Electricity generation installation comprising a thermal power plant, in particular nuclear, with a thermal energy-to-electrical energy conversion system (CES), and at least one exothermic chemical production unit of which at least part of the high-temperature and / or low-temperature waste heat is reinjected into the installation's CES system.
The integration of a closed-loop heat exchanger system for reinjecting waste heat from synthetic fuel production units into the nuclear power plant's thermal energy conversion system improves energy efficiency and safety in combined electricity and fuel production systems.
Patent Information
- Application Number
- FR2024006736
- Authority / Receiving Office
- FR · FR
- Patent Type
- Applications
- Current Assignee / Owner
- Filing Date
- 2024-06-21
- Publication Date
- 2025-12-26
AI Technical Summary
Existing installations combining nuclear reactors with hydrogen production units and synthetic fuel production units are not optimal in terms of energy efficiency, particularly in the use of waste heat for high-temperature electrolysis and exothermic synthesis reactions.
Implementing a closed-loop heat exchanger system for indirect thermal coupling, reinjecting high-temperature and low-temperature waste heat from synthetic fuel production units back into the thermal energy-to-electrical energy conversion system of the nuclear power plant, using a Rankine cycle with specific heat exchangers and fluidic circuits to optimize energy transfer.
Enhances overall energy efficiency of electricity, heat, and synthetic fuel production, ensuring safety and independence from the electrical grid, while maintaining stable operating conditions for the nuclear reactor, hydrogen production unit, and synthetic fuel production unit.
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Abstract
Description
Title of the invention: Electricity generation installation comprising a thermal power plant, in particular nuclear, with a thermal energy to electrical energy conversion system (CES), and at least one exothermic chemical production unit of which at least part of the high temperature and / or low temperature waste heat is reinjected into the installation's CES system. technical field
[0001] The present invention relates to the field of electricity generation installations from a thermal power plant.
[0002] By "thermal power plant", we mean here and within the framework of the invention, any power plant generating heat for the production of electricity and which operates from a heat source according to the principle of thermal machines and which includes a system for converting the thermal energy from the heat source into electricity (SCE).
[0003] A thermal power plant according to the invention can be: - a nuclear power plant comprising a steam turbine; - a combustion power plant, also known as a "flame" power plant, comprising a boiler (coal, fuel oil, gas or biomass) and a steam turbine or comprising an internal combustion engine (fuel oil, gas, etc.) and a gas turbine, a diesel engine or a combined cycle engine combining a gas turbine and a steam turbine; - a power plant recovering pre-existing heat (solar thermal, geothermal steam, etc.) including a steam turbine, - a power plant with at least one salt reservoir heated by an electrical resistance, including a steam turbine; - a power plant or any other decarbonized heat source whose characteristics, particularly temperature, allow conversion into electricity.
[0004] A nuclear power plant suitable within the scope of the invention may consist of one or more light water nuclear reactors (LWRs), in particular pressurized water reactors (PWRs) with conversion cycle inlet temperatures of approximately 300 °C, or boiling water reactors (BWRs), or one or more fourth-generation reactors (GEN IV), in particular as small modular reactors (SMRs) or nuclear reactors. Advanced (AMR for "Advanced Nuclear Reactors"), with conversion cycle inlet temperatures exceeding 500 °C. These may be fast neutron reactors cooled with liquid metal, notably liquid sodium, known as SFR (Sodium Fast Reactor), which belongs to the GEN IV reactor family.
[0005] The installation according to the invention can be a cogeneration installation, i.e. the simultaneous or non-simultaneous production of electricity and heat.
[0006] Hydrogen production within the framework of the invention can be carried out by high-temperature water electrolysis (HTE, or EVHT for high-temperature steam electrolysis, or HTE, English acronym for "High Temperature Electrolysis", or HTSE, English acronym for "High Temperature Steam Electrolysis") also with solid oxides (SOEC, English acronym for "Solid Oxide Electrolysis Cell"), or by alkaline electrolysis or by proton-exchange membrane electrolysis (PEM for "Proton - Exchange Membrane") or by anion-exchange membrane electrolysis (AEM for "Anion-Exchange Membrane").
[0007] The production of at least one synthetic fuel by exothermic chemical reaction can be achieved by a reverse water-gas shift (RWGS) process and / or a Fischer-Tropsch (FT) process, and where appropriate by a reforming process to produce a synthetic fuel, such as kerosene, methane, or to produce methanol, ammonia, etc. Reforming allows the recycling of fractions including carbon chains below C5 to maximize the production of the fraction of interest. Kerosene comprising C8-Ci6 carbon chains is typically obtained after distillation at atmospheric pressure.
[0008] Although described with reference to a pressurized water nuclear reactor power plant, the invention applies to any other thermal power plant as previously mentioned comprising a thermal energy-to-electricity (TEE) conversion cycle, in particular a Rankine cycle. Previous technique
[0009] In the context of climate and energy transition, the nuclear industry must meet several challenges for the future. Indeed, to address tomorrow's energy and societal challenges, it will be necessary to design nuclear reactors that enable:
[0010] - to limit the need for a so-called "environmental" liquid cold source (rivers, rivers, sea) and associated discharges into the environment;
[0011] - to be more flexible and therefore more complementary to other so-called energies renewables (RES), to meet fluctuating electricity demand and the intermittency of RES;
[0012] - to decarbonize processes by supplying heat to industries energy consumers (desalination, heat networks, hydrogen...) while increasing energy efficiency;
[0013] - to capture atmospheric CO2 to limit the effects of warming climate and contribute to closing the carbon cycle as a source of carbon for industrial processes;
[0014] and this without degrading the profitability of the installation, either by economically benefiting from the new services provided, or by significantly increasing the amount of electricity produced during the day.
