CN113035382B - Nuclear reactor system for alkali metal thermoelectric conversion of molten alloy electrode - Google Patents
Nuclear reactor system for alkali metal thermoelectric conversion of molten alloy electrode Download PDFInfo
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- CN113035382B CN113035382B CN202110241398.8A CN202110241398A CN113035382B CN 113035382 B CN113035382 B CN 113035382B CN 202110241398 A CN202110241398 A CN 202110241398A CN 113035382 B CN113035382 B CN 113035382B
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/04—Thermal reactors ; Epithermal reactors
- G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
- G21C1/22—Heterogeneous reactors, i.e. in which fuel and moderator are separated using liquid or gaseous fuel
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- 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
- G21C15/243—Promoting flow of the coolant for liquids
- G21C15/247—Promoting flow of the coolant for liquids for liquid metals
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
The invention discloses a nuclear reactor system for alkali metal thermoelectric conversion of a molten alloy electrode, which belongs to the technical field of nuclear reactor engineering and comprises a reactor, a high-temperature heat exchanger, an electrode chamber, a load, a first heat regenerator, a sodium distillation separation chamber, a second heat regenerator, a condenser and an electromagnetic pump; the outlet and the inlet of the reactor are respectively connected with the inlet and the outlet of the high-temperature heat exchanger; the electrode chambers comprise a liquid sodium electrode chamber, a BASE electrode chamber and a molten alloy electrode chamber; the two ends of the load are respectively connected with the liquid sodium electrode chamber and the molten alloy electrode chamber; the electromagnetic pump is arranged between the heat absorption side inlet of the second heat regenerator and the heat release side outlet of the condenser; the heat absorption side outlet of the second heat regenerator is connected with the inlet of the liquid sodium electrode chamber; the sodium distillation separation chamber is arranged inside the high-temperature heat exchanger. The invention adopts the molten alloy and the liquid sodium as the circulating working medium, and utilizes the activity difference between the molten alloy and the liquid sodium as the driving force, thereby realizing high performance index at lower temperature and improving the reliability of the system.
Description
Technical Field
The invention belongs to the technical field of nuclear reactor engineering, and particularly relates to an alkali metal thermoelectric conversion nuclear reactor system with molten alloy and liquid sodium as electrodes.
Background
The alkali metal thermoelectric conversion device has no movable part, has the characteristics of less operation and maintenance, low vibration noise, good system sealing performance, high reliability and the like, and is applied to the military fields of aviation, nuclear power and the like. However, the driving force of alkali metal transportation in the BASE of the conventional alkali metal thermoelectric conversion device is a large enough pressure difference between two sides, which requires that the operating temperature of the device is high enough; in any configuration of the conventional alkali metal thermoelectric device, the cathode side (low-voltage side) of BASE is always gaseous sodium, so that a porous electrode must be used, which causes the problem that the conventional alkali metal thermoelectric conversion device generally suffers from large performance degradation, and the performance degradation is more severe at higher operating temperatures. Therefore, the liquid electrode is proposed by the scholars, which is mostly seen in the charging and discharging of the battery, but the idea is only generally proposed for realizing the conversion from the heat energy to the electric energy, and the problem of alloy reduction is not solved.
Therefore, a system for generating electricity by using nuclear energy as a heat source of a liquid electrode alkali metal thermoelectric conversion device is urgently needed.
