A1 EP 0070758A1
- Authority
- EP
- European Patent Office
- Prior art keywords
- sodium
- circulation
- channels
- space
- chamber
- 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
Links
- 229910052708 sodium Inorganic materials 0.000 claims abstract description 102
- 239000011734 sodium Substances 0.000 claims abstract description 102
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 claims abstract description 98
- 239000007788 liquid Substances 0.000 claims abstract description 46
- 238000005070 sampling Methods 0.000 claims abstract description 25
- 230000001681 protective effect Effects 0.000 claims abstract description 18
- 238000001514 detection method Methods 0.000 claims abstract description 15
- 238000009826 distribution Methods 0.000 claims description 20
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 18
- 230000035939 shock Effects 0.000 claims description 5
- 150000003385 sodium Chemical class 0.000 description 4
- 238000006073 displacement reaction Methods 0.000 description 3
- 239000012530 fluid Substances 0.000 description 3
- 239000012535 impurity Substances 0.000 description 3
- 230000002093 peripheral effect Effects 0.000 description 3
- 230000004888 barrier function Effects 0.000 description 2
- 125000006850 spacer group Chemical group 0.000 description 2
- 239000000126 substance Substances 0.000 description 2
- 238000003466 welding Methods 0.000 description 2
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 230000006378 damage Effects 0.000 description 1
- 238000010790 dilution Methods 0.000 description 1
- 239000012895 dilution Substances 0.000 description 1
- 239000007789 gas Substances 0.000 description 1
- 239000001257 hydrogen Substances 0.000 description 1
- 229910052739 hydrogen Inorganic materials 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 238000009827 uniform distribution Methods 0.000 description 1
Images
Classifications
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B1/00—Methods of steam generation characterised by form of heating method
- F22B1/02—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
- F22B1/06—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being molten; Use of molten metal, e.g. zinc, as heat transfer medium
- F22B1/063—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being molten; Use of molten metal, e.g. zinc, as heat transfer medium for metal cooled nuclear reactors
Definitions
- the present invention relates to a device for detecting leaks in a steam generator.
- a boiler In power plants, a boiler provides heat to the fluid in a primary circuit, this fluid then circulates in a steam generator in order to transfer its heat to water in a secondary circuit which is transformed into vapor, this vapor is then sent to the turbines.
- the steam generator In nuclear power plants, for example of the fast neutron type, it is known to use liquid sodium as the primary fluid.
- 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.
- Steam generators of the "sodium-water” type generally include a primary secondary liquid sodium circuit consisting of a multitude of tubes immersed in liquid sodium and connected by welding to tubular plates, the water introduced into these tubes being transformed in vapor.
- the risk of leaks is located at the welds connecting the tubes to the tube plates.
- a known leak detection device consists in analyzing the liquid sodium sampled in the vicinity of the tube plates. During this sampling, a difficulty lies in the fact that the liquid sodium circulates at high speed, which results in a great dilution of the chemicals present in the sodium when the appearance of a leak.
- the present invention proposes a new design of the leak detection device which eliminates these drawbacks.
- the present invention relates particularly to a device for detecting leaks by sampling liquid sodium contained in a steam generator
- a primary circuit consisting of a sodium circulation chamber between an introduction chamber and a sodium discharge chamber, each chamber being limited on the side of the circulation enclosure by a sodium distribution grid, and on the other side by a tubular plate provided with an anti-thermal screen parallel to the tubular plate and separated from the latter by a space of confinement of a volume of liquid sodium for the protection of the tubular plate against thermal shocks
- a circuit secondary consisting of a plurality of water circulation tubes fixed in leaktight manner at their two ends to the tubular plates and opening out, on the other side of the latter, respectively in a steam evacuation chamber and a chamber water supply.
- the detection device comprising means for continuous sampling and analysis of a certain quantity of confined liquid sodium contained in the space for protection against thermal shocks.
- the means for sampling the confined sodium consists of at least one tubular collector placed in the protection space, at the periphery of the tubular plate and along which are distributed a plurality of sampling ports, and a plurality of channels opening at one end into the protective space and at the other end into the sodium circulation enclosure, these channels causing circulation of liquid sodium from the center of this space towards its periphery, towards the tubular collector.
- the sampling means is placed in the protective space corresponding to the sodium introduction chamber, and that the channels causing the circulation of sodium open into this space. protection in the vicinity of the periphery of the tube plate.
- the sampling means is placed in the protective space corresponding to the sodium discharge chamber, and that the channels causing the circulation of sodium open into this space. protection near the center of the tube plate.