[0015] Recently, many studies have highlighted the possibility of combining nuclear power reactors with hydrogen production units from high-temperature water electrolysis, in order to create cogeneration plants that efficiently produce electricity and hydrogen: [1], [2].
[0016] The electrolysis of water is an electrochemical reaction that decomposes water into dioxygen and dihydrogen gas with the aid of an electric current according to the reaction:
[0017] H2O H2 + ' / 2 O2.
[0018] To carry out the electrolysis of water, it is advantageous to carry it out at high temperature typically between 600 and 950°C, because part of the energy required for the reaction can be supplied by heat, which is cheaper than electricity, and carrying out the reaction is more efficient at high temperature and finally it may not require a catalyst.
[0019] To implement high-temperature electrolysis, it is known to use a reactor, also called a SOEC (Solid Oxide Electrolysis Cell) type electrolyzer, consisting of a stack of elementary units, each comprising a solid oxide electrolysis cell made up of three anode / electrolyte / cathode layers stacked one on top of the other, and interconnecting plates, for example made of metallic alloys, also called bipolar plates, or interconnectors. The function of the interconnectors is to ensure both the passage of electric current and the circulation of gases in the vicinity of each cell (injected steam, hydrogen and oxygen extracted in an EHT electrolyzer) and to separate the anodic and cathodic compartments, which are the gas circulation compartments on the anode and cathode sides of the cells, respectively.To perform high-temperature steam electrolysis (HTE), water vapor (H2O) is injected into the cathode compartment. Under the influence of the current applied to the cell, the dissociation of water molecules into vapor occurs at the interface between the hydrogen electrode (cathode) and the electrolyte: this dissociation produces dihydrogen gas (H2) and hydroxide ions (OH). The dihydrogen is collected and discharged from the hydrogen compartment. The hydroxide ions (OH) migrate through the electrolyte and recombine into dioxygen at the interface between the electrolyte and the oxygen electrode (anode).
[0020] To increase the flow rates of hydrogen and oxygen produced, it is known to stack several elementary electrolysis cells one on top of the other, separating them by interconnecting devices, usually called interconnectors or bipolar interconnecting plates. The assembly is positioned between two end interconnecting plates that support the electrical and gas supplies of the electrolyzer (electrolysis reactor).
[0021] A high-temperature water electrolyzer (HTW) thus comprises at least one, generally a plurality of electrolysis cells stacked one on top of the other, each elementary cell being formed of an electrolyte, a cathode and an anode, the electrolyte being intercalated between the anode and the cathode.
[0022] In steady-state operation, a high-temperature electrolyzer (HTE) requires upstream a combined input of thermal and electrical power to bring the reactants to the temperature required for electrolysis and within itself an input of electrical power to carry out the electrolysis.
[0023] The applicant proposed in the patent application filed on December 21, 2022 under number FR2214108 and entitled "Light Water Reactor (LWR) Nuclear Cogeneration Plant and High Temperature Water Electrolysis System(s) for Hydrogen Production from Heat of LWR Reactor", an optimal indirect thermal coupling, i.e. without any mass transfer, between a nuclear reactor and a high temperature electrolysis hydrogen production unit by means of a judiciously chosen withdrawal tap downstream of the high pressure body of the Rankine cycle turbine of the nuclear reactor which will transfer the heat thus withdrawn, via a closed loop between an intermediate heat exchanger and a coupling steam generator, to liquid water supplying the production unit in order to inject steam at a high temperature required to carry out the electrolysis.This indirect heat input can be continuous or gradually reduced until the heat released by the electrolysis reaction is sufficient to power it. This application also includes a heat reinjection coupling circuit into the reactor's tertiary circuit, which allows for the recovery of at least some of the waste heat, namely the heat recovered from the electrolysis outlet gas cooling system. and which was not used for this purpose. The reinjected waste heat can be considered to be in a low temperature range, as it is typically between 80°C and 150°C.
[0024] The inventors were interested in the possibility of creating an integrated energy installation with a nuclear reactor and a synthetic fuel production chain, in particular kerosene.
[0025] Synthetic fuels can be obtained through thermochemical processes, by different conversion routes, from energy vectors heat and electricity and raw materials such as water and CO2.
[0026] US20130281553A1 describes the production of synthetic fuels coupled with a A dedicated nuclear reactor combines carbon dioxide and hydrogen to produce synthetic gas, which is then converted into a product of interest. The hydrogen and carbon dioxide are obtained through electrolysis and carbon capture processes, respectively. Fuels can be produced, in particular, by the Fischer-Tropsch process. The described coupling demonstrates the advantages of integrating a chemical production plant with a nuclear reactor to provide the electrical and thermal energy required for the various processes. Furthermore, this patent application explores the possibility of using the absorbent solution employed for carbon dioxide capture to cool the nuclear reactor.
[0027] Other publications mention more precisely the coupling between a nuclear reactor and a synthetic fuel production process.
[0028] Publication [3] thus discloses the possibility of using the steam generated by a light water nuclear reactor (LWR) in an electrolysis unit and in post-treatment units such as distillation and hydrotreatment.
[0029] Publication [4] also refers to the supply by a nuclear reactor of the steam and electricity needed for a high-temperature electrolysis unit as well as the electricity needed for the various units of a synthetic fuel production system.
[0030] All these coupling solutions between a nuclear reactor, a high-temperature electrolysis unit whose necessary electricity is supplied by the nuclear reactor and at least one synthetic fuel production unit from the hydrogen produced by the electrolysis unit are not optimal, in terms of energy efficiency.
