CN111600512A - Nuclear reactor power supply system with energy gradient utilization function - Google Patents
Nuclear reactor power supply system with energy gradient utilization function Download PDFInfo
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- CN111600512A CN111600512A CN202010500007.5A CN202010500007A CN111600512A CN 111600512 A CN111600512 A CN 111600512A CN 202010500007 A CN202010500007 A CN 202010500007A CN 111600512 A CN111600512 A CN 111600512A
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- steam
- alkali metal
- thermoelectric conversion
- nuclear reactor
- steam generator
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- H—ELECTRICITY
- H02—GENERATION; CONVERSION OR DISTRIBUTION OF ELECTRIC POWER
- H02N—ELECTRIC MACHINES NOT OTHERWISE PROVIDED FOR
- H02N11/00—Generators or motors not provided for elsewhere; Alleged perpetua mobilia obtained by electric or magnetic means
- H02N11/002—Generators
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01D—NON-POSITIVE DISPLACEMENT MACHINES OR ENGINES, e.g. STEAM TURBINES
- F01D15/00—Adaptations of machines or engines for special use; Combinations of engines with devices driven thereby
- F01D15/10—Adaptations for driving, or combinations with, electric generators
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01K—STEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
- F01K11/00—Plants characterised by the engines being structurally combined with boilers or condensers
- F01K11/02—Plants characterised by the engines being structurally combined with boilers or condensers the engines being turbines
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- H—ELECTRICITY
- H02—GENERATION; CONVERSION OR DISTRIBUTION OF ELECTRIC POWER
- H02N—ELECTRIC MACHINES NOT OTHERWISE PROVIDED FOR
- H02N3/00—Generators in which thermal or kinetic energy is converted into electrical energy by ionisation of a fluid and removal of the charge therefrom
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- Engineering & Computer Science (AREA)
- Mechanical Engineering (AREA)
- General Engineering & Computer Science (AREA)
- Chemical & Material Sciences (AREA)
- Combustion & Propulsion (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Engine Equipment That Uses Special Cycles (AREA)
Abstract
The invention discloses a nuclear reactor power supply system for energy gradient utilization, which belongs to the technical field of nuclear reactor engineering and comprises a reactor, a high-temperature heat pipe, an alkali metal thermoelectric conversion element, a direct-current steam generator and a steam Rankine cycle loop, wherein the high-temperature heat pipe is connected with the high-temperature heat pipe; one end of the alkali metal thermoelectric conversion element is an evaporation end, and the other end of the alkali metal thermoelectric conversion element is a condensation end; the high-temperature heat pipe is divided into an evaporation section and a condensation section, the part of the high-temperature heat pipe inserted into the reactor is set as the evaporation section, and the part of the evaporation end inserted into the alkali metal thermoelectric conversion element is set as the condensation section; the direct current steam generator is coupled with the condensation end of the alkali metal thermoelectric conversion element; the once-through steam generator is in communication with the steam rankine cycle circuit. The direct-current steam generator of the steam Rankine cycle is combined with the condensation end of the alkali metal thermoelectric conversion device, the temperature of the condensation end of the alkali metal thermoelectric conversion device is controlled by utilizing the boiling heat exchange of the steam, and the system is simple, compact in structure and high in condensation efficiency.
Description
Technical Field
The invention belongs to the technical field of nuclear reactor engineering, and particularly relates to a nuclear reactor power supply system for energy cascade utilization.
Background
The alkali metal thermoelectric direct conversion technology takes alkali metal as a working medium, utilizes the selective permeability of BASE materials, completes the direct conversion from heat energy to electric energy through thermodynamic cycle, and has the advantages of high thermoelectric conversion efficiency, small duty factor, wide energy sources (mineral energy, solar energy, nuclear energy and heat accumulator heat energy), modular structure and the like.
The temperature of the high-temperature end of the alkali metal thermoelectric conversion element is generally 900-1300K, and the temperature of the low-temperature end is generally 600-800K. At high operating temperatures, alkali metal thermoelectric direct conversion can achieve thermoelectric conversion efficiencies above 20%. But still a great deal of high-quality energy is discharged to the environment in the operation process, the temperature of the part of energy is 300 ℃ to 450 ℃, and the part of energy can be completely used as a heat source of other low-grade energy conversion systems.
Therefore, there is a need for a power generation system that uses low-grade heat energy generated by alkali metal thermoelectric conversion to generate superheated steam to drive a turbine generator to generate power, so as to realize step utilization of energy.