- This steam generator comprises a cylindrical enclosure 1 of elongated shape, filled with circulating liquid sodium constituting the primary circuit. At one end of this enclosure is tightly fixed a closed cylindrical envelope 2 provided with a liquid sodium inlet 3 and defining an introduction chamber 4. On the other end of the cylindrical enclosure 1 is fixed so seals a closed cylindrical casing 5 provided with a liquid sodium outlet 7 and defining an evacuation chamber 6.
- the liquid sodium constituting the primary circuit of this steam generator fills completely the space delimited by the closed envelope 2, the cylindrical enclosure 1 and the closed envelope 5.
- the liquid sodium heated by the primary exchangers of the nuclear reactor enters through the introduction chamber 4 inside the cylindrical enclosure 1, gives up its heat to a secondary circuit placed inside this cylindrical enclosure 1, then leaves through the evacuation chamber 6 and returns to the primary exchangers of the nuclear reactor.
- the secondary circuit arranged inside the cylindrical enclosure 1 is composed of a plurality of straight tubes 8 arranged parallel to the longitudinal axis of the cylindrical enclosure 1 and regularly spaced from one another. These tubes pass through the entire interior of the cylindrical casing 1 as well as the introduction 4 and discharge 6 chambers. The ends of these tubes are connected on either side to two tubular plates 9, 10 which constitute the sealed bottom of the closed cylindrical envelopes 2 and 5. The faces opposite to the tubes of the tubular plates 9, 10 communicate with chambers 11, 12.
- the secondary water circuit is thus established: the water is introduced through the introduction 12 located on the side of the sodium discharge chamber 6 inside the tubes 8, turns into vapor thanks to the hot liquid sodium which surrounds the tubes 8 and leaves the tubes 8 through the discharge chamber 11 located side comprising the liquid sodium introduction chamber 4.
- This steam generator further comprises grids 13, 14 which are applied respectively to the inlet and outlet of the cylindrical enclosure 1 and which are intended to cause a uniformly distributed distribution of the flow of liquid sodium circulating inside the enclosure cylindrical 1, so that this liquid sodium gives up substantially the same amount of heat to all the tubes 8.
- This steam generator also comprises anti-thermal screens 15, 16 located respectively in the sodium introduction 4 and sodium discharge 6 chambers and arranged respectively, parallel to a small distance from the tubular plates 9 and 10.
- FIG. 2 which is an enlarged view of the part situated on the right in FIG. 1, we mainly find the introduction chamber 4 of the liquid sodium, the space of protection 17 against thermal shocks and the evacuation chamber of steam 11.
- This figure 2 shows on the other hand a set of means constituting the leak detection device which is the subject of the present invention and which we will now describe.
- This leak detection device comprises a sampling device located near the tubular plate 9 in order to analyze the liquid sodium located in contact with the welds connecting the tubes 8 to this tubular plate 9.
- This sampling device is made up a tubular collector 19 in the form of a torus disposed inside the protective space 17, a short distance from the tubular plate 9 and at its periphery. All the tubes 8 are therefore arranged inside the collector 19.
- This collector 19 is provided with a plurality of sampling orifices distributed uniformly and arranged radially inwards, the collector 19 is further connected by a set of lines 21 to an external pump to the steam generator 22 which sends the liquid sodium sampled in a unit 23 intended to chemically analyze this liquid sodium in order to determine whether there has been during the operation of the steam generator an introduction of water inside this liquid sodium.
- the sodium sample leak detection device further comprises a plurality of channels 20 which create a communication between the protective space 17 and the interior of the cylindrical chamber 1. These channels thus cross, at one end, the heat shield 15 and at the other end, the distribution grid 13.
- the liquid sodium collection device works as follows. If a leak occurs at the weld connecting one of the tubes 8 to the tube plate 9, since the pressure of the secondary circuit is very much higher than the pressure of the primary circuit, this leak will result in the introduction of water or vapor inside the liquid sodium, at the level of the tube plate 9.
- the liquid sodium comprising this water will therefore be that located in the protection space 17, since this liquid sodium is confined in this space, it is expedient take the sodium sample contained in this space since the impurities revealing the leak. are not immediately diluted in all of the sodium constituting the primary circuit. To understand the operation of this sampling device, we must take stock of the different pressures prevailing in the different chambers constituting the primary circuit of this steam generator.
- the liquid sodium enters the chamber 4 with a pressure P1; when it passes through the distribution grid 13, a pressure drop is created and, inside the cylindrical enclosure 1, there prevails a pressure P2 less than Pl.
- P1 a pressure drop
- Pl a pressure less than Pl.
- the pressure prevailing in the protection space 17 is therefore the same as that prevailing in chamber 4, that is to say Pl.