[0031] There is therefore a need to improve the installations for generating electricity by nuclear reactor(s) and for the simultaneous or non-simultaneous production of a synthetic fuel from the heat supplied by the nuclear reactor(s) and hydrogen supplied by an electrolysis unit of the installation, improving their energy efficiency.
[0032] More generally, there is a need to improve the energy efficiency of an installation comprising a thermal power plant, a thermal energy to electrical energy conversion system (CES), at least one electrolysis unit whose electricity is supplied by the CES system and at least one chemical production unit for at least one synthetic fuel whose heat is supplied by the thermal power plant and whose hydrogen is supplied by the electrolysis unit.
[0033] The object of the invention is to meet at least partially this need(s). Description of the invention
[0034] To this end, the invention relates, in one of its aspects, to an electricity generation installation, intended to produce electricity and, where applicable, heat, comprising:
[0035] - a thermal power plant, with a thermal energy conversion system into electrical energy (SCE);
[0036] - at least one electrolysis unit, electrically connected to the SCE system and capable of being thermally coupled to the thermal power plant by a fluidic circuit, so as to be supplied respectively by the electricity and heat necessary for the electrolysis reaction;
[0037] - at least one production unit of at least one synthetic fuel or a organic chemical compound, adapted to carry out at least one exothermic synthesis reaction; the production unit being connected to the electrolysis unit by a fluidic circuit and so as to be supplied by hydrogen;
[0038] - at least one fluidic circuit, called a high-pressure reinjection coupling circuit temperature and / or low temperature, to thermally couple the output of the production unit to at least part of the SCE system so as to reinject at least part of the so-called high temperature and / or low temperature waste heat produced by the exothermic synthesis reaction into the SCE system.
[0039] The heat transfer fluid of the high-temperature reinjection coupling circuit is preferably at a temperature of at least 150°C, advantageously between 200 and 300°C, advantageously between 215 and 275°C.
[0040] The heat transfer fluid of the low-temperature reinjection coupling circuit is preferably at a temperature of at least 80°C, advantageously between 80 and 150°C, advantageously between 80 and 100°C.
[0041] According to an advantageous embodiment, - The SCE system implements a Rankine cycle comprising: at least one steam generator, at least one turbine comprising a high-pressure casing connected to the steam generator and a low-pressure casing connected to the high-pressure casing by at least one fluidic branch, a high-pressure heater connected to the high-pressure body, to a water tank (called a food-grade tank), and to the steam generator, a low-pressure heater connected on one side by at least one fluid branch to the low-pressure body and on the other side by at least one fluid branch to the feed tank, a condenser, connected on one side to the low-pressure body and on the other side to the low-pressure heater; The high-temperature reinjection coupling circuit includes: a heat exchanger connected on one side in a closed loop to the outlet of the production unit of at least one synthetic fuel and on the other side at the inlet to the high-pressure body and at the outlet to the low-pressure body,
[0042] and / or a heat exchanger connected on one side in a closed loop to the outlet of the production unit of at least one synthetic fuel and on the other side upstream of the high-pressure heater and at the outlet to the steam generator,
[0043] and / or a heat exchanger connected on one side in a closed loop to the outlet of the production unit of at least one synthetic fuel and on the other side at the inlet to the high-pressure body and at the outlet to the high-pressure heater,
[0044] and / or a heat exchanger connected on one side in a closed loop to the outlet of the production unit of at least one synthetic fuel and on the other side at the inlet to the low-pressure body and at the outlet to the low-pressure heater,
[0045] and / or a heat exchanger connected on one side in a closed loop to the outlet of the cooler and on the other side at the inlet between the condenser and the low pressure heater and at the outlet between the low pressure heater and the food storage tank.
[0046] According to another embodiment, the installation further comprises at least one direct carbon dioxide capture (DAC) unit, connected to the production unit of at least one synthetic fuel by a fluidic circuit and thermally coupled to the thermal power plant by a fluidic circuit so as to respectively supply CO2 is needed for the exothermic synthesis reaction in the production unit and must be supplied with heat necessary for the direct capture of CO2.
[0047] According to another embodiment, the installation further comprises, at the outlet of the cooler, a low-temperature preheater for the electrolysis unit and, where applicable, a low-temperature preheater for the direct carbon dioxide (DAC) capture unit,
[0048] Advantageously, the synthetic fuel production unit is adapted to implement a reverse water gas shift (RWGS) process and / or a Fischer-Tropsch (FT) process and, where appropriate, a reforming process.
[0049] Advantageously still, the SCE system implements a Rankine cycle including an alternator adapted to supply at least part of its electricity to the electrolysis unit and, where appropriate, to the direct carbon dioxide capture (DAC) unit.
[0050] The electrolysis unit is preferably a high-temperature electrolysis unit.
[0051] The invention essentially consists of implementing at least one closed loop at heat exchanger to achieve indirect thermal coupling by return of waste heat at least at high temperature and / or at low temperature, to a thermal power plant with its heat-to-electricity conversion system, of a production unit of at least one synthetic fuel whose necessary hydrogen is supplied by a hydrogen production unit by electrolysis itself thermally coupled with the thermal power plant.
[0052] By "indirect" we mean here and within the framework of the invention the fact that there is no mass transfer between the cycles of the thermal power plant and the production unit of at least one synthetic fuel, and therefore that the heat transfer takes place through heat exchangers.
[0053] In other words, according to the invention, the high-temperature and / or low-temperature thermal discharges from the production unit of at least one synthetic fuel are at least partly reinjected into the SCE system of the thermal power plant.
