EP0147304B1 - Générateur de vapeur sodium-eau à tubes concentriques droits et à circulation de gaz dans l'espace annulaire - Google Patents

Générateur de vapeur sodium-eau à tubes concentriques droits et à circulation de gaz dans l'espace annulaire Download PDF

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Publication number
EP0147304B1
EP0147304B1 EP84402629A EP84402629A EP0147304B1 EP 0147304 B1 EP0147304 B1 EP 0147304B1 EP 84402629 A EP84402629 A EP 84402629A EP 84402629 A EP84402629 A EP 84402629A EP 0147304 B1 EP0147304 B1 EP 0147304B1
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EP
European Patent Office
Prior art keywords
tube
steam generator
tubes
admission
intermediate fluid
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
EP84402629A
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German (de)
English (en)
French (fr)
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EP0147304A3 (en
EP0147304A2 (fr
Inventor
Zéphyr Tilliette
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Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
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Commissariat a lEnergie Atomique CEA
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Publication of EP0147304A2 publication Critical patent/EP0147304A2/fr
Publication of EP0147304A3 publication Critical patent/EP0147304A3/fr
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Classifications

    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
    • F01K—STEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
    • F01K3/00—Plants characterised by the use of steam or heat accumulators, or intermediate steam heaters, therein
    • F01K3/18—Plants characterised by the use of steam or heat accumulators, or intermediate steam heaters, therein having heaters
    • F01K3/181—Plants characterised by the use of steam or heat accumulators, or intermediate steam heaters, therein having heaters using nuclear heat
    • 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