- This second device of collection works in a completely identical way to the first, it includes a tubular collector placed in the protective space at the periphery of the tubular plate in the same way as above. There are also channels 24 connecting the protection space and the interior of the cylindrical enclosure 1. The only difference is that these channels 24 are arranged so as to open into the central zone of the protection space. .
- FIG. 3 shows a particular embodiment of a sodium sampling device according to the present invention.
- This partial section is located in the steam generator in the region extending from the distribution grid to the tube plate, in the peripheral zone in which the tubular manifold and the circulation channels are mainly located.
- FIG. 3 there is a distinction between the end of the cylindrical enclosure 1 on which a distribution grid 13 is fixed radially, there is also a distinction between the tubular plate 9 arranged parallel to the distribution grid 13. Between the grid 13 and the plate 9 are the sodium introduction chamber 4, and, in parallel and at a small distance from the plate 9, an anti-thermal screen 15 which defines between it and the tubular plate 9 a protective space 17.
- the tubular manifold 19 disposed at the periphery of the tubular plate is rigidly held by means of support elements 25 which rigidly hold the heat shield 15 at the same time.
- the circulation channels 20 distributed at the periphery of the tube plate are arranged concentrically around some of the tubes 8 located at the periphery of the tube plate. These channels 20 are tightly welded to the faces of the grid 13 and of the screen 15 which are in contact with the introduction chamber 4 .. Between the channels and their corresponding concentric tubes there is an annular space 26.
- the tubes 8 normal or those surrounded by a channel 20 pass successively through the distribution grid 13 and the heat shield 15 passing through orifices formed in this grid and this screen, these orifices having a diameter greater than the outside diameter of the tubes 8 so that the liquid sodium can pass through the annular space left between these orifices and these tubes.
- the orifices 27 of the distribution grid 13 corresponding to the tubes surrounded by a channel 20 have a diameter greater than the orifices 28 of the distribution grid 13 corresponding to the other tubes. The purpose of this difference in diameter is to compensate for the pressure drop created by the channel 20 so that the flow of liquid sodium which leaves through the orifices 27 in the enclosure 1 is identical to the flow which leaves the other orifices 28 in this same enclosure 1.
- the liquid sodium circuit is established as follows: the sodium in the chamber 4 crosses the central zone of the screen 15 through the annular space defined by the orifices 30, then propagates radially outward in the chamber 17, spring from the chamber 17 through the annular space left by the orifices 29, circulates in the channel 20 and leaves in the enclosure 1 through the annular space left by the orifices 27.
- the manifold tubular 19 permanently sucks part of the sodium which propagates towards the outside of the chamber 17, then this sodium is brought by pipes to the outside of the steam generator from where it is analyzed chemically.
- the distribution grid 13 is not directly fixed to the cylindrical enclosure 1, but is rigidly fixed by welding to the channels 20 themselves welded to the screen anti-thermal 15 which is itself welded by spacers 25 around the tube plate 9.
- the channels 20 thus behave like spacers. In this way the expansions resulting from temperature variations allow a certain displacement of the distribution grid 13 relative to the end of the enclosure 1, thus avoiding the stresses in the structure.
- the present invention is not limited to the embodiment illustrated in FIG. 3 nor to the type of steam generator illustrated in FIG. 1. It would be possible, without departing from the scope of the invention, to imagine its application to other types steam generators, for example with helical tubes or U-shaped tubes.