[0054] In conclusion, indirect thermal coupling with reinjection of waste heat from the production unit of at least one synthetic fuel offers a number of advantages, including: - an overall energy efficiency of the combined electricity, heat and synthetic fuel installation (where applicable) produced from hydrogen by high-temperature electrolysis that is greater than or at least equal to existing solutions, - the safety of a thermal power plant, in particular an unmodified nuclear reactor, - the absence of risk to the overall installation, - operating conditions of the nuclear reactor, the hydrogen production unit and the synthetic fuel production unit which can remain the same and independent of each other; - the possibility of producing synthetic fuels or electrofuels, known as "e-fuels", independently of an electrical grid.
[0055] Other advantages and features of the invention will become clearer from the detailed description of examples of implementation of the invention given by way of illustration and not limitation with reference to the following figures. Brief description of the drawings
[0056] [Fig-1] [Fig.1] is a schematic view of a cogeneration plant according to the invention of a pressurized water reactor (PWR) thermally coupled with a high-temperature electrolysis unit and a synthetic fuel production unit whose waste heat is reinjected into the nuclear power plant's conversion system (CSS), [Fig. 1] showing the thermal couplings on the CSS side.
[0057] [Fig.2] [Fig.2] is a schematic view illustrating the EHT electrolysis units, of direct CO2 capture and synthetic fuel production of the installation according to [Fig.1], [Fig.1] showing the thermal couplings on the unit side.
[0058] [Fig.3] [Fig.3] illustrates two nuclear installation configurations depending on the state of the art and two configurations of a nuclear installation according to the invention, as illustrated in figures 1 and 2.
[0059] [Fig.4] [Fig.4] shows, in the form of a bar chart, the yields energy values of the different configurations of [Fig.3], calculated from a nuclear reactor with a power output of 100 MW. Detailed description
[0060] Throughout this application, the terms "inlet", "outlet", "upstream", "downstream" are to be understood by reference to the direction of flow of a heat transfer fluid within one of the fluidic circuits, symbolized by an arrow, of an installation according to the invention.
[0061] The points A to P of the different fluidic lines concerned in [Fig.1] are symbolized by circles.
[0062] Figures 1 to 2 show a nuclear installation with a PWR reactor according to the invention.
[0063] The primary circuit 1 is a closed-loop fluid circuit comprising mainly the reactor core 2, a heat exchanger 3 as a steam generator (SG), and a hydraulic pump 4 for circulating the heat transfer fluid which is water changing from liquid to vapor, typically around 300°C at high pressure, typically around 150 bar, in normal operation.
[0064] Other equipment, such as a pressurizer and all the devices enabling operation under the required safety conditions, are not described here.
[0065] The secondary circuit 10 is a thermal energy to electrical energy conversion system (TEE) which mainly comprises a turbine 6 consisting of a high-pressure body 60 and a low-pressure body 61 connected to the high-pressure body 60 by a fluid branch 62, a condenser 7 connected to the low-pressure body 61 by a fluid branch 63 and a hydraulic pump 80 to circulate water in liquid form as a heat transfer fluid.
[0066] Thus, in this circuit 10, the water in the form of steam is expanded in the high-pressure body of the turbine, then superheated before continuing its expansion in the low-pressure body 61. The turbine drives an alternator 9 which produces electricity.
[0067] The water from the secondary circuit is then condensed via the condenser 7, as a so-called "cold" source.
[0068] The steam generator 3 produces steam for the high and low pressure bodies 60, 61 of the turbine 6, which is characteristic of a Rankine cycle with the operating modalities of a generator cycle of the installation and must be able to operate according to the needs of an electrical network.
[0069] The steam generator 3 is typically sized to remove 1.5 times the power of the nuclear reactor. It is specified that the turbine housings 60, 61 are sized based on the peak steam flow rate produced by the steam generator 30.
[0070] The hydraulic pump 4 is designed to operate at least at the availability coefficient Kd of the nuclear reactor and must be able to operate according to the fluctuations in the electricity requirements of the electrical network to which the alternator 9 of the nuclear reactor is electrically connected.
[0071] The flow rate of the pump 4 must allow, taking into account the heat capacity of the heat transfer fluid and the sizing of the steam generator 3, to supply the latter with heat transfer fluid at a flow rate that allows it to meet the power demands of the electrical network.
[0072] The pump 4 has metal walls resistant to the chemical attack of the heat transfer fluid at high temperatures, typically above 300°C. Several pumps can be positioned in parallel to distribute the pumping flow rate and a redundant pump can be provided for safety reasons.
[0073] The circuit 10 also includes at least one circuit for heating the feedwater of the steam generator 3 before it is injected / expanded as steam into the high-pressure body 60 of the turbine 6.
[0074] This heating circuit includes first of all a high-pressure heater 64 connected to the high-pressure body 60, to a water tank, called a feed tank 66, and to the first steam generator 30. It also includes a low-pressure heater 65 connected on the one hand by at least one fluid branch to the low-pressure body and on the other hand by at least one fluid branch to the condenser 7.
[0075] In this circuit, a condensate extraction pump 81 from the condenser 7 conveys the condensate to the feed tank 66 via the low-pressure heater 65. The condensate is typically at a temperature of 40°C at a pressure of around 0.075 bar at the outlet of the condenser 7.
[0076] As shown in [Fig.1], the low pressure heater 65 uses as a heat source the steam drawn from the low pressure body 61 of the turbine 6. The low pressure heater 65 thus heats the feedwater of the steam generator 30. When the feedwater leaves the low pressure heater 65, it typically has a temperature between 80 and 100 °C.