Disclosure of Invention
The invention provides a power generation system which utilizes low-grade heat energy generated after alkali metal thermoelectric conversion to generate superheated steam to drive a turbonator to generate power so as to realize gradient utilization of energy.
In order to achieve the purpose, the invention adopts the technical scheme that:
a nuclear reactor power supply system with energy cascade utilization comprises a reactor, a high-temperature heat pipe, an alkali metal thermoelectric conversion element, a direct-current steam generator and a steam Rankine cycle loop; one end of the alkali metal thermoelectric conversion element is an evaporation end 31, and the other end of the alkali metal thermoelectric conversion element is a condensation end; the high-temperature heat pipe is divided into an evaporation section and a condensation section, the part of the high-temperature heat pipe inserted into the reactor is set as the evaporation section, and the part of the high-temperature heat pipe inserted into the evaporation end of the alkali metal thermoelectric conversion element is set as the condensation section; the direct current steam generator is coupled with the condensation end of the alkali metal thermoelectric conversion element; the once-through steam generator is in communication with the steam Rankine cycle loop.
Further, the steam rankine cycle circuit includes a steam turbine, a generator, a condenser, and a feedwater pump; the direct-current steam generator is provided with a water supply chamber and a steam chamber; the inlet of the steam turbine is communicated with the steam chamber of the once-through steam generator; the outlet of the feed water pump is communicated with the feed water chamber of the direct current steam generator.
Further, the reactor is a fast neutron reactor, and comprises a metal matrix and a fuel element; the fuel element is a uranium nitride or uranium carbide fuel.
Further, the fuel element is uranium nitride.
Furthermore, the working medium of the high-temperature heat pipe is sodium or lithium alkali metal working medium.
Further, the working medium of the high-temperature heat pipe is sodium.
Further, the once-through steam generator is composed of an arrangement of a plurality of heat transfer pipes coupled to the condensation end of the alkali metal thermoelectric conversion element.
Further, the heat transfer pipe may have one of a circular, rectangular or oval form.
The invention has the beneficial effects that:
1. the direct-current steam generator of the steam Rankine cycle is combined with the condensation end of the alkali metal thermoelectric conversion device, the temperature of the condensation end of the alkali metal thermoelectric conversion device is controlled by utilizing the boiling heat exchange of the steam, and the system is simple, compact in structure and high in condensation efficiency;
2. in the invention, the waste heat of alkali metal thermoelectric conversion is transferred to the direct current steam generator to generate steam, and the steam can be used for pushing a steam turbine to generate electricity, desalinate seawater, supply heat to a region and the like, thereby realizing the cascade utilization of nuclear fission energy and improving the overall thermal efficiency of the system;
3. the combination of the alkali metal thermoelectric conversion element and the direct current steam generator can be in various forms, and the application requirements of different power energy sources are met.
Drawings
FIG. 1 is a schematic diagram of a nuclear reactor power system arrangement for energy cascade utilization of the present invention;
FIG. 2 is a schematic diagram of an alkali metal thermoelectric conversion module according to the present invention;
wherein, 1, a reactor; 11. a metal substrate; 12. a fuel element; 2. a high temperature heat pipe; 3. an alkali metal thermoelectric conversion element; 31. an evaporation end; 32. a condensing end; 33. a wick; 4. a once-through steam generator; 41. a water feed chamber; 42. a steam chamber; 43. a heat transfer tube; 5. a steam Rankine cycle system; 51. a steam turbine; 52. a generator; 53. a condenser; 54. a feed pump; 6. a feed water flow regulating valve; 7. a steam valve.
Detailed Description
The invention provides a nuclear reactor power supply system with energy cascade utilization. The technical solution of the present invention is described in detail below with reference to the accompanying drawings so that it can be more easily understood and appreciated.
Example 1
A nuclear reactor power supply system for energy cascade utilization is shown in FIG. 1 and comprises a reactor 1, a high-temperature heat pipe 2, an alkali metal thermoelectric conversion element 3, a direct-current steam generator 4 and a steam Rankine cycle loop 5; one end of the alkali metal thermoelectric conversion element 3 is an evaporation end 31, and the other end is a condensation end 32; the high-temperature heat pipe 2 is divided into an evaporation section and a condensation section, the part of the high-temperature heat pipe 2 inserted into the reactor 1 is set as the evaporation section, and the part of the evaporation end 31 inserted into the alkali metal thermoelectric conversion element 3 is set as the condensation section; the direct current steam generator 4 is coupled with the condensation end 32 of the alkali metal thermoelectric conversion element 3, so that the structure is more compact; the once-through steam generator 4 communicates with a steam rankine cycle circuit 5.