Landscapes
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- High Energy & Nuclear Physics (AREA)
- Life Sciences & Earth Sciences (AREA)
- Sustainable Development (AREA)
- Sustainable Energy (AREA)
- Thermal Sciences (AREA)
- Mechanical Engineering (AREA)
- General Engineering & Computer Science (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Examining Or Testing Airtightness (AREA)
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR8113427 | 1981-07-08 | ||
FR8113427A FR2509433A1 (fr) | 1981-07-08 | 1981-07-08 | Dispositif de detection de fuites dans un generateur de vapeur |
Publications (2)
Publication Number | Publication Date |
---|---|
EP0070758A1 true EP0070758A1 (de) | 1983-01-26 |
EP0070758B1 EP0070758B1 (de) | 1984-12-19 |
Family
ID=9260351
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
EP82401251A Expired EP0070758B1 (de) | 1981-07-08 | 1982-07-02 | Dampferzeuger mit einer Vorrichtung zur Ermittlung von Undichtheiten |
Country Status (5)
Country | Link |
---|---|
US (1) | US4515748A (de) |
EP (1) | EP0070758B1 (de) |
JP (1) | JPS5866035A (de) |
DE (1) | DE3261615D1 (de) |
FR (1) | FR2509433A1 (de) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2576708A1 (fr) * | 1985-01-25 | 1986-08-01 | Novatome | Generateur de vapeur dont le fluide caloporteur est du metal liquide et dont la detection des fuites est effectuee par prelevement de ce metal liquide |
CZ298660B6 (cs) * | 2005-11-14 | 2007-12-12 | Matal@Oldrich | Zarízení pro provádení kontrol tesnosti teplosmenné plochy parního generátoru typu VVER v dobe odstávky |
Families Citing this family (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB2204942B (en) * | 1987-04-07 | 1991-08-21 | Nat Nuclear Corp Ltd | Heat exchangers |
JP5106812B2 (ja) * | 2006-09-05 | 2012-12-26 | 三菱重工コンプレッサ株式会社 | ガスクーラにおけるガス漏れ検知システム |
RU2706801C1 (ru) * | 2018-12-14 | 2019-11-21 | Российская Федерация, от имени которой выступает Государственная корпорация по атомной энергии "Росатом" Госкорпорация "Росатом" | Парогенератор обратного типа для реактора на быстрых нейтронах со свинцовым теплоносителем |
Citations (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2129508A5 (de) * | 1971-03-08 | 1972-10-27 | Foster Wheeler Corp | |
FR2287668A1 (fr) * | 1974-10-11 | 1976-05-07 | Commissariat Energie Atomique | Dispositif de protection thermique pour echangeur de chaleur |
EP0057643A2 (de) * | 1981-02-02 | 1982-08-11 | Commissariat à l'Energie Atomique | Schutzeinrichtung für die Rohrplatte an der heissen Seite eines vertikaler Wärmetauschers |
Family Cites Families (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US955004A (en) * | 1909-07-31 | 1910-04-12 | William O Singer | Wrench. |
FR2142139A5 (de) * | 1971-06-14 | 1973-01-26 | Commissariat Energie Atomique | |
GB1472445A (en) * | 1973-08-23 | 1977-05-04 | Electricite De France | Leak detection in heat-exchangers |
US4090554A (en) * | 1976-11-17 | 1978-05-23 | The Babcock & Wilcox Company | Heat exchanger |
FR2379881A1 (fr) * | 1977-02-04 | 1978-09-01 | Commissariat Energie Atomique | Bloc-pompe echangeur de chaleur pour reacteurs nucleaires |
FR2449260A1 (fr) * | 1979-02-14 | 1980-09-12 | Commissariat Energie Atomique | Echangeur thermique |
-
1981
- 1981-07-08 FR FR8113427A patent/FR2509433A1/fr active Granted
-
1982
- 1982-07-02 DE DE8282401251T patent/DE3261615D1/de not_active Expired
- 1982-07-02 EP EP82401251A patent/EP0070758B1/de not_active Expired
- 1982-07-08 JP JP57119163A patent/JPS5866035A/ja active Granted
- 1982-07-08 US US06/396,439 patent/US4515748A/en not_active Expired - Fee Related
Patent Citations (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2129508A5 (de) * | 1971-03-08 | 1972-10-27 | Foster Wheeler Corp | |
FR2287668A1 (fr) * | 1974-10-11 | 1976-05-07 | Commissariat Energie Atomique | Dispositif de protection thermique pour echangeur de chaleur |
EP0057643A2 (de) * | 1981-02-02 | 1982-08-11 | Commissariat à l'Energie Atomique | Schutzeinrichtung für die Rohrplatte an der heissen Seite eines vertikaler Wärmetauschers |
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2576708A1 (fr) * | 1985-01-25 | 1986-08-01 | Novatome | Generateur de vapeur dont le fluide caloporteur est du metal liquide et dont la detection des fuites est effectuee par prelevement de ce metal liquide |
EP0190075A1 (de) * | 1985-01-25 | 1986-08-06 | Novatome | Dampferzeuger mit flüssigem Metall als Wärmetransportmittel und mit Leckfeststellung durch Entnahme eines solchen flüssigen Metalles |
CZ298660B6 (cs) * | 2005-11-14 | 2007-12-12 | Matal@Oldrich | Zarízení pro provádení kontrol tesnosti teplosmenné plochy parního generátoru typu VVER v dobe odstávky |
Also Published As
Publication number | Publication date |
---|---|
DE3261615D1 (en) | 1985-01-31 |
US4515748A (en) | 1985-05-07 |
FR2509433B1 (de) | 1984-05-11 |
JPS5866035A (ja) | 1983-04-20 |
JPH0159558B2 (de) | 1989-12-18 |
EP0070758B1 (de) | 1984-12-19 |
FR2509433A1 (fr) | 1983-01-14 |
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