[0077] The pump 80 makes it possible to bring this feed water from the feed tank 66 to the high pressure heater 64 to bring it to a temperature of around 150°C at a pressure of 40 bars in the steam generator 30.
[0078] A steam dryer 67 is arranged between the high-pressure bodies 60 and low-pressure bodies 61 of the turbine 6 and is connected to the feed tank.
[0079] The high-pressure heater 64 uses as a heat source the steam drawn from the high-pressure body 60 of the turbine 6.
[0080] The installation according to the invention further comprises, at least one high temperature electrolysis unit EHT 100 thermally coupled to the nuclear reactor by an injection coupling circuit 200.
[0081] This injection coupling circuit 200 includes first of all an intermediate heat exchanger 202 connected in a closed loop to a withdrawal tap A, made in the fluid branch 62 between the high pressure body 60 and the low pressure body 61 of the turbine, and to the feed tank 66. More specifically, taking into account the temperature and pressure of the hot steam that we wish to withdraw, the withdrawal tap A is at a point in the branch 62 which connects the high pressure body 60 of the turbine and the dryer 67.
[0082] As detailed later, this tapping at point A is chosen at the appropriate temperature level to provide the latent heat necessary to vaporize the feed water of unit 100.
[0083] The tapping of the draw-off A can be carried out in a strictly identical manner (type of weld, characteristic diameter of pipe, etc.) to that of the draw-off supplying the high-pressure heater 64.
[0084] Branch A is advantageously equipped with a regulating valve for the inlet pressure in the intermediate heat exchanger 202. This regulating valve can also be used as a regulating valve for the inlet pressure in the high-pressure heater 64. This allows the valve to be operated in two different modes. This regulating valve makes it possible to optimize the operation and control of the coupling cycle 200, with a high degree of flexibility.
[0085] In the closed loop from the draw-off point A, the fluid branch 201 allows the steam to be channeled and transferred to the exchanger 202. After heat exchange, the fluid branch 203 returns the liquid water to a point B of the feed tank.
[0086] This circuit also includes a second steam generator, called the coupling steam generator 205, adapted to produce feed steam at an inlet point C of the electrolysis unit 100 from demineralized liquid water from a point D. This coupling generator 205 is also connected in an intermediate closed loop to the heat exchanger 202.
[0087] In this intermediate closed loop 207, a circulation pump 206 brings pressurized liquid water via the fluid branch 204 from the exchanger 202 to the coupling generator 205 and then after heat exchange, returns the water via the fluid branch 207 to the exchanger 202.
[0088] The installation according to the invention further comprises, at least one 300 unit of direct air capture (DAC for "Direct Air capture"), thermally coupled to the nuclear reactor by an injection coupling circuit 400.
[0089] This circuit 400 includes first of all an intermediate heat exchanger 402 connected in a closed loop to a first injection spigot made at point E at the level of the body of the low pressure turbine 61, and to a second reinjection spigot made at point F between the outlet of the body of the low pressure turbine 61 and the condenser 7.
[0090] In this closed loop from the draw-off point E, the fluid branch 401 brings a mixture of water and steam to the exchanger 402 and after exchange, the fluid branch 403 allows the pressurized liquid water to be channeled and transferred to point F.
[0091] This circuit also includes an intermediate heat exchanger 405, called a coupling exchanger, connected to a fluidic branch 408 whose inlet at the point of withdrawal G is connected to a supply of desorbed CO2 from unit 300 (DAC) and the outlet is connected to at least one supply of absorbed CO2 from unit 300 (DAC).
[0092] This coupling exchanger 405 is connected in an intermediate closed loop to the heat exchanger 402, so as to inject the heat necessary for the operation of the unit 300 (DAC).
[0093] In this intermediate closed loop, a circulation pump 406 brings a heat transfer fluid from the coupling exchanger 402 via a fluid branch 404 to the exchanger 405 and then after heat exchange, returns the heat transfer fluid via a fluid branch 407 to the exchanger 402.
[0094] The installation further includes a synthetic fuel production unit 500 which can implement a reverse water gas shift (RWGS) process and / or a Fischer-Tropsch (FT) process and, where appropriate, a reforming process.
[0095] This allows the recycling of fractions including carbon chains below C5 to maximize the production of the fraction of interest. The fraction of interest is kerosene, comprising C8-Ci6 chains and typically obtained after distillation at atmospheric pressure.
[0096] As illustrated in [Fig.2], the production unit 500 is supplied directly with hydrogen produced by the high-temperature electrolysis unit 100 and with carbon dioxide CO2 captured by the DAC unit 300.
[0097] The synthetic fuel exiting the production unit 500 undergoes two consecutive coolings (Cooling 1, Cooling 2) and, if necessary, a third cooling before being discharged.
[0098] In the installation according to the invention, the waste heat generated by the production unit 500 is reinjected into the Rankine cycle 10.
[0099] A first coupling circuit for reinjection 600 of the low-temperature waste heat, typically in a range of 80°C to 150°C, includes first of all a coupling heat exchanger 602 connected in a closed loop by a fluid branch 601 to a first sampling tap made at point I between the condenser 7 and the low-pressure heater 65, preferably downstream of the low-pressure pump 81, and by a fluid branch 603 to a second reinjection tap made at point J at the outlet of the low-pressure heater 65, upstream of the feed tank 66.
[0100] In this closed loop, the pressurized liquid water is brought to the exchanger 602 and after exchange, the fluid branch 603 allows the heated pressurized liquid water to be channeled and transferred to point J.
