EP4390972A1 - Anlage mit mindestens einem kernreaktor und einer zumindest teilweise über dem reaktor angeordneten und mit einem wärmegitter verbundenen wärmespeichergrube - Google Patents

Anlage mit mindestens einem kernreaktor und einer zumindest teilweise über dem reaktor angeordneten und mit einem wärmegitter verbundenen wärmespeichergrube Download PDF

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Publication number
EP4390972A1
EP4390972A1 EP23217565.3A EP23217565A EP4390972A1 EP 4390972 A1 EP4390972 A1 EP 4390972A1 EP 23217565 A EP23217565 A EP 23217565A EP 4390972 A1 EP4390972 A1 EP 4390972A1
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EP
European Patent Office
Prior art keywords
reactor
pit
water
thermocline
circuit
Prior art date
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Pending
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EP23217565.3A
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English (en)
French (fr)
Inventor
Fabrice Bentivoglio
Jean-Baptiste DROIN
Clément LIEGEARD
Franck Morin
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Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
Original Assignee
Commissariat a lEnergie Atomique CEA
Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
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Publication of EP4390972A1 publication Critical patent/EP4390972A1/de
Pending legal-status Critical Current

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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D1/00—Details of nuclear power plant
    • 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
    • F28D20/00—Heat storage plants or apparatus in general; Regenerative heat-exchange apparatus not covered by groups F28D17/00 or F28D19/00
    • F28D20/0034—Heat storage plants or apparatus in general; Regenerative heat-exchange apparatus not covered by groups F28D17/00 or F28D19/00 using liquid heat storage material
    • F28D20/0039—Heat storage plants or apparatus in general; Regenerative heat-exchange apparatus not covered by groups F28D17/00 or F28D19/00 using liquid heat storage material with stratification of the heat storage material
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/24—Promoting flow of the coolant
    • G21C15/26—Promoting flow of the coolant by convection, e.g. using chimneys, using divergent channels
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D9/00—Arrangements to provide heat for purposes other than conversion into power, e.g. for heating buildings
    • 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
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/32—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core

Definitions

  • the present invention relates to the field of nuclear power plants, in particular those comprising pressurized water nuclear reactors (PWR). More particularly, it concerns the field of small so-called small or medium power reactors or SMRs in English (acronym for “Small Modular Reactor”), with a calogenic vocation.
  • PWR pressurized water nuclear reactors
  • the main objective of the invention is thus to greatly simplify the operation of a heat-producing PWR reactor which operates at low pressure, typically less than 15 bar and which is intended to provide a relatively low thermal power, of the order of a few tens of MWth.
  • the invention aims to achieve a coupling between a nuclear reactor and a heat storage to smooth the heat production of the reactor, until it can operate all year round at 100% of its power using the storage to manage the intermittent consumption of a low temperature heat network, typically below 100°C, for which the reactor is intended. It can be an urban, rural or industrial heating network.
  • SMR reactor we mean here and in the context of the invention, the usual technological meaning, namely a nuclear fission reactor, of smaller size and power than those of conventional PWR reactors, which is manufactured in a factory and transported to a nuclear installation site for installation.
  • the invention applies to any type of PWR reactor capable of being immersed in a water basin with its primary circuits and secondary to natural or forced convection.
  • SMR reactor we mean here and in the context of the invention, the usual technological meaning, namely a nuclear fission reactor, of smaller size and power than those of conventional REL reactors, a block of which is manufactured in factory and transported to a nuclear installation site for installation.
  • reactor block we mean here and in the context, the vessel, called the reactor vessel as well as all the components and part of the fluidic circuit, in particular the core of the reactor creating heat by nuclear fission reactions , which is housed inside the reactor vessel.
  • heat-producing we mean here and in the context of the invention, a nuclear installation, a nuclear power plant or a nuclear reactor whose power is mainly dedicated to the supply of heat.
  • the power of a heat-producing reactor can be 100% to provide heat. A small part of its power can still be used to provide electricity.
  • electrogenerating is meant here and in the context of the invention, a nuclear installation, a nuclear power plant or a nuclear reactor whose power is mainly dedicated to the supply of electricity.
  • the power of an electrogenerating reactor can be 100% to provide electricity. A small part of its power can still be used to provide heat.
  • pressurized water reactors are the most suitable for providing heat at relatively low temperatures.
  • boiling water reactors are intended to produce steam in a primary circuit directly operated in a turbo-alternator group in order to produce electricity.
  • FNR Fourth generation fast neutron reactors
  • graphite moderator and gas coolant reactors are intended to provide heat at relatively high temperatures.
  • a pressurized water nuclear reactor comprises three cycles (fluidic circuits) whose general principle of normal operation is as follows.
  • High pressure water from a primary circuit draws the energy provided, in the form of heat, by the fission of uranium nuclei, and where applicable plutonium, in the reactor core.
  • this water under high pressure and high temperature, typically 155 bars and 300 °C, enters a steam generator (GV) and transmits its energy to a secondary circuit, also using pressurized water as heat transfer fluid.
  • GV steam generator
  • the water from the secondary circuit is then condensed via a condenser using a third cycle, the tertiary or cooling cycle, as a cold source.
  • the envelope of the reactor building 1 can be made up of several thicknesses.