Disclosure of Invention
The invention mainly aims to provide a system for generating electricity by using nuclear energy as a heat source of a liquid electrode alkali metal thermoelectric conversion device, which adopts the following technical scheme:
a nuclear reactor system for thermoelectric conversion of alkali metal with a molten alloy electrode comprises a reactor, a high-temperature heat exchanger, an electrode chamber, a load, a first heat regenerator, a sodium distillation separation chamber, a second heat regenerator, a condenser and an electromagnetic pump;
the outlet and the inlet of the reactor are respectively connected with the inlet and the outlet of the high-temperature heat exchanger;
the electrode chamber comprises a liquid sodium electrode chamber, a BASE and a molten alloy electrode chamber, wherein the BASE is arranged between the liquid sodium electrode chamber and the molten alloy electrode chamber and is used for separating the liquid sodium electrode chamber from the molten alloy electrode chamber;
the two ends of the load are respectively connected with the liquid sodium electrode chamber and the molten alloy electrode chamber;
the heat absorption side inlet and the heat absorption side outlet of the first heat regenerator are respectively connected with the outlet of the molten alloy electrode chamber and the low-sodium-content molten alloy inlet of the sodium distillation separation chamber; a heat release side inlet and a heat release side outlet of the first heat regenerator are respectively connected with a low-sodium content molten alloy outlet of the sodium distillation separation chamber and an inlet of the molten alloy electrode chamber;
the electromagnetic pump is arranged between the heat absorption side inlet of the second heat regenerator and the heat release side outlet of the condenser;
the heat absorption side outlet of the second heat regenerator is connected with the inlet of the liquid sodium electrode chamber; a heat release side inlet of the second heat regenerator is connected with a sodium vapor outlet of the sodium distillation separation chamber, and a heat release side outlet of the second heat regenerator is connected with a heat release side inlet of the condenser;
the sodium distillation separation chamber is arranged inside the high-temperature heat exchanger.
Further, the reactor is one of a molten salt reactor, a lead bismuth reactor or a lead cold fast reactor.
Further, the alloy of the electrode chamber of the molten alloy is lead sodium or tin sodium.
Further, the liquid sodium electrode chamber and the molten alloy electrode chamber are at the same temperature.
Furthermore, the working medium on the heat absorption side of the condenser is one of seawater, fresh water or air.
Further, the liquid sodium electrode chamber, the BASE, the molten alloy electrode chamber, the load, the first heat regenerator, the sodium distillation separation chamber, the second heat regenerator, the condenser and the electromagnetic pump can form a plurality of circulation loops according to the requirement.
The invention has the beneficial effects that:
1. compared with the traditional alkali metal thermoelectric conversion device, the invention adopts the molten alloy and the liquid sodium as the circulating working medium, and the molten alloy and the liquid sodium are electrodes, so that the problem of performance attenuation caused by the growth of crystal grains is solved; and the activity difference between the molten alloy and the liquid sodium is used as a driving force instead of pressure difference, so that high performance indexes can be realized at a lower temperature, and the reliability of the system is further improved.
2. The invention utilizes the high-temperature fast reactor as the heat source of the sodium distillation separation chamber, and solves the problem of alloy reduction.
3. Under the condition of not introducing extra heat sources and cold sources, the temperature of the condensed sodium is increased and the temperature of the high-temperature low-sodium-content molten alloy is reduced by adopting a heat return mode, so that the continuity of circulation is realized.
4. Compared with the traditional nuclear power generation system, the whole system has no rotating part and has the advantages of less operation and maintenance, low noise, good sealing performance and high reliability.
Drawings
FIG. 1 is a schematic view of the overall structural arrangement of the present invention;
wherein, 1, a reactor; 2. a high temperature heat exchanger; 3. a liquid sodium electrode chamber; 4. BASE; 5. a molten alloy electrode chamber; 6. a load; 7. a first heat regenerator; 8. a sodium distillation separation chamber; 9. a second regenerator; 10. a condenser; 11. an electromagnetic pump.
Detailed Description
Example 1
A nuclear reactor system for thermoelectric conversion of alkali metal with a molten alloy electrode (shown in figure 1) comprises a reactor 1, a high-temperature heat exchanger 2, an electrode chamber, a load 6, a first heat regenerator 7, a sodium distillation separation chamber 8, a second heat regenerator 9, a condenser 10 and an electromagnetic pump 11.
The outlet and the inlet of the reactor 1 are respectively connected with the inlet and the outlet of the high-temperature heat exchanger 2; wherein, the coolant (molten salt, lead bismuth or lead) absorbs heat in the reactor 1 and releases heat in the high-temperature heat exchanger 2.