Definitions

  • a sodium-water heat exchanger of this type is already known (FR-A-1 501 741).
  • this exchanger the liquid metal and the water are separated from each other by a space arranged to contain an intermediate heat transfer fluid.
  • the exchanger comprises a cylindrical barrel 30 closed at each of its ends by a thick tube plate 22, 25.
  • a convex bottom 41, 42 is attached to each tube plate.
  • Intermediate tube plates 31 and 32 are arranged in the barrel 30 between the plates 22 and 25.
  • a bundle of straight double-walled tubes extends between the plates 31 and 32.
  • the liquid metal, for example sodium circulates externally to the bundle of double-walled tubes.
  • the tube plate and the plate 22 define an inlet chamber for the intermediate fluid.
  • the tube plate 32 and the tube plate 25 determine a discharge chamber for this intermediate fluid.
  • An inlet connection 35 in the intake chamber is fixed to the barrel.
  • An evacuation connector 36 leaving the evacuation chamber of the intermediate fluid is fixed to this same barrel.
  • the inlet connector 35 is connected to the reservoir of a heat transfer fluid forming a static barrier which fills the interior of the envelope parts 33, 34, as well as the space between the exterior tubes 49 and the interior tubes. 46.
  • the inlet fitting can be used to adjust the volume of the intermediate fluid.
  • the outlet connector 36 is connected to a suitable draining means.
  • the transfer fluid can be a liquid metal, for example sodium or a mixture of sodium and potassium, lead, bismuth, lithium or a eutectic of lead and bismuth.
  • the intermediate fluid is static. Heat exchange by convection being practically nonexistent, the heat exchange is essentially by conduction and it is necessary that the intermediate fluid has a very good thermal conductivity. Consequently, the intermediate fluid is necessarily a liquid, and preferably a liquid metal.
  • the present invention relates to a vapor generator of the liquid metal-water type comprising a dynamic intermediate fluid, a gas instead of a liquid.
  • the steam generator of the invention is characterized in that the intermediate fluid circulates between the internal tubes and the external tubes, the evacuation chamber of the intermediate fluid being connected to the inlet of a small exchanger heat associated with this generator, the intermediate fluid inlet chamber being connected to the outlet of this same exchanger.
  • the steam generator is also characterized in that the intermediate fluid is a gas (or a mixture of gases) under chemically neutral pressure such as helium which effectively separates sodium from water-vapor and in that this gas circulates actively and thus ensures thermal transfers by convection.
  • the generator of the invention avoids having to resort to an intermediate sodium-sodium circuit. This therefore results in a significant simplification of the nuclear installation. Furthermore, it satisfactorily solves the main difficulty encountered in the production of a steam generator of this type, namely the separation of sodium and water effectively. We know that water and sodium react violently with each other; it is therefore necessary to prevent their mixing. The presence of a chemically pure and pressurized intermediate gas between water and sodium constitutes an effective barrier. The gas does not cause a large excess thickness of the tube which contains it. In addition, the pressure of the intermediate gas being roughly the average between that of sodium and steam, there is a happy staging for the proper use of structures and materials.
  • heat transmission it is the convection of the intermediate fluid circulating in the annular space which is the determining factor.
  • the heat transfer coefficient through this double wall compares favorably with that of pre-stressed double wall tube steam generators (Westinghouse, General Electric).
  • a tube generator prestressed is described in the journal “Nuclear Technology, vol 55, Nov. 1981”.
  • the circulation of the intermediate gas implies an external heat exchange because this gas carries a thermal power of the order of 6 to 7% of the total thermal power. This energy is effectively used as a heating supplement to the steam cycle and, more particularly, to the reheating of medium pressure steam after high pressure expansion.
  • the steam generator of the invention allows trapping of water leaks on the helium circuit and even its operation with moderate water leaks.
  • This concept with a small external loop allows better power adjustment possibilities, better operating conditions at partial load of the reactor.
  • the “small” intermediate circuit with gas circulation has variable speed blowers acting on the flow rate, means of pressure variation and regulation by-pass bypass, which is usual on such circuits. It can therefore be adapted to any level of operation and there are thus flexible means of action complementary to those existing on the one hand on the primary sodium circuit and; on the other hand, on the water-steam circuit.
  • the reheated HP vapor is maintained at an approximately constant temperature by helium, which avoids thermal transients and significantly reduces the decrease in the thermodynamic efficiency of the steam cycle.
  • the tube bundle can be produced with standard manufacturing and tolerance tubes. This represents a clear advantage compared to double-walled tubes with mechanical connection by prestressing which require special tolerances, therefore much more expensive tubes.
  • the materials used are common and well known, in particular as regards the internal water-vapor tube for which creep is not to be feared at its operating temperature of approximately 400 ° C.
  • the steam generator comprises four plates with tubes sotuted two by two on either side of the heat exchange zone. Namely, in the upper part of the generator, a first and a second plate and in the lower part a third and a fourth plate.
  • the intermediate fluid inlet chamber is delimited by the third and fourth tube plates while the intermediate fluid discharge chamber is delimited by the first and second tube plates.
  • the outer tubes are connected to the first and third tube plates, the inner tubes to the second and fourth tube plates.
  • An intermediate fluid intake pipe being connected to the casing in the intake chamber; an evacuation pipe being connected to the casing in the evacuation chamber.