The reactor 1 is a fast neutron reactor, and the reactor 1 comprises a metal matrix 11 and a fuel element 12; of these, the fuel element 12 is a uranium nitride or uranium carbide fuel, preferably uranium nitride.
The reactor core of the reactor 1 is a high-temperature solid reactor, and the temperature of the metal matrix 11 is more than 1300K.
The working medium of the high-temperature heat pipe 2 is sodium or lithium alkali metal working medium, preferably sodium; the operating temperature of the working medium in the high-temperature heat pipe 2 is 900-1300K.
In this embodiment, a plurality of alkali metal thermoelectric conversion elements 3, a plurality of condensing sections of the high-temperature heat pipes 2, and a set of dc steam generators 4 together form a static energy conversion module, which completes the first-stage utilization of energy, as shown in fig. 2.
Wherein the steam Rankine cycle circuit 5 consists of a steam turbine 51, a generator 52, a condenser 53 and a feed water pump 54; the once-through steam generator 4 is provided with a feedwater chamber 41 and a steam chamber 42; the inlet of the steam turbine 51 communicates with the outlet chamber 42 of the once-through steam generator 4; the outlet of the feed water pump 54 is communicated with the feed water chamber 41 of the once-through steam generator 4 to form a dynamic energy conversion module, thereby completing the secondary utilization of energy.
A feed water flow rate adjusting valve 6 is provided between the feed water pump 54 and the feed water chamber 41 to adjust the feed water flow rate.
In the present embodiment, the once-through steam generator 4 is composed of an arrangement of a plurality of heat transfer tubes 43, and the heat transfer tubes 43 are coupled to the condensation-end surfaces of the alkali-metal thermoelectric conversion elements 3. The heat transfer pipe 43 may be in one of a circular, rectangular or oval form.
Working medium in the direct current steam generator 4 absorbs heat of the condensation end 32 of the thermoelectric conversion element 3, boiling pressure on the secondary side of the direct current steam generator is controlled through the opening degree of the steam valve 7, and the temperature of the condensation end 5 of the alkali metal thermoelectric conversion element 4 is guaranteed to be constant.
The working principle of the embodiment is as follows:
the heat source of the nuclear reactor power supply system for energy cascade utilization is a high-temperature reactor 1. The high-temperature heat pipe 2 transfers the heat of the reactor 1 to the evaporation section 31 of the alkali metal thermoelectric conversion element 3 by utilizing the natural circulation flow of the internal working medium, the alkali metal working medium is evaporated into a gaseous state, the steam generates electricity through the BASE membrane electrode, then the sodium steam transfers the heat to the steam generator 4 at the condensation end 32 and is condensed into liquid sodium, and the liquid sodium flows back to the evaporation section 31 again under the action of the liquid absorption core 33, so that a circulation is completed, and the first-stage utilization of energy is realized.
The feed water of the once-through steam generator 4 first enters the feed water chamber 41, is then distributed evenly to the heat transfer tubes 43, is heated by the alkali metal thermoelectric conversion element 3 to superheated steam, and is sent to the turbine 51 to apply work, thereby driving the generator 52 to generate electricity. The exhaust steam enters the condenser 53 to be condensed, and then enters the once-through steam generator 4 after being pressurized by the feed water pump 54. A feed water flow control valve 6 at the outlet of the feed water pump 54 is used to adjust the feed water flow. The steam valve 7 is used to control the steam pressure. A second use of energy is achieved by rankine cycle of the steam.
The technical solutions of the present invention are fully described above, it should be noted that the specific embodiments of the present invention are not limited by the above description, and all technical solutions formed by equivalent or equivalent changes in structure, method, or function according to the spirit of the present invention by those skilled in the art are within the scope of the present invention.
Claims (8)
1. A nuclear reactor power supply system with energy cascade utilization is characterized by comprising a reactor (1), a high-temperature heat pipe (2), an alkali metal thermoelectric conversion element (3), a direct-current steam generator (4) and a steam Rankine cycle loop (5); one end of the alkali metal thermoelectric conversion element (3) is an evaporation end (31), and the other end is a condensation end (32); the high-temperature heat pipe (2) is divided into an evaporation section and a condensation section, the part of the high-temperature heat pipe (2) inserted into the reactor (1) is set as the evaporation section, and the part of the evaporation end (31) inserted into the alkali metal thermoelectric conversion element (3) is set as the condensation section; the direct current steam generator (4) is coupled with a condensation end (32) of the alkali metal thermoelectric conversion element (3); the once-through steam generator (4) is in communication with the steam Rankine cycle loop (5).