The electrode chambers comprise a liquid sodium electrode chamber 3, a BASE4 and a molten alloy electrode chamber 5, and a BASE4 is arranged between the liquid sodium electrode chamber 3 and the molten alloy electrode chamber 5 and used for separating the liquid sodium electrode chamber 3 and the molten alloy electrode chamber 5.
The two ends of the load 6 are respectively connected with the liquid sodium electrode chamber 3 and the molten alloy electrode chamber 5.
The heat absorption side inlet and the heat absorption side outlet of the first heat regenerator 7 are respectively connected with the outlet of the molten alloy electrode chamber 5 and the low-sodium-content molten alloy inlet of the sodium distillation separation chamber 8; the heat release side inlet and the heat release side outlet of the first heat regenerator 7 are respectively connected with the low-sodium content molten alloy outlet of the sodium distillation separation chamber 8 and the inlet of the molten alloy electrode chamber 5.
An electromagnetic pump 11 is disposed between the heat absorption-side inlet of the second regenerator 9 and the heat release-side outlet of the condenser 10.
The heat absorption side outlet of the second heat regenerator 9 is connected with the inlet of the liquid sodium electrode chamber 3; the heat release side inlet of the second regenerator 9 is connected with the sodium vapor outlet of the sodium distillation separation chamber 8, and the heat release side outlet of the second regenerator 9 is connected with the heat release side inlet of the condenser 10.
The sodium distillation separation chamber 8 is provided inside the high temperature heat exchanger 2.
In this embodiment, the high-sodium content molten alloy (lead sodium or tin sodium alloy) in the molten alloy electrode chamber 5 is reheated by the first regenerator 7 and then enters the sodium distillation separation chamber 8, the sodium distillation separation chamber 8 is disposed in the high-temperature heat exchanger 2, the high-sodium content molten alloy in the sodium distillation separation chamber 8 absorbs heat released by the coolant in the high-temperature heat exchanger 2, and since the boiling point of sodium is much smaller than that of lead or tin, sodium is distilled out in the form of vapor, so the high-sodium content molten alloy after absorbing heat in the sodium distillation separation chamber 8 is divided into two paths: one path of sodium vapor enters a heat release side inlet of a second heat regenerator 9, enters a condenser 10 after heat release in the second heat regenerator 9 and is condensed into liquid, liquid sodium is pressurized by an electromagnetic pump 11 and then enters a heat absorption side inlet of the second heat regenerator 9, and the liquid sodium enters a liquid sodium electrode chamber 3 after being reheated to a temperature T1 in the second heat regenerator 9; the other path of low-sodium content molten alloy enters the heat release side inlet of the first heat regenerator 7, releases heat in the first heat regenerator 7 to the temperature T1 and enters the molten alloy electrode chamber 5.
In the embodiment, the reactor 1 is one of a molten salt reactor, a lead bismuth reactor or a lead cold fast reactor; the alloy positioned in the molten alloy electrode chamber 5 is lead sodium or tin sodium; the working medium on the heat absorption side of the condenser 10 is one of seawater, fresh water or air.
In another embodiment, the circulation loop formed by the liquid sodium electrode chamber 3, the BASE4, the molten alloy electrode chamber 5, the load 6, the first regenerator 7, the sodium distillation separation chamber 8, the second regenerator 9, the condenser 10 and the electromagnetic pump 11 in embodiment 1 may be provided in plurality as needed.