  • Such a steam generator allows a better adjustment between the circulation and heat exchange conditions relating to both water-vapor and helium, the intermediate fluid on the one hand, the intermediate fluid and the liquid metal of somewhere else. It allows to better adapt the diameters of the water vapor and helium veins. Furthermore, it allows a reduction in the exchange length by increasing the diameters of the sodium-helium and helium-water tubes.
  • fins are provided in the annular space where the intermediate fluid circulates, which further reduces the exchange length.
  • each of the internal tubes can expand freely and individually as in the first embodiment, but especially in this configuration each external sodium-intermediate gas tube can also expand freely and individually. This feature improves the functional and mechanical reliability of the steam generator.
  • FIG. 1 a general view of a nuclear installation comprising a nuclear reactor cooled by a liquid metal, for example sodium.
  • a nuclear boiler such as, for example, that of the French Super Phoenix reactor has a primary sodium circuit, which includes the core of the reactor and transports the heat released by the latter in intermediate exchangers; a secondary circuit whose purpose is to avoid any interaction between the radioactive primary sodium and the water-vapor. This secondary circuit transports heat from the intermediate exchangers to the steam generators.
  • the boiler includes a water / steam circuit which starts from the generators and supplies the turbo-alternator groups.
  • the secondary sodium circuit does not exist.
  • Primary sodium is introduced directly into the steam generator in which it transmits most of its heat (92-93%) to the water to be vaporized.
  • the heart 10 is contained in a tank 11 filled with a liquid metal such as sodium.
  • the tank 11 is housed in a concrete tank well 12 forming part of the reactor building 16.
  • Pumps 18 send the primary sodium inside the steam generators.
  • the steam generators 15 are divided into four groups of several steam generators. Each group of generators is supplied by a primary sodium pump 18. After passing through the steam generators, the sodium returns to the tank 11 to return to the core 10 and the cycle resumes.
  • the turbine 22 comprises a high pressure stage 22a, a medium pressure stage 22b and a low pressure stage 22c. It drives an alternator 24.
  • the steam is sent via the pipe 23 into the high pressure stage 22a. At the outlet of this section, it is sent to a dryer 24 and then to a medium-pressure reheating 26 by steam extraction.
  • the steam then passes through a second medium-pressure reheating 30 which uses the heat of the intermediate fluid heated in the steam generator.
  • the steam is then directed to the medium pressure stage 22b of the turbine by the pipe 32, then to the low pressure stage 22c by the pipe 34.
  • the steam is condensed in the condenser 35.
  • a refrigerant atmospheric 38 constitutes the cold source 35 associated with the condenser 35.
  • the condensed water returns to the steam generator via the pipe 37. It can be seen that, in this figure, the pipe 37 ends at the top of the generator. It could however also be connected to its base.
  • the installation also includes a pressurized gas circuit with low thermal power (6 to 7% of total power).
  • this gas is helium.
  • This choice has several advantages: helium is chemically neutral. It does not react with sodium or with water. It does not require the use of steels different from those commonly used at the high operating temperatures of a generator of this type. It has good thermal and thermodynamic characteristics. Its thermal conductivity is significantly higher than that of air or carbon dioxide, its specific heat is more than four times that of liquid sodium, but its specific mass is 120 to 150 times lower.
  • Helium can be used on an industrial scale. Its flow places little stress on structures. In the case of its use in an auxiliary exchanger placed in a reactor vessel, one takes advantage of the advantage that it does not absorb the neutrons.
  • Helium is introduced at the base of the steam generator through line 25. It emerges at its upper part. It is brought to the medium-pressure superheater 30 by the pipe 27. In this superheater 30, which is the external exchanger associated with the generatur 15, the helium gives up the relatively small amount of heat which it has stored by passing through the generator 15. The cooled helium returns to the steam generator.
  • FIG. 2 a steam generator 1 produced in accordance with the invention, connected to a heat exchanger 30 which constitutes an apparatus which provides additional heat to the steam cycle, medium pressure steam reheating by means of the small intermediate helium circuit .
  • the steam generator comprises a casing 40 of cylindrical longitudinal shape with a straight section and having a vertical longitudinal axis X-X.
  • the envelope is closed at its upper part by a domed bottom 40a and at its lower part by a bottom 40b. It is divided into three parts along the longitudinal axis, namely a heat exchange zone between the first and second fluids, a first intake-evacuation zone for these two fluids, and a second inlet-outlet for these same fluids.
  • the admission-evacuation zones are located on either side of the exchange zone.
  • intake-exhaust zone is meant an area into which the fluids are introduced and / or discharged.
  • the reference 42a designates the first intake-exhaust zone, located at the top of the generator.
  • the central exchange zone is designated by the reference 42b.
  • the second intake-exhaust zone 42c is located at the base of the steam generator.
  • a generator such as that of the invention, which uses three fluids, there are three intake orifices and three evacuation orifices for these fluids, ie a total of six intake or evacuation pipes. These pipes are distributed between the two intake-exhaust zones 42a and 42c.
  • the sodium is brought via line 13 to the upper part of the exchange zone 42b. It circulates from top to bottom in this exchange zone before exiting at the bottom by the pipe 14 to return to the reactor core.
  • the intermediate gas that is to say helium
  • the helium flows from bottom to top against the current by compared to the heating fluid that is sodium. It is evacuated from the steam generator in zone 42a. It is led by the pipe 27 to the exchanger 30 in which it is cooled. The cooled helium is introduced again at the base of the steam generator after being recompressed by a blower 31.