  • a reactor building 1 can consist of an exterior reinforced concrete wall 12, an interior concrete wall prestressed 10 separated from the exterior wall 12 by an annular space 13 devoid of material, and a metal skin 11 on the inside of the prestressed concrete wall 10, for a 1650 MWe reactor.
  • the number of loops can be three for a 900MWe reactor or 4 for a reactor of 1300 MWe and more.
  • the reactor building 1 is therefore sized, among other things, to house all of the components of the primary circuit 2.
  • FIG. 3 illustrates the energy transfer cycle (heat then electricity) of a PWR reactor.
  • the fluid connections between the interior and exterior of the reactor building 1 are provided by lines 30, 31 of the external circuit of the steam generators 23 towards the secondary circuit 3 comprising a turbine 32 connected to the electric generator 33, a condenser 34 , a food pump 35 and a heater not shown.
  • the reactor building 1 is crossed by a line called hot line 30 which evacuates the steam from the steam generator 23 to evacuate the power and bring it to the turbine 32, and by a so-called cold line 31 which supplies liquid water to the steam generator 23.
  • a pool reactor has generally been implemented on an experimental basis with a low power, typically 10 MWth: the pressure in the primary circuit can be close to atmospheric pressure, implying both moderate neutron fluences within the core, and the temperature of the primary circuit is limited and close to 100°C maximum.
  • the height of liquid water above the core makes it possible to slightly increase the primary pressure within the fissile core, while remaining within the order of magnitude of a few bars.
  • the advantage of such a reactor lies in the simplicity of design, the reactor vessel not being considered as an enclosure subject to pressure, the concrete vessel well and its watertight internal casing forming the reactor vessel surrounding the primary circuit.
  • the reactor also has significant thermal inertia, due to the importance of the water inventory in the primary circuit in relation to the power of the reactor, which also brings a gain in general safety with respect to -vis incidental transients, and driving. Finally, the thickness of the tank well and its absence of lateral or lower crossings ensures by design that it is impossible to drain the primary circuit, nor its depressurization. Such a pond reactor therefore meets many criteria of simplicity of design, safety in design, and ease of control.
  • An example of a heat-producing loop reactor is the Chinese HAPPY 200 reactor from the company SPIC, dedicated to district heating in the city of Beijing. With a unit power of 200 MWth, it is designed in batches of two units, thus equaling the performance of the aforementioned CNNC DHR400 project.
  • the reactor vessel is a self-supporting steel structure, designed in the factory and assembled on site, although with complete welding of the primary loop, thus requiring heavy site work.
  • the thermal power is evacuated from the core via two primary loops supplying plate exchangers, by forced convection using two pumps.
  • a pool of water surrounds the entire reactor vessel, but without direct contact due to a double envelope. In an accidental transient situation, this double envelope is flooded by the cold water present in the pool.
  • This loop reactor configuration thus has the advantage of being able to provide heat at a temperature relatively close to of that leaving the core, thanks to forced convection in the primary circuit, which facilitates the extraction of thermal power, and due to the presence of plate exchangers between primary and secondary circuits, which also allows a low thermal gradient between temperatures of the primary circuit and the secondary circuit.
  • the last category is that of so-called integrated reactors, which include a block delimited by a reactor vessel entirely produced in the factory and transported to site, and which houses the primary circuit in its entirety, and in particular the exchangers between primary and secondary circuits.
  • This type of integrated reactor has the same configuration as the main concepts of so-called SMR reactors currently existing, with an electrogenerating function, namely a configuration based on the integration of the steam generator, or even of all the components of the primary circuit in particular the pressurizer and the primary pumps, inside the reactor vessel.
  • SMRs are called integrated SMRs.
  • SMR reactors allow simplification of systems, mainly for safety purposes, and an increased capacity for modularity through significant manufacturing of components in the factory for transport to the construction site.
  • integrated SMRs have the advantage of no longer requiring overhead fluid lines in pressurized water, which considerably reduces the risk of accidents and associated consequences linked to the rupture of the primary circuit lines.
  • installation on site is greatly facilitated by limiting itself to secondary piping connections, apart from the connections of the volumetric and chemistry system of the primary circuit, which are of small diameter.
  • the nuclear power plant project with the acronym NUWARD TM is a power plant with an electrogenerating vocation, made up of two integrated SMRs, with a unit power equal to 170MWe, each of which includes a block housing all the components of the primary circuit at inside the reactor vessel.
  • Such an integrated SMR reactor whose block is generally designated under the numerical reference 4 comprises a fixed compartment 40 and a removable compartment 41 in the form of a cover, for the fuel handling or maintenance phases of the reactor internals.
  • a precursor concept for an integrated heat-producing reactor is the THERMOS project carried out jointly by the Applicant and the company Technicatome: [4].
  • the reactor according to this project had a thermal power of 100 MWth and was intended to supply urban heat to the city of Grenoble.
  • the reactor vessel integrates the entire primary circuit, thus allowing operation under a pressure higher than that of a tank reactor, necessary to provide urban heat close to 120°C.
  • the reactor vessel which was proposed was thus entirely assembled in the factory, and notably housed the exchangers between primary and secondary circuits in its upper part.
  • the low temperature gradient in the core required the presence of primary fluid pumping groups, arranged in the hot part, which is not ideal in terms of safety and ease of maintenance.