2. The nuclear reactor power system of claim 1 wherein the steam rankine cycle circuit (5) includes a steam turbine (51), a generator (52), a condenser (53), and a feedwater pump (54); the once-through steam generator (4) is provided with a water feeding chamber (41) and a steam chamber (42); the inlet of the steam turbine (51) is communicated with the steam chamber (42) of the once-through steam generator (4); the outlet of the feed water pump (54) is communicated with the feed water chamber (41) of the once-through steam generator (4).
3. Nuclear reactor power supply system according to claim 1, characterized in that said reactor (1) is a fast neutron reactor, said reactor (1) comprising a metallic matrix (11) and a fuel element (12); the fuel element (12) is uranium nitride or uranium carbide fuel.
4. A nuclear reactor power supply system according to claim 3, characterized in that the fuel element (12) is uranium nitride.
5. A nuclear reactor power supply system as claimed in claim 1, characterized in that the working fluid of the high temperature heat pipe (2) is a sodium or lithium alkali working fluid.
6. The nuclear reactor power supply system of claim 5 wherein the working fluid of the high temperature heat pipe (2) is sodium.
7. The nuclear reactor power supply system according to claim 1, characterized in that the once-through steam generator (4) is composed of an arrangement of a plurality of heat transfer tubes (43), the heat transfer tubes (43) being coupled with the condensation end (32) of the alkali metal thermoelectric conversion element (3).
8. An energy cascade nuclear reactor power system as claimed in claim 7, characterized in that said heat transfer tubes (43) are in the form of one of a circle, a rectangle or an ellipse.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202010500007.5A CN111600512A (en) | 2020-06-04 | 2020-06-04 | Nuclear reactor power supply system with energy gradient utilization function |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202010500007.5A CN111600512A (en) | 2020-06-04 | 2020-06-04 | Nuclear reactor power supply system with energy gradient utilization function |
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| CN111600512A true CN111600512A (en) | 2020-08-28 |
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| CN202010500007.5A Pending CN111600512A (en) | 2020-06-04 | 2020-06-04 | Nuclear reactor power supply system with energy gradient utilization function |
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Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113035382A (en) * | 2021-03-04 | 2021-06-25 | 哈尔滨工程大学 | Nuclear reactor system for alkali metal thermoelectric conversion of molten alloy electrode |
| WO2022121878A1 (en) * | 2020-12-08 | 2022-06-16 | 上海核工程研究设计院有限公司 | Alkali metal reactor power supply |
| RU2809235C1 (en) * | 2020-12-08 | 2023-12-08 | Шанхай Ньюклеар Инжиниринг Ресеарч Энд Дизайн Инститьют Ко., Лтд. | Alkali metal reactor power source |
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| CN109519242A (en) * | 2018-11-29 | 2019-03-26 | 郭刚 | A kind of AMTEC/ORC combined generating system |
| CN110729067A (en) * | 2019-10-31 | 2020-01-24 | 哈尔滨工程大学 | Nuclear power supply system for underwater unmanned submersible vehicle |
| CN110752786A (en) * | 2019-10-31 | 2020-02-04 | 哈尔滨工程大学 | Alkali metal thermoelectric conversion device for deep sea underwater platform |
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2020
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Patent Citations (3)
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| CN109519242A (en) * | 2018-11-29 | 2019-03-26 | 郭刚 | A kind of AMTEC/ORC combined generating system |
| CN110729067A (en) * | 2019-10-31 | 2020-01-24 | 哈尔滨工程大学 | Nuclear power supply system for underwater unmanned submersible vehicle |
| CN110752786A (en) * | 2019-10-31 | 2020-02-04 | 哈尔滨工程大学 | Alkali metal thermoelectric conversion device for deep sea underwater platform |
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Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2022121878A1 (en) * | 2020-12-08 | 2022-06-16 | 上海核工程研究设计院有限公司 | Alkali metal reactor power supply |
| RU2809235C1 (en) * | 2020-12-08 | 2023-12-08 | Шанхай Ньюклеар Инжиниринг Ресеарч Энд Дизайн Инститьют Ко., Лтд. | Alkali metal reactor power source |
| CN113035382A (en) * | 2021-03-04 | 2021-06-25 | 哈尔滨工程大学 | Nuclear reactor system for alkali metal thermoelectric conversion of molten alloy electrode |
| CN113035382B (en) * | 2021-03-04 | 2022-06-17 | 哈尔滨工程大学 | Nuclear reactor system for alkali metal thermoelectric conversion of molten alloy electrode |
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Application publication date: 20200828 |