  • the internal volume delimited by the envelope 40 is divided into several chambers by thick steel plates arranged perpendicular to the longitudinal axis X-X of the envelope and axially spaced. These plates delimit interior volumes separated from each other. These plates are pierced with distributed orifices, in which tubes are fixed.
  • the generator has four plates. First and second tube plates are arranged at the top of the generator.
  • the first tube plate 50 constitutes the limit between the central exchange zone 42b and the upper intake-evacuation zone 42a.
  • the second tube plate 52 is located above the first plate 50.
  • the plate 54 constitutes the limit between the central exchange zone 42b and the intake-evacuation zone 42c.
  • the plate 56 is located under the plate 54.
  • the plate 52 delimits with the upper bottom 40a of the envelope 40 an interior volume 58.
  • the plate 50 and the plate 52 axially spaced define between them a volume 60.
  • the plate 50 and the plate 54 delimit between them the volume 62 which constitutes the actual exchange zone.
  • the plate 54 and the plate 56 delimit between them a volume 64.
  • the plate 56 delimits with the lower bottom of the envelope a volume 68.
  • the steam generator also includes a bundle of tubes distributed in a cross section. More precisely, the tube bundle is made up of two series of tubes, a series of internal tubes and a series of external tubes arranged coaxially.
  • the upper end of each internal tube 70 is fixed to the plate 52. Its lower end is fixed to the tube plate 56.
  • the upper end of each external tube 72 is fixed to the tube plate 50.
  • the lower end of each external tube 72 is fixed to the tube plate 54.
  • Water is introduced into chamber 68 which forms a water box at the lower part of the generator via line 37; it enters the tubes 70 in which it flows from bottom to top (arrow 76) it emerges from the tubes 70 (arrow 78) in the form of vapor in the chamber 58 which constitutes an evacuation collector.
  • the intermediate fluid namely helium
  • the helium enters the annular space between the internal tubes 70 and the external tubes 72.
  • a wire 80 is wound in a spiral around the internal tubes 70. This wire has a function of centering the inner tube relative to the outer tube.
  • the resulting helix effect lengthens the path of the intermediate fluid, increases turbulence and therefore improves the heat exchange between the gas and respectively the sodium and the water-vapor.
  • This device can be replaced or supplemented by fins on the outer surface of the inner tube.
  • the hot helium is collected in the evacuation chamber 60 before being directed to the heat exchanger 30.
  • the hot sodium is brought via line 13 to the upper part of the exchange zone 42b. It is distributed around the internal ferrule 82 by means of an annular chamber 84. It crosses the ferrule 82 at its upper part and flows from top to bottom between the external tubes 72. At the lower part of the exchange zone 42b , the sodium passes under the shell 82; it is collected in the annular space 86 before being evacuated from the generator by the pipe 14.
  • the heat exchanger 30 is a conventional type exchanger. It comprises an outer casing 100 having a domed upper bottom 102 and a lower bottom 104 also domed. Inside the envelope 100 there is an upper tube plate 106 and a lower tube plate 108. The tube plate 106 defines with the bottom 102 an inlet chamber 110 for helium. The tube plate 106 and the tube plate 108 delimit between them a heat exchange zone between helium and the medium pressure vapor coming from the turbine. The tube plate 108 defines with the bottom 104 an evacuation chamber 114 for helium. Inside the envelope 100, between the plates 106 and 108 is a bundle of tubes 116. The tubes are fixed at one end to the plate 106 and at the other end to the plate 108.
  • the helium enters the interior of the tubes 116 (arrow 120). It runs through these tubes from top to bottom and exits at the bottom of the exchanger (arrow 122) in the evacuation chamber 114. Steam is introduced into the bottom of the exchange zone by the line 124. It flows between the tubes from bottom to top and exits at the top of the exchange zone via the pipe 126.
  • This description of the exchanger 30 is given only by way of example because this device is suitable for d other embodiments.
  • FIG. 5 a vertical sectional view of a second embodiment of a steam generator according to the invention and, in Figures 3 and 4, a schematic view which gives the principle of an elementary tubular cell.
  • Fig. 4 is a sectional view along line IV-IV of FIG. 3 of this tube shown on an even larger scale.
  • the internal volume delimited by the envelope 40 is divided into several chambers by thick steel plates arranged perpendicular to the longitudinal axis XX of the envelope and axially spaced. These plates delimit volumes separated from each other. They are pierced with distributed orifices in which tubes are fixed.
  • the generator comprises three plates arranged in a cross section of the envelope. These plates are respectively the plate 50, said first plate, to which is fixed one end of the external tubes 72, the plate 52, said second plate, to which is fixed one end of the internal tubes 70 and a third plate 130 more axially spaced from the central area as the plates 50 and 52.
  • the plate 130 is the upper bottom of the generator. It is surmounted by an extension of the cylindrical envelope 40.
  • the plate 130 and the plate 52 determine between them a chamber 58 for the evacuation of the steam.
  • the plate 50 and the plate 52 determine between them a helium evacuation chamber 60.
  • the first plate 50 determines, with the lower curved bottom 40b of the envelope, the volume 62 which constitutes the exchange zone of the steam generator.
  • the steam generator also has one or more small tube plates 133. These plates are much smaller in diameter than the plates 50, 52 or 130. In practice there are several identical plates 133. The plane of these plates is parallel to the longitudinal axis XX of the steam generator. They are located at the top of the latter on the side wall of the envelope 40. A water box 133a with its inlet pipe 37 is fixed to each plate 133.