  • the thermal inertia of the primary and secondary circuits is relatively limited, the basin in which the reactor is immersed being thermally disconnected from the normal operation of the reactor, which is detrimental to operational safety and the smoothing of power call transients. power of the customer heating network.
  • the IRWST pool includes a pit forming the vessel well inside which the assembly consisting of the reactor vessel and the containment vessel is partially immersed.
  • This IRWST pool also serves as a cold source for sizing accidents.
  • This type of integrated reactor presents the same advantages of factory buildability and modularity, as those of integrated SMRs with generator function, in particular from the company NuScale Power.
  • Patent applications/patents can be cited here CN210069996U , CN113790469A , CN205388908U , US20120314829A1 , JP2003270383A , US4294311 , FR2322242B2 , FR2257869B1 , CN210123170U And CN105509121B which raise the possibility of such a coupling.
  • the patent US4294311 evokes the possible storage of heat from a nuclear reactor of the PWR type in a pit filled with a media, of the PTES type (Anglo-Saxon acronym “Pit thermal Energy Storage”) with layers of different temperatures separated by membranes in polyurethane. Not only does such a pit seem expensive to implement but, moreover, no real details are given on the coupling between the reactor and the PTES pit.
  • the aim of the invention is therefore to respond at least in part to this need.
  • a tank well placed on the ground involves forced convection circulation of tertiary water.
  • the pit is advantageously covered with a thermally insulating cover.
  • the pit is artificially dug into the ground and includes a sealing coating, preferably thermally insulating, covering its bottom and its side walls.
  • the covering is a membrane adapted to match the shape of the bottom and side walls of the pit.
  • the thermally insulating blanket or sealing coating may comprise one or more thermal insulation material(s) chosen from stainless steel, a polymer such as high density polyethylene (HDPE), or an elastomer.
  • a polymer such as high density polyethylene (HDPE)
  • HDPE high density polyethylene
  • the excavated or installed tank pit is preferably closed by a removable metal cover forming the separation wall with the volume of the pit.
  • the excavated or installed tank pit may include a concrete wall forming the separation wall with the ground and the volume of the pit.
  • the height He of the tank well excavated below the bottom of the pit is advantageously at least equal to 15m.
  • the reactor is a calogenous SMR type reactor.
  • the invention essentially consists of positioning a PWR type reactor at the bottom of a thermal storage pit delimiting a thermocline and thermally coupling them.
  • the tertiary circuit of the reactor is made up of the pit itself and one (or more) exchanger(s) with the secondary circuit whose inlet is fluidly connected in a cold temperature zone below the thermocline and the outlet is fluidly connected in a hot temperature zone above the thermocline so as to ensure natural or forced convection of the water in said tertiary circuit, whatever the season of the year and the call power of the heating network whose inputs and outputs are preferably connected respectively to the cold and hot temperature zones.
  • the heating network itself includes a circuit for pumping and discharging water and heat exchange with the network.
  • the installation as planned with its heat reactor is intended to supply urban heating networks, supply industrial processes such as desalination, desiccation, transformation of food products.
  • a complementary electrical production unit can also be added, using an organic Rankine cycle, to obtain local emergency electrical production in the event of ultimate need, complementary to the conventional battery park solutions generally used.
  • active means classified as emergency of the diesel combustion type.
  • primary water By “primary water”, “secondary water”, “tertiary water”, we mean the water which constitutes the fluid respectively of the primary, secondary and tertiary circuit.
  • temperatures, powers, volumes, flow rates, etc. indicated are for information purposes only.
  • other temperatures can be considered depending on the configurations in particular SMR reactor power, volume of water in the secondary basin, power requirement for the heating network, etc.
  • This reactor 4 has a unit power of 20 MW thermal, for heat generation purposes, that is to say dedicated to the supply of hot water, typically at 90°C. Its unit power can however vary upwards or downwards, in a range of approximately 10 MW to 100 MW, and the hot water supply temperature can also change.
  • the reactor 4 of central axis vertical cylinder This reactor vessel consists of a fixed compartment 40 and a removable compartment 41, above the reactor core for the fuel handling or maintenance phases of the reactor internals.
  • This removable compartment 41 is a cover in the form of a dome 5 whose central chimney integrates a rolling valve 64 adapted for cooling the reactor pressurizer as detailed below.
  • the core C of the reactor comprises a set of fuel assemblies 42 such as those conventionally used in PWR type reactors but with a fissile height adapted to obtain the desired total thermal power.
  • Each fuel assembly has several locations lacking fuel rods, replaced by absorbent rods which can move up or down in the assembly to control the reaction. Data from preliminary studies carried out by the Applicant consider a number of 52 assemblies and a lifespan of 10 years, with a fissile height of 1.5 m.
  • the metal envelope 40 houses in its lower part a cylinder 43 supporting a basket of assemblies usually designated under the name "core support basket”, dedicated to holding the fuel assemblies 42, and a separation envelope 40 with its peripheral neutron reflector 440 intended to ensure the maintenance of the neutron flux in the core.
  • Two flanges 45 are bolted between the fixed compartment 40 and the dome 41.
  • the seal between a flange 45 and each of the two compartments 40, 41 is advantageously ensured by a metal seal.
  • the dismantling of this flange 45 allows the complete handling of the fuel assemblies during the core reloading phases.