[0101] The coupling exchanger 602 is also connected to a closed loop 604. In this closed loop 604, the pressurized liquid water is heated by the Cooling 2 at the outlet of the exchanger 602 at point L and returns to the exchanger at point K with the heated water which has thus recovered the low-temperature waste heat from the production unit 500.
[0102] Also, as shown in [Fig.2], the liquid water heated at Cooling 2 can serve as a preheating liquid for the water and carbon dioxide feeding the EHT 100 electrolysis unit.
[0103] A second high-temperature waste heat reinjection coupling circuit 700, typically in a range of 200°C to 350°C, includes firstly a coupling heat exchanger 702 directly connected to a fluid branch 701 between the dryer 67 and the body of the low-pressure turbine 61.
[0104] In this fluid branch 701, the pressurized liquid water at point M is brought from the dryer 67 to the exchanger 702 and after exchange, the liquid water heated at point N is channeled and transferred to the low-pressure turbine body 61.
[0105] The coupling exchanger 702 is also connected to a closed loop 703. In this closed loop 703, a heat transfer fluid which has recovered the high-temperature waste heat from the outlet of the production unit 500 supplies the exchanger 702 at point O and supplies the production unit back from point P.
[0106] The second reinjection coupling circuit 700 may include another coupling heat exchanger 704 connected in a closed loop by a fluid branch 705 to a first sampling tap made at point M' at the inlet of the high-pressure heater, and by a fluid branch 706 to a second reinjection tap made at point N' at the inlet of the steam generator 3.
[0107] In this closed loop, the pressurized steam is brought to the exchanger 704 and after exchange, the fluid branch 706 allows this heated pressurized steam to be channeled and transferred to point N'.
[0108] The coupling exchanger 704 is also connected to the closed loop 703 or a closed series or parallel fluidic loop. In this closed loop, a heat transfer fluid that has recovered the high-temperature waste heat from the outlet of the production unit 500 supplies the exchanger 704 at point O' and returns to the production unit from point P'.
[0109] Point O and point O' can be the same, and points P and P' can be the same. In the illustrated example, the exchangers 702 and 704 are in fluidic parallel.
[0110] In the illustrated example, each of the fluid branches of the circuits consists of a cylindrical pipe, preferably with metallic walls, insulated externally with high-temperature insulation. The diameter of a pipe is calculated to allow the entire thermal power to be dissipated with a maximum permissible flow velocity of the heat transfer fluid, typically on the order of 1 to 10 m / s.
[0111] The electrical network connected to the alternator 9 is designed to transport and distribute electricity to end users according to their needs. It is an electrical network adapted to the voltage requirements of the systems and operating according to power demands. related to the uses of electricity, which must be able to accept the peak electrical power produced by the installation.
[0112] In addition, the alternator 9 can supply the electricity requirements of the EHT 100 unit, including the electrolyzers which require direct current, to implement high-temperature electrolysis, of the DAC 300 unit and all the electrical requirements of the other systems.
[0113] The inventors have performed a sizing of all the components of the cogeneration plant, with the characterization of each point of the circuits 200, 400, 600, 700 in terms of temperature and pressure. This sizing is established using software, called CYCLOP, which the applicant has qualified for the steady-state sizing of thermodynamic conversion cycles.
[0114] The CYCLOP software essentially allows the modeling of an energy conversion cycle, consisting of different loops connected by thermal, mechanical, or electrical exchanges. Each loop is made up of components (exchangers, pumps, turbines, etc.) connected to each other by a fluid circulation.
[0115] The operation of this software makes it possible to calculate each thermodynamic point of the complete cycle and to deduce the production of useful energy and therefore its efficiency. Each component is characterized by chosen macroscopic quantities, but it is possible to link this tool to finer pre-sizing modules which make it possible to obtain more detailed characteristics of a given cycle.
[0116] The software also allows the optimization of the efficiency of a cycle according to its free parameters (turbine pressure ratio, withdrawal pressures and flow rates, etc.), using deterministic or genetic optimization algorithms.
[0117] The use of this software and its relevance are described, for example, in [5] or [6]. The dimensioning can also be carried out using other commercial software, in particular that under the name THERMOFLEX®.
[0118] The energy efficiency of the installation is calculated for a 100 MW nuclear reactor; it corresponds to the lower heating value of a liquid cut (C5+) of a production unit 500 divided by the core power of the nuclear reactor.
[0119] The following table 1 gives different values of water temperature and pressure at the various points A to P mentioned above as well as in the various fluid branches concerned of circuits 200, 400, 600, 700 were obtained using the CYCLOP software.
[0120] [Tables 1] Fluidic point / branch Temperature (°C) Pressure (bar) Vapor / liquid mixture draw-off point A 147-179 6.0-7.4 Saturated liquid water injection point B 145-177 5.7-6.9 Vapor / liquid mixture withdrawal point C 95-117 1.5-1.9 Vaporized water injection point D 104-128 1.5-1.9 Vapor / liquid mixture sampling point E 99-124 1.3-1.5 Liquid water sampling return point F 91-111 0.9-1.1 Absorbed CO2 withdrawal point G 81-99 Desorbed CO2 injection point H 81-99 Liquid water sampling point I 30-36 6.0-7.4 Liquid water return point J 65-79 5.7-6.9 Liquid water reinjection point K 81-99 54-66 Liquid water return point L 36-44 54-66 Steam inlet point M 145-177 5.7-6.9 Steam outlet point N 211-257 5.3-6.5 Heat transfer fluid reinjection point O 215-263 2.7-3.3 Heat transfer fluid return point P 198-242 2.7-3.3
[0121] The inventors calculated the energy efficiency of one configuration of the installation according to the invention compared to three configurations of installations according to the state of the art.