  • the generator also has tube plates 134 much smaller in diameter than the plates 50, 52 or 130. They are located at the bottom of the generator and distributed over the wall of the envelope 40. A helium box 134a with its helium inlet pipe 25 is fixed to each plate 134.
  • the intake-evacuation zone 42a situated at the upper part of the generator extends substantially along its longitudinal axis to the first tube plate 50. Water is introduced into this zone.
  • the intermediate fluid, namely helium and vapor, are discharged into this area.
  • the central exchange zone 42b extends practically to the bottom bottom 40b of the exchanger.
  • Primary sodium is introduced at the top of this area.
  • the lower admission-evacuation zone 42c comprises the admission of helium via the line 25 and the evacuation of the primary sodium through the line 14.
  • this embodiment which relates to the concept of so-called “bayonet” tubes resides in the means which make it possible to bring the supply water from the top of the steam generator to the lower end of the zone d 'exchange. While in the embodiment of FIG. 2, these means consist of the tube plate 56 and the water box 68, arranged at the base of the steam generator, in the embodiment of FIGS. 3 to 5, the water is supplied from the upper part of the generator vapor at the bottom of each inner tube by a first tube 135 surrounded by a second tube 136. Each tube 135 has first and second ends. The first end is fixed to the tube plate 133 located at the upper lateral part of the casing 40 of the generator. Each tube 136 has a first and a second end.
  • the first end is fixed to the tube plate 130.
  • the second end of each tube 136 located at the bottom of the steam generator, is tightly connected to the second end of the tube 135 which it surrounds.
  • the walls of the tubes 135 and 136 delimit an annular space 138 opening at its upper part to the ambient air prevailing above the plate 130. This annular space is filled with a stagnant gas which constitutes an effective thermal insulation.
  • FIG. 4 an enlarged view in relation to FIG. 3 in section of a modular set of multiple tubes of the so-called “bayonet” plunger type presented in FIG. 3.
  • This assembly comprises four concentric tubes, respectively from the inside to the outside: the first tube 135, the second tube 136, the internal tube 70, the external tube 72.
  • the double tube constituted by the first and second tubes 135 and 136 expands freely at two ends. It is centered in the vapor stream by a helical wire (not shown) or other suitable means.
  • the internal tube may include fins 70a which have the purpose of increasing the heat exchange between the intermediate gas and the wall of the tube. The presence of fins makes it possible to shorten the length of the exchange zone 42a. Furthermore, the diameter of the inner tube 70 being larger, the exchange surface is increased. This is another factor which makes it possible to reduce the length of the exchange zone.
  • FIG. 5 an embodiment of the exchanger according to the principle set out with reference to Figures 3 and 4, but closer to an actual embodiment. While in fig. 3 there is shown only one dip tube with multiple walls on an enlarged scale, in order to distinguish the four tubes which constitute it, we have shown in FIG. 5 several of these tubes which constitute the bundle of the exchanger.
  • the bundle of tubes 136 is fixed to its upper part higher on the tube plate 130; the bundle of tubes 70 is fixed at its upper part to the tube plate 52; the bundle of outer tubes 72 is fixed at its upper part to the tube plate 50 and, at its lower part to the small side tube plates 134. Two of these plates have been shown in FIG. 5 but, in practice, they could be more numerous.
  • the water enters the upper part of the exchanger travels through the first tube in the vertical direction, from top to bottom, bypasses the end of the first and second tubes ( arrow 140 in fig. 3).
  • the steam generation stream is formed by the annular space between the tubes 70 and 72.
  • the vaporization is upward.
  • the evacuation of the steam is done from the top of the generator.
  • the air gap separating the water inlet tube and the vaporization stream plays the role of thermal insulation.
  • the sodium circulation is downward and external to the multiple tubes.
  • the circulation of helium is ascending.
  • the advantages of this embodiment are to allow a better adjustment between the circulation and heat exchange conditions relating to both water vapor and helium on the one hand, helium and sodium on the other go. It also allows a reduction in the exchange length by increasing the diameters of the sodium-helium and especially helium-water tubes. This leads to a reduction in the exchange length. This length is further reduced by the presence of fins.
  • the water supply tubes namely the tubes 135, can expand freely and individually.
  • the internal water / vapor tube 70 fixed at one end to the tube plate 52 and closed at its other end, can expand freely.
  • the external tubes 72 individually connected to the tube plates 134 by elbows can also expand freely and individually.
  • the use of the chemically neutral gas that is helium can extend to the cooling functions of the shutdown reactor, that is to say for the cooling of the primary sodium when the main pumps no longer operate.
  • the intermediate helium circuit of the steam generator described in the invention is connected as shown in FIG. 6, to an exchanger 150 designed to cool the reactor when it is stopped and placed in bypass on the pipe 27 for evacuating the intermediate fluid from the generator 15 and on the inlet pipe 25 for the intermediate fluid in this generator.
  • an exchanger 150 designed to cool the reactor when it is stopped and placed in bypass on the pipe 27 for evacuating the intermediate fluid from the generator 15 and on the inlet pipe 25 for the intermediate fluid in this generator.
  • a bypass of the intermediate helium circuit connected to a heat exchanger 151 placed in the reactor vessel can also be used together and others are possible.
  • helium has many advantages for this function. It is chemically neutral, leads to moderate heat exchange coefficients, therefore to transients and less severe thermal shocks. It does not activate under neutron radiation, it is easily purified. The final rejection of heat can be on water or on air. However, the exchanger will be more compact in the first case.