  • the studies carried out by the Applicant provide for outages for fuel reloading scheduled for ten-yearly inspections, without intervention on the core between these periods.
  • rod cluster guides 46 allow the insertion of nuclear reactivity control rods 42, in a manner similar to what is usually encountered in conventional PWR reactors.
  • the control bars 42 are rods made of neutron absorbing material.
  • the free volume above the reactor core C allows the completely extended positioning of the control rods 42, as well as the waiting position of so-called emergency absorbent rods, dedicated to the safety shutdown of the nuclear reaction.
  • a perforated plate with holes 48 is fixed, allowing the free passage of the hot primary fluid coming from the core through the holes 480, as well as the rods for controlling the movement of the rolling ring 481.
  • a regulating valve 481 for the water flow of the primary circuit also called flow lamination, is arranged.
  • This valve is in the form of a rolling ring 481 which matches the interior periphery of the compartment 45 of the tank and extends over a height between the plate 48 and the primary water outlet openings, making it possible to adjust the flow rate of the latter.
  • This rolling valve 481 has the function of regulating the natural circulation flow of the water from the primary circuit passing through the openings 400 which constitute the inlets of the primary water collectors of the exchangers 49 between primary and secondary circuit.
  • the positioning control of this regulation valve is carried out by an electric motor controlling the vertical movement of the control rod 482 linked to the crown 481, which is advantageously identical to those used by the control rods of the reactivity control bars 46 .
  • this regulation valve 481 allows the water from the primary circuit to completely pass through the openings 400, thus making it possible to maximize the heat exchange in the exchangers 49 between primary and secondary circuits, in order to evacuate the residual power and cool the primary circuit. This operation by gravity fall of this regulation valve guarantees reliability and safety in the event of electrical loss or reactor failure.
  • reactor 4 of figures 5 And 6 in normal operation, the thermal power created by the nuclear chain reaction within the reactor core is evacuated by the fluid of the primary circuit which rises by natural convection in an upward manner, to arrive in the upper part, where it can then flow along the different outlet openings 400 corresponding to the inlet collectors of the exchangers 49 between primary and secondary circuit and in an upper central portion of the core, in the form of a chimney.
  • This non-detailed central chimney, called a riser contains in addition to the control rod control mechanisms, the core parameter instrumentation sensors, and above the movement motors 47 of the reactivity control rods 42.
  • the separation envelope 44 of the core C makes it possible to separate the water, the fluid of the primary circuit, in its so-called cold and hot temperatures.
  • the primary water at cold temperature surrounding the core C inside the envelope 40 while the primary water at hot temperature, heated by circulating upwards in the core C, is found in the central portion upper part of the heart.
  • a separation plate 7 separating the interior of the dome 41 from the tank containing a pressurizer, from the riser.
  • This separation plate 7 contains a plate with through holes 70 making it possible to ensure the functions of thermal insulation and pressure differences of the integrated pressurizer.
  • This separation plate can be of the type already described in the request for patent WO2012/158929 A3 .
  • the water from the primary circuit passes through the openings 401 which constitute the primary water outlet collectors of the exchangers 49 then returns in a closed circuit towards the lower part of the reactor core .
  • the circulation in closed circuit P only by natural convection of primary water is symbolized by the white arrows in figures 5 And 6 .
  • the driving force of the primary circuit in natural convection is controlled by the difference in height between the average altimetric position of the exchangers 49 (primary cold source), and the average height of the fissile zone of the core C (primary hot source).
  • the adjustment of the primary water pressure is carried out by the rolling valve 481 whose control mechanisms are housed in one of the holes 480 of the plate 48.
  • the inlet and outlet temperature of the primary water is adjusted thanks to the conditions of neutron fluence, that is to say the thermal power of the core, by the positions of the reactivity control bars 42 in the core, and to the conditions of temperature and saturation pressure in the pressurizer.
  • the valve for rolling the primary water flow which sets the conditions of exchange circulation between primary and secondary circuits in relation to the power produced at the core.
  • the operation of the heat reactor can be controlled simply by controlling the pressure and temperature at the level of the pressurizer using the primary steam cooling system 6 and the heaters 8, and adjusting the circulation flow rate.
  • the exchangers 49 between the primary and secondary circuits are preferably plate exchangers, advantageously made of stainless steel, and designed to withstand the water pressure of the primary circuit.
  • these exchangers 49 are manufactured by stacking consisting of grooved metal plates assembled together either by hot isostatic compression (CIC) or by hot uniaxial compression (CUC) so as to obtain diffusion welding between the metal plates, or by brazing.
  • the flow is downward for the primary water, and upward for the secondary water.
  • the secondary circuit of this reactor 4 is not a closed loop circuit as in conventional PWR reactors, but includes a water basin B, as shown schematically in Figure Figure 11 .
  • This basin B is contained in the space of the reactor well reactor forming the third containment barrier, and the reactor vessel 4 is immersed therein.
  • This secondary circuit with liquid water basin B is an open environment delimited by the tank well, without a circulation pump.
  • the exchangers 49 are not integrated into the reactor vessel 40, 41 but arranged and fixed outside it.
  • Such an arrangement is possible because the improbable possibility of rupture of the primary water inlet or outlet pipes, thus causing a large diameter breach and loss of the latter, does not have significant accidental consequences for the reactor. .