[0122] Configuration No. 1 according to the state of the art corresponds to an installation with purely generator power supply from the nuclear reactor without energy optimization or any recovery of waste heat.
[0123] Configuration No. 2 according to the state of the art corresponds to a generator supply from the nuclear reactor without recovery of waste heat but with a heat input with a temperature below 300°C without energy cost.
[0124] Configuration No. 2 according to the state of the art corresponds to an installation with generator power from the nuclear reactor without recovery of waste heat but with a heat input with a temperature below 300°C without energy cost.
[0125] Configuration No. 3 according to the invention corresponds to a heat return to the Rankine cycle coupled to the nuclear reactor, at a temperature of approximately 100°C which corresponds to the low-temperature waste heat of units 100 and 300.
[0126] Configuration No. 4 according to the invention corresponds to a heat return to the Rankine cycle coupled to the nuclear reactor, at a temperature according to Table 1 which corresponds to the high temperature waste heat of units 100 and 300 and to a temperature according to Table 1 which corresponds to the low temperature waste heat of units 100 and 300.
[0127] These different configurations are represented in [Fig.3]. It should be noted that the acronym SMR designates an SMR type nuclear reactor (power here of 100MW), SCE designates the Rankine cycle, EHT designates a high temperature electrolysis unit, FT designates a unit implementing a Fischer Tropsch process, RWGS designates a unit implementing the reverse gas-to-water reaction, and DAC designates a direct CO2 capture unit.
[0128] The results of the power calculations for these different configurations are shown in [Fig. 4]. It appears from these results that configuration No. 4 according to the invention allows an improvement in energy efficiency compared to configuration No. 1 according to the prior art of 20.5% and compared to that according to configuration No. 3 according to the invention of 0.5%.
[0129] It is specified that the energy efficiency was calculated for a 100 MW nuclear reactor, it corresponds to the lower heating value of the liquid cut (C5+) divided by the core power of the nuclear reactor and it is represented in dark green on the exit bars.
[0130] The invention is not limited to the examples just described; in particular, features of the illustrated examples can be combined in unillustrated variants.
[0131] Other variants and embodiments may be envisaged without departing from the scope of the invention.
[0132] If, in the illustrated examples, the waste heat is reinjected respectively at the low-pressure reheating stage for low temperatures, and at the superheating and high-pressure reheating stages for high temperatures, one can consider more generally,
[0133] - a reinjection of the waste heat at low temperature, into any location, of the SCE system, with a series or parallel reinjection of other heating elements in particular; and / or
[0134] - a reinjection of the high-temperature waste heat into the cycle, in any location in the SCE system, particularly at the superheating point between the steam generator and the turbine, at the superheating point between the turbines or at the reheating point (at high or low pressure), with reinjection in series or in parallel with other reheating points in particular.
[0135] The nuclear cogeneration plant just described in relation to a pressurized water nuclear reactor can be implemented with all indirect thermodynamic cycle nuclear reactors, for which the cycle of Heat production is physically separated from the energy conversion cycle, as in a boiling water reactor or a Generation IV nuclear reactor, which involves different temperature levels in the conversion cycle. Therefore, while the detailed example concerns a small pressurized water reactor (SMR), a cogeneration plant can be considered with a large or conventional reactor.
[0136] More generally, the invention can be implemented for any thermal power plant such as a solar, geothermal...
[0137] The invention can be implemented with any unit for the production of synthetic molecules in which there is an exothermic reaction, such as the production of methanol, ammonia, or methane. The more exothermic and at higher temperatures the reaction, the greater the reinjection of waste heat back into the Rankine cycle and the improved the energy efficiency.
[0138] An improvement in the overall energy efficiency of an installation according to the invention could be observed by a production unit implementing a high-temperature Fischer Tropsch process of approximately 300°C.
[0139] If the installation according to the invention is described with a high temperature electrolysis unit (HTE), the invention can be implemented with alkaline electrolysis, PEM or AEM.
[0140] In the case where there is no need for heat for electrolysis:
[0141] - the low-temperature waste heat reinjection circuit is retained, because the Rankine's cycle can still utilize this energy;
[0142] - the high-temperature waste heat reinjection circuit is still relevant, allowing the replacement of the superheating upstream of the low-pressure turbine;
[0143] - the heat extraction loop at the outlet of the EHT 100 unit is eliminated, which allows for a further increase in electricity production.
[0144] For CO2 capture, technologies other than direct air capture (DAC) can be considered. For example, capture from flue gases or a concentrated CO2 stream from another process (e.g., methanation) can be implemented. In the latter case, the heat required by the cycle would be reduced or even eliminated, and the loop at the outlet of the DAC 300 unit would therefore be removed without compromising the effectiveness of the other connections.
[0145] The possibility of electrically connecting the installation to the network can be provided for, in particular to guarantee a fuel production base in the event of a shutdown / maintenance of the nuclear reactor or a transient operation, and / or in the case where the reactor is not solely dedicated to the production of fuels while maintaining a thermal connection with the process.
[0146] The thermal supply of the installation can be provided by a nuclear reactor that is solely heat-generating.
[0147] A reforming unit can be implemented in the installation.
[0148] It is also possible to consider implementing storage (CO2, H2...) within the installation. List of cited references
[0149] [1]: Fujiwara et al. "Hydrogen production by high temperature electrolysis with nuclear reactor'\Progress in Nuclear Energy 50 (2008).
[0150] [2]: Richard D. Boardman et al. “Developing a low-cost renewable supply of hydrogen with high-temperature electrochemistry". MRS Bulletin, volume 47, march 2022, mrs.org / bulletin.