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EP84402629A 1983-12-21 1984-12-18 Générateur de vapeur sodium-eau à tubes concentriques droits et à circulation de gaz dans l'espace annulaire Expired EP0147304B1 (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
FR8320469A FR2557280B1 (fr) 1983-12-21 1983-12-21 Generateur de vapeur sodium-eau a tubes concentriques droits et a circulation de gaz dans l'espace annulaire
FR8320469 1983-12-21

Publications (3)

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EP0147304A2 EP0147304A2 (fr) 1985-07-03
EP0147304A3 EP0147304A3 (en) 1985-08-14
EP0147304B1 true EP0147304B1 (fr) 1987-07-15

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US (1) US4633819A (ja)
EP (1) EP0147304B1 (ja)
JP (1) JPS60155801A (ja)
DE (1) DE3464794D1 (ja)
FR (1) FR2557280B1 (ja)

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FR2995628A1 (fr) * 2012-09-19 2014-03-21 Alstom Technology Ltd Cycle de conversion d'energie par vapeur produite par un reacteur a neutrons rapides refroidi au sodium
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Also Published As

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DE3464794D1 (en) 1987-08-20
JPS60155801A (ja) 1985-08-15
EP0147304A3 (en) 1985-08-14
US4633819A (en) 1987-01-06
FR2557280A1 (fr) 1985-06-28
EP0147304A2 (fr) 1985-07-03
FR2557280B1 (fr) 1986-03-28

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