  • the liquid water pool B completely envelops the reactor vessel 4, and an accident of this type cannot lead to a risk of dewatering of the core, endangering the physical integrity of the reactor core.
  • thermocline The internal circuit within an exchanger 49 which is part of the secondary circuit of the reactor 4 therefore sees a flow of liquid water pass as a secondary fluid which heats up on contact with the primary water within the exchanger 49, by natural suction from its inlet collector 490 at the bottom to their outlet collector 491 at the top thereof.
  • the secondary water then creates a greater volume at a so-called hot temperature.
  • the separation layer between a so-called cold temperature and the so-called hot temperature of secondary water is designated under the name of thermocline, as symbolized under the name thermocline 1 in Figure 6 .
  • the water basin B is configured to achieve vertical thermal stratification resulting in the formation of a thermocline delimited between the bottom of the basin at a cold temperature in which the reactor vessel 4 is submerged and the top of the basin at the warm temperature. It is the height of the thermocline layer which will set the cooling flow of the secondary circuit through the exchangers 49.
  • the closed circuit circulation S only by natural convection of the secondary water is symbolized by the gray arrows in figures 5 And 6 .
  • the flow rate by natural convection of the secondary water is adjusted by regulating valves 5 integrated in each of the outlet collectors 491 of the exchangers 49, as illustrated in Figure 9 .
  • the cold secondary water temperature is governed by the temperature conditions of the secondary water pool B.
  • the hot temperature is set by the control valves in the outlet collectors 491, and by the heat exchange within the exchangers 49 themselves.
  • FIG. 10A, 10B, 10C An example of integration of a control valve 5 in the form of a butterfly valve 5 50 in an outlet manifold 491 is shown in Figures 10A, 10B, 10C which show the valve in a position respectively fully open in which the maximum flow of secondary water from the basin can pass, intermediate, and a completely closed in which no flow can pass.
  • the butterfly 5 is rotated by the output shaft 51 of an electric motor 52.
  • the end of the shaft 51 opposite that linked to the butterfly 50 is linked to an offset flyweight 53.
  • the gravity fall of the flyweight 53 places the valve 5 in its fully open position so as to circulate the maximum flow of secondary water from basin B.
  • thermocline 1 is completely merged with the upper free level of secondary water basin B.
  • the driving height of secondary water circulation is then maximum due to the maximum weight of the water column cold supplying the inlets of exchangers 49.
  • the thermal power demand towards the primary circuit is then maximum, and the average temperature of the primary water drops.
  • the lowering of the temperature of the primary water leads to an average cooling of the moderator in the core, thereby inducing an increase in the reactivity of the core, and therefore an increase in its thermal power.
  • Maximum conditions for thermal heating of the secondary water volume are accompanied by a natural increase in core power, reactor 4 is therefore naturally stable.
  • the position of the primary water rolling valve combined with the positions of the reactivity control bar 42, however, makes it possible to limit the increase in the reactivity of the core, to remain within the temperature rise range of the entire reactor block 4 and its reactor well.
  • thermocline 1 drops in level, this implies an elevation of the secondary hot water layer, and therefore a drop in the driving height of secondary water through the exchangers 49 since the height of the cold water column decreases. Then, the circulation of secondary water by natural convection decreases, thereby reducing the exchange thermal between primary and secondary circuits.
  • the reduction in power evacuation leads to an increase in the average temperature of the primary water, and therefore an increase in the average temperature of the moderator in the core. There is therefore a decrease in reactivity through expansion of the moderator, and the neutron and thermal power produced decreases.
  • the reactor is therefore naturally stable for evacuation and thermal storage towards the volume of secondary water defined by basin B.
  • the volume of secondary water is dimensioned by the dimensions of the tank well on the one hand and by the height dedicated to the cold and hot zones of the secondary water on the other hand.
  • the volume of secondary water is of the order of 300 to 400 m 3 for the cold zone, and 100 to 150 m 3 for the hot zone, i.e. a total volume for basin B of between 400 and 550 m 3 .
  • thermocline 1 can only be maintained at a fixed position on the condition that there is a continuous withdrawal of a quantity of the secondary water at its warm temperature and replacement by the same quantity of water secondary to its cold temperature. This continuous sampling is detailed below in relation to the Figure 12 , so that there is a balance between the thermal power produced by the reactor core, and its extraction by this sampling and replacement.
  • the heat evacuated by the reactor can be stored, before its transport to a heat network, by a thermal storage pit.
  • the stability conditions described above make it possible to temporarily store the power produced by the reactor core by modifying the ratio between the secondary water and its temperature. cold and at its hot temperature, and by lowering the level of thermocline 1. After several minutes of operation, the continued evacuation of the thermal power produced by the reactor without an external escape, leads to the shutdown of the reactor, to evacuate only the residual power, through specifically dedicated residual power evacuation systems.
  • a continuous thermal power of 50 MW with secondary water supply at 90°C and return at 45°C, requires pumping of 270 liters per second, or 970 m 3 per hour from the hot water layer above above thermocline 1 and a return of the same quantity at the bottom of the reactor well.
  • this evacuation and this return can be implemented by means of piping coming from the upper part of the tank well, in order to avoid lateral connections likely to cause leaks or lateral mechanical strength problems restricting expansion. or earthquake resistance.