[0151] [3]: Zang G. et al., “The modeling ofSynfuel Production Process - ASPENModel ofFTproduction with electricity demand provided at LWR scale", December 2021. https: / / publications.anl.gov / anlpubs / 2022 / 02 / 173337.pdf
[0152] [4]: Delgado et al., “Techno-economic analysis and life cycle analysis ofe-fuel production using nuclear energy" Journal of CO2 Utilization, 72, 2023, 102481.
[0153] http: / / dx.doi.Org / 10.1016 / j.jcou.2023.102481
[0154] [5]: H.D. Nguyen, N. Alpy, D. Haubensack. “Insight on electrical and thermal powers mix with a Gen2 PWR: Rankine cycle performances under low to high température grade cogénération.” Energy, Elsevier, 2020, 202, pp. 117518. ffl0.1016 / j.energy.2020.117518ff. ffcea-0256923If.
[0155] [6]: D. Haubensack et al., “The COPERNIC / CYCLOP computer tool: pre-conceptual design of génération 4 nuclear Systems, HTR-2004”, 2nd International Topic Conférence for the HTGR, September 22-24, 2004, Beijing, China, 2004.
Claims
Demands
1. Electricity generation installation, intended to produce electricity and where applicable heat, comprising: - a thermal power plant (1), with a thermal energy-to-electrical energy conversion system (TEE); - at least one electrolysis unit (100), electrically connected to the TEE and capable of being thermally coupled to the thermal power plant by a fluidic circuit, so as to be supplied by the electricity and heat required for the electrolysis reaction, respectively; - at least one production unit (500) of at least one synthetic fuel or organic chemical compound, adapted to carry out an exothermic synthesis reaction; the production unit being connected to the electrolysis unit by a fluidic circuit so as to be supplied by hydrogen;- at least one fluidic circuit (600, 700), called a high-temperature and / or low-temperature reinjection coupling circuit, to thermally couple the output of the production unit to at least a part of the SCE system so as to reinject at least a part of the so-called high-temperature and / or low-temperature waste heat produced by the exothermic synthesis reaction into the SCE system.;
2. Installation according to claim 1, the heat transfer fluid of the high-temperature reinjection coupling circuit being at a temperature of at least 150°C, advantageously between 200 and 350°C, advantageously between 215 and 275°C.
3. Installation according to claim 1 or 2, the heat transfer fluid of the low-temperature reinjection coupling circuit being at a temperature of at least 80°C, advantageously between 80 and 150°C, advantageously between 80 and 100°C.
4. An installation according to any one of the preceding claims, wherein: - the SCE system implements a Rankine cycle comprising: • at least one steam generator (3), • at least one turbine (6, 60) comprising a high-pressure body (60) connected to the steam generator and a low-pressure body (61) connected to the high-pressure body by at least one fluidic branch (62), • a high-pressure heater (64) connected to the high-pressure body (60), to a water tank, called a feed tank (66), and to the steam generator (30), • a low-pressure heater (65) connected on one side by at least one fluid branch to the low-pressure body (61) and on the other side by at least one fluid branch to the feed tank, • a condenser (7), connected on one side to the low-pressure body and on the other side to the low-pressure heater; - The high-temperature reinjection coupling circuit includes: • a heat exchanger (702) connected on the one hand in a closed loop to the outlet of the production unit of at least one synthetic fuel and on the other hand at the inlet to the high-pressure body (60) and at the outlet to the low-pressure body (61), and / or • a heat exchanger (704) connected on the one hand in a closed loop to the outlet of the production unit of at least one synthetic fuel and on the other hand at the inlet upstream of the high-pressure heater (64) and at the outlet to the steam generator (3), and / or • a heat exchanger connected on one side in a closed loop to the outlet of the production unit of at least one synthetic fuel and on the other side at the inlet to the high-pressure body and at the outlet to the high-pressure heater (64), and / or • a heat exchanger connected in a closed loop to the outlet of the production unit of at least one fuel of synthesis and on the other hand at the inlet to the low pressure body and at the outlet to the low pressure heater, and / or • a heat exchanger (602) connected on the one hand in a closed loop to the outlet of the cooler and on the other hand at the inlet between the condenser and the low pressure heater (65) and at the outlet between the low pressure heater (65) and the food tank (66).
5. An installation according to any one of the preceding claims, further comprising at least one direct carbon dioxide capture (DAC) unit, connected to the production unit of at least one synthetic fuel by a fluidic circuit and thermally coupled to the thermal power plant by a fluidic circuit so as to respectively supply the production unit with CO2 necessary for the exothermic synthesis reaction and to be supplied with heat necessary for the direct capture of CO2.
6. Installation according to any one of claims 4 or 5, further comprising, at the outlet of the cooler, a low-temperature preheater for the electrolysis unit and, where applicable, a low-temperature preheater for the direct carbon dioxide capture (DAC) unit,
7. Installation according to any one of the preceding claims, the synthetic fuel production unit being adapted to implement a reverse water gas shift (RWGS) process and / or a Fischer-Tropsch (FT) process and optionally a reforming process.
8. Installation according to any one of the preceding claims, the thermal power plant comprising at least one nuclear reactor, in particular a pressurized water reactor (PWR) or a boiling water reactor (BWR) or a fast neutron reactor in particular cooled with sodium (NaFNR).
9. Installation according to any one of the preceding claims, the SCE system implementing a Rankine cycle comprising an alternator adapted to supply at least part of its electricity to the electrolysis unit (100) and where appropriate to the direct carbon dioxide capture (DAC) unit.
10. Installation according to any one of the preceding claims, the electrolysis unit being a high-temperature electrolysis (100).
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