  • the primary circuit of the reactor operates solely by natural convection, that is to say without a pumping group.
  • the inventors then thought of modulating the thermal losses by conduction through the dome 6, to control the depressurization of the primary steam of the pressurizer, taking advantage of the fact that the metal envelope 60 of the cover 41 is thin, typically between 10 and 20 mm.
  • the steam cooling and condensation part comprises a double-walled dome 6 60, 61 spaced apart from each other forming a space E inside which liquid water from basin B can circulate from the bottom to the top of the dome forming a central evacuation chimney 62.
  • space E has a constant height of around 1 to 3 cm.
  • thermocline 1 In normal operation, the level of the thermocline 1 is fixed sufficiently above the pressurizer, in particular so as to be located above the central evacuation chimney 62, as illustrated in Figure 11 .
  • the liquid water which thus circulates solely by natural convection in the space E delimited by the two walls 60, 61, from a cold temperature below the thermocline 1, will condense the saturated vapor of the primary circuit inside of the tank and thus reduce the pressure within the tank.
  • the cold temperature of liquid water entering the space E at the bottom of the dome 6 is around 50°C, which allows effective and rapid cooling of the dome 6, and in particular of the internal wall 60 forming the enclosure mechanical resistance to the pressure of the primary circuit, and thereby the primary water vapor underlying it.
  • the central chimney 62 integrates within it a regulation valve 64 or in other words rolling valve which makes it possible to adjust the flow of secondary liquid water which circulates in space E and therefore to regulate the liquid cooling as such. Indeed, in a completely closed position of the valve 64, the layer of water is trapped and stratified in the space E. Conversely, in a position of opening, in particular completely, of the valve 64, the water hot rises naturally in space E then through the central chimney 62 and will join the upper hot water layer of basin B, while the cold water from basin B is sucked in through the entry in the low position of the double wall 60, 61.
  • a regulation valve 64 or in other words rolling valve which makes it possible to adjust the flow of secondary liquid water which circulates in space E and therefore to regulate the liquid cooling as such. Indeed, in a completely closed position of the valve 64, the layer of water is trapped and stratified in the space E. Conversely, in a position of opening, in particular completely, of the valve 64, the water hot rises naturally in space E then through the central chimney 62 and
  • Valve 64 can be a butterfly valve like secondary flow valve 5 illustrated in Figures 10A, 10B, 10C .
  • the two walls 60, 61 of the dome 6 are metallic, preferably stainless steel.
  • the external wall 61 of the dome 6 is advantageously covered with a cap 63 housing within it a thermal insulator.
  • the reactor 4 comprises, as a passive heat sink, a plurality of cooling fins 65 arranged inside the internal wall 60, being preferably distributed uniformly on the surface of the latter, of preferably welded or brazed.
  • These fins 65 thus increase the contact surface with the steam of the primary circuit and therefore make it possible to improve the heat exchange by conduction between said steam and the dome 6.
  • these fins 65 are rectilinear and extend over a major part of the height of the dome.
  • These fins 65 are preferably made of the same material as the walls 60, 61 of the dome 6, and typically have a thickness of a few cm and a length of a few tens of cm along the inside of the wall 60.
  • the heating part of the pressurizer comprises a plurality of electrical resistances 8 wrapped in an electrical insulator and powered by electrical cables, arranged inside the dome, preferably on the separation plate 7 which in its center comprises a portion with holes 70 allowing the functions of thermal insulation and pressure difference of the integrated pressurizer to be ensured.
  • a portion with holes 70 is for example as according to the device described in the application patent WO 2012/158929A3 .
  • the electrical resistances 8 can be of the type of those described in the patent US4135552 .
  • the inventors in order to smooth the heat production of reactor 4, until it can operate all year round at 100% of its power, the inventors have provided a thermal coupling between the latter and a thermal storage pit 9 filled with water delimiting a thermocline which will make it possible to manage the intermittent consumption of a heating network.
  • the inventors planned to position the reactor well 100 of the reactor 4 below the bottom of an artificially dug thermal storage pit 9, of the PTES type (Anglo-Saxon acronym for “Pit Thermal Energy Storage”), filled of water. As illustrated in Figure 12 , the positioning of the excavated tank pit 100 is in the middle of the pit 9 which is symmetrical in shape.
  • publication [6] which describes the creation of such a pit 9.
  • the bottom 90 and the side walls 91 of the pit are covered with a waterproofing coating in the form of a membrane (liner).
  • this membrane can be made of high density polyethylene (HDPE).
  • the pit 90 is covered with a thermally insulating cover 92 to limit thermal losses into the atmospheric air.
  • thermocline 2 is designated as thermocline 2 in Figure 12 .
  • the cold and hot temperatures of the heating network can be respectively equal to 45°C and 90°C.
  • thermocline 2 changes depending on the season and the related atmospheric and ground temperatures. More precisely, the position of thermocline 2 evolves rather to the first order as a function of the energy loaded and discharged voluntarily from the reactor 4 and/or to the heat network 300. Then, to the second order, it degrades naturally due to first of all the thermal conduction between the hot layer and the cold layer of thermocline 2, and also because of thermal losses to the outside which can actually depend on the season and the temperatures of the atmosphere. We specify here that the ground temperature varies very little and only has a marginal effect.
  • thermocline in a thermal storage tank.
  • the layer of cold water within pit 9 is minimal and the thermocline is at its lowest, as symbolized by the dotted line on the Figure 12 .
  • the tank well 100 excavated below the bottom 90 of the thermal storage pit 9 comprises a peripheral wall 101 of prestressed concrete internally coated with a metallic coating, preferably in the form of a stainless steel membrane.
  • a metallic coating preferably in the form of a stainless steel membrane.
  • Such a covering has the function of serving as a rigid structure for the reactor vessel 40, 41, 42 forming the third confinement barrier, and the prestressed concrete wall 101 has the function of responding to the pressure and temperature conditions of secondary water, and ensuring the physical integrity of the third barrier.
  • the assembly consisting of the reactor vessel 40, 41, 42 forming a reactor block 4 to which the exchangers 49 are fixed is supported by a metal base 102, preferably made of stainless steel, or of black steel coated with an anti- corrosion.
  • this base is held in the bottom of the tank well 100 by a mechanical locking system, not shown, adapted to prevent its movement and its lifting in the event of an earthquake.
  • the base 102 and the reactor block 4 which it supports can be lifted and brought to the top of the reactor well.
  • the mechanical locking system of the base must be able to be unlocked in a simple manner using tools accessible from the top of the tank well 100.
  • the base 102 which supports the reactor block 4 is rigidly connected to a foundation slab 103, and the metal covering with which the prestressed concrete wall 101 is covered is fixed rigidly and watertight to the slab 103.
  • the reactor 4 has a total physical impossibility of the occurrence of a serious accident, with significant melting of the core and perforation of the primary circuit tank. There is therefore no specific corium recovery device at the bottom of the reactor pit.
  • the tank well 100 is closed by a removable and waterproof cover cap 104, adapted to resist the pressure of the secondary circuit.
  • the cover cap 104 is a metal slab, mechanically welded, more preferably cellular or formed of boxes.
  • a gas sky 105 preferably nitrogen, is delimited by the free level of the volume of secondary water in the tank well 100.
  • This gas sky 105 makes it possible to control the secondary water pressure, to adapt the free level variations and secondary water expansion, and to prevent the presence of oxygen.
  • the mechanical connection between the metal lining of the tank well and the cover plug is constituted by a metal seal or a high temperature elastic seal, in order to maintain total tightness.
  • a pipe not shown with water circulation within it can be embedded in the concrete wall 101, at a distance close to the interior and the lining metal forming the third barrier.
  • the tertiary circuit of the reactor is constituted by the pit 9 itself and at least one exchanger 200 with the secondary circuit whose inlet 201 is fluidly connected in a cold temperature zone below the thermocline and the outlet 202 is fluidly connected in a hot temperature zone above the thermocline.
  • a heat network 300 has at least one inlet 301 which is fluidly connected to an area of the pit below the thermocline and at least one outlet 302 fluidly connected to an area of the pit above the thermocline.
  • a pipe 210 is connected to the inlet of the tertiary circuit of the heat exchanger 200 and its end 211 forming a withdrawal collector opens directly into the zone of the pit below the thermocline.
  • a pipe 220 is connected to the outlet of the tertiary circuit of the heat exchanger and its end 221 forming an injection manifold opens directly into the zone of the pit above the thermocline.
  • thermocline By considering the altitude of the withdrawal collector 211 in the zone below the thermocline, that is to say the lowest cold layer of the water of the pit 9, whatever the season, we guarantee a minimum driving height of water necessary for the establishment of natural convection of water in pit 9, that is to say in the tertiary circuit of the installation.
  • the closed circuit circulation T only by natural or forced convection of tertiary water is symbolized by the dotted arrows in Figure 12 . It is specified that this circulation T is shown in pit 9 for the purposes of clarity but that in reality the rising branch of the convection passes through the pipe 220 and that the descending branch does not exist as such, since it is a natural piston which advances over the entire section of thermocline 2.
  • a pipe 310 is connected to the inlet 301 of the heat network and its end 311 forming an injection manifold opens directly into the area of the pit below the thermocline.
  • a pipe 320 is connected to the outlet 302 of the heat network and its end 321 forming a withdrawal collector opens directly into the area of the pit above the thermocline.
  • the reactor installation configuration in storage pit 9 as shown in figures 12 And 15 allows circulation by natural convection.
  • the tank well 100 is installed partly below the bottom 90 of the swimming pool 9, that is to say with a tank well 100 excavated to a height He such that we can do without a pump, the pipe 210 supplying water from the pit 9 at its cold temperature opening into the bottom 90 of the pit.
  • the excavation height He can be between 16 and 18m.
  • thermo-hydraulic pre-sizing calculations on all of the primary, secondary and tertiary circuits of the installation according to the Figure 12 from thermomechanical calculation software. It may be a classic thermo-hydraulic software known under the name CATHARE:[8].
  • an exchanger pinch 49 is the minimum temperature difference between the primary water and the secondary water at a point of the given exchanger.
  • thermo-hydraulic operating parameters making it possible to pre-size the exchangers 49, and an estimate of the positioning of the latter vis-à-vis of the heart.
  • an estimated volume of exchangers 49 can be established, with installation at a minimum height of 3.16 m relative to the average altitude of the fissile zone.
  • the primary water pressure of 4 bars is determined such that the boiling margin with respect to the average core outlet temperature is 20°C.
  • the reactor vessel 40, 41 of the reactor block 4 has an overall height of approximately 9 m, with an overall diameter of 3 m integrating the main shell 42 with a diameter of the lower compartment 40 of the vessel of 2.74 m and a diameter of the upper compartment 41 of 2.15 m.
  • a number of three identical exchangers 49 is retained with for each a useful heat exchange volume of approximately 1.2 m 3 and an exchange height between primary circuits and secondary of 2m.
  • the three exchangers 49 are fixed with their collectors 400, 401, 490, 491 at 120° from each other to the compartments 40, 42 of the reactor vessel.
  • the thickness of the reactor vessel is not dictated by considerations of resistance to pressure since it is immersed in the secondary water of basin B, but rather by constraints of mechanical rigidity, resistance to buckling and heart support. An average thickness of around 20 mm is therefore retained. We recall here that the primary pressure is lower than the secondary pressure.
  • the material envisaged for the reactor vessel 4 and the exchangers 49 is stainless steel.
  • CAD Computer-aided design
  • the average temperature of secondary water is around 85°C, which is lower than the boiling temperature of water in the atmosphere.
  • the volume of primary water is of the order of 30 m 3 , or approximately a factor of 10 lower than that of the volume of secondary water.
  • the following table 2 illustrates the characteristics of the thermo-hydraulic sizing of secondary and tertiary circuits.
  • the CAO indicates a number of three 200 interchanges, which could be reduced to two, for reasons of economic optimum.
  • the operating conditions are therefore substantially identical to those governing the circulation of primary water.
  • a number of three identical exchangers 200 are retained, each with a useful heat exchange volume of approximately 1.1 m 3 and an exchange height between secondary and tertiary circuits of 1.7 m.
  • the pinch in an exchanger 200 is increased compared to that of an exchanger 49 due to the temperature difference between the layer of cold water at 35°C in pit 9, and the layer of hot water at 90° vs.
  • the driving height of natural convection of secondary water is at least 2.7 m, which sets the maximum altitude position of thermocline 1.
  • the minimum driving height necessary for the establishment of natural convection of tertiary water corresponds to the difference in altimetry between the median position of an exchanger 200, and the position of the separation thermocline between cold layer and hot layer in pit 9. This thermocline evolves seasonally and at the end of the summer period, before the supply of heat to the network 300 is started, the cold water layer is minimum and as is already apparent from the above, the conservative value chosen is the altitude of the withdrawal collector 211 of the tertiary water.
  • the pre-sizing carried out is based on the minimization of pressure losses allowing the establishment of natural convection at moderate driving height.
  • the minimum calculated height is of the order of 2 m, which allows compact installation, despite the cumulative conditions of natural convection of the primary, secondary and tertiary circuits which lead to relatively deep burial of the reactor block 4.
  • the level of the invert 103 of the tank pit is located approximately 50 m above the ground, when the tank pit 100 is completely excavated, that is to say buried completely below the bottom 91 of the pit 9.
  • the bottom of pit 9 is 32 m from the ground surface. In the hypothesis of a deeper pit 9, for example 40 m, the depth of the raft would then be closer to 60 m, because of the need to establish natural convection of tertiary water.
  • Water injections into thermal storage pit 9 and withdrawal to reactor 4 are planned to have constant flow rates all year round corresponding to operation of the reactor at 100% power.
  • the outward and return flow rates of the heating network 300 are variable depending on the power demand of the network. Variations in hydrostatic head in pit 9 during the year may require the addition of a device to regulate the withdrawal flow to the reactor to keep the latter constant.
  • the different collectors for withdrawal 211 or injection 221 of tertiary water or withdrawal 321 and injection 311 of the heat network 300 can be produced according to a preferred configuration.
  • the exchanger 200 between secondary and tertiary circuit is shown in Figure 12 inside the pit 9.
  • the exchanger(s) 200 is(are) arranged outside the secondary water volume, more preferably behind the tank well 100 in the concrete wall 101, as illustrated in Figures 16 and 16A , with an isolation valve 212 on each inlet and outlet pipe, in order to be able to isolate the secondary circuit and complete the sealing of the third radioactive containment barrier.
  • thermosyphon any PWR reactor with water flow rates in the primary and secondary circuits generated by pumps, that is to say according to forced convection or by a thermosyphon may be suitable for coupling by its tertiary circuit in natural convection with a thermal storage pit filled with water as described previously.

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  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
EP23217565.3A 2022-12-20 2023-12-18 Anlage mit mindestens einem kernreaktor und einer zumindest teilweise über dem reaktor angeordneten und mit einem wärmegitter verbundenen wärmespeichergrube Pending EP4390972A1 (de)

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FR2214004A FR3143826A1 (fr) 2022-12-20 2022-12-20 Installation comprenant au moins un réacteur nucléaire et une fosse de stockage thermique agencée au moins en partie au-dessus du réacteur et reliée à un réseau de chaleur.

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Citations (14)

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US4135552A (en) 1975-10-21 1979-01-23 Westinghouse Electric Corp. Pressurizer heaters
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CN216957473U (zh) * 2022-01-29 2022-07-12 山东核电有限公司 一种含有储能功能的核电厂灵活性综合利用装置***

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