The principle of the combined power generation nuclear reactor system is as follows:
fission reaction occurs in the reactor 1 to generate heat, coolant (molten salt, lead bismuth or lead) absorbs heat in the reactor 1, heat is released in the high-temperature heat exchanger 2, the high-sodium content molten alloy in the molten alloy electrode chamber 5 enters the sodium distillation separation chamber 8 after being reheated by the first reheater 7 to absorb heat again, and because the boiling point of sodium is far smaller than that of lead or tin, the sodium is distilled out in the form of steam, so the high-sodium content molten alloy after absorbing heat in the sodium distillation separation chamber 8 is divided into two paths: one path of sodium vapor is primarily released heat in the second heat regenerator 9, then condensed into liquid by the condenser 10, pressurized by the electromagnetic pump 11, reheated to a temperature of T1 by the second heat regenerator 9, and then enters the liquid sodium electrode chamber 3; the other path of low-sodium content molten alloy enters the first heat regenerator 7 to release heat to the temperature T1 and then enters the molten alloy electrode chamber 5.
Because the liquid sodium electrode chamber 3 on two sides of the BASE4 has different sodium activity from the molten alloy electrode chamber 5, sodium ions will pass through the BASE4 from the side with high activity (i.e. the side of the liquid sodium electrode chamber 3) to the side with lower activity (i.e. the side of the molten alloy electrode chamber 5), while electrons will pass through the load 6 from the side of the liquid sodium electrode chamber 3 and return to the side of the molten alloy electrode chamber 5 to be combined with the sodium ions, thereby continuously converting the heat energy into electric energy.
The above description is only a preferred embodiment of the present invention, and is not intended to limit the technical scope of the present invention, so that any minor modifications, equivalent changes and modifications made to the above embodiment according to the technical spirit of the present invention will still fall within the technical scope of the present invention.
Claims (6)
1. A nuclear reactor system for thermoelectric conversion of alkali metal with a molten alloy electrode is characterized by comprising a reactor (1), a high-temperature heat exchanger (2), an electrode chamber, a load (6), a first regenerator (7), a sodium distillation separation chamber (8), a second regenerator (9), a condenser (10) and an electromagnetic pump (11);
the outlet and the inlet of the reactor (1) are respectively connected with the inlet and the outlet of the high-temperature heat exchanger (2);
the electrode chambers comprise a liquid sodium electrode chamber (3), a BASE (4) and a molten alloy electrode chamber (5), wherein the BASE (4) is arranged between the liquid sodium electrode chamber (3) and the molten alloy electrode chamber (5) and is used for separating the liquid sodium electrode chamber (3) from the molten alloy electrode chamber (5);
two ends of the load (6) are respectively connected with the liquid sodium electrode chamber (3) and the molten alloy electrode chamber (5);
the heat absorption side inlet and the heat absorption side outlet of the first heat regenerator (7) are respectively connected with the outlet of the molten alloy electrode chamber (5) and the low-sodium-content molten alloy inlet of the sodium distillation separation chamber (8); a heat release side inlet and a heat release side outlet of the first heat regenerator (7) are respectively connected with a low-sodium-content molten alloy outlet of the sodium distillation separation chamber (8) and an inlet of the molten alloy electrode chamber (5);
the electromagnetic pump (11) is arranged between the heat absorption side inlet of the second regenerator (9) and the heat release side outlet of the condenser (10);
the outlet of the heat absorption side of the second heat regenerator (9) is connected with the inlet of the liquid sodium electrode chamber (3); the heat release side inlet of the second regenerator (9) is connected with the sodium vapor outlet of the sodium distillation separation chamber (8), and the heat release side outlet of the second regenerator (9) is connected with the heat release side inlet of the condenser (10);
the sodium distillation separation chamber (8) is arranged inside the high-temperature heat exchanger (2).
2. A molten alloy electrode alkali metal thermoelectric conversion nuclear reactor system as claimed in claim 1, wherein the reactor (1) is one of a molten salt stack, a lead bismuth stack or a lead-cooled fast stack.
3. A molten alloy electrode alkali metal thermoelectric conversion nuclear reactor system as claimed in claim 1, wherein the alloy located in the molten alloy electrode chamber (5) is lead sodium or tin sodium.
4. A molten alloy electrode alkali metal thermoelectric conversion nuclear reactor system as claimed in claim 1, characterised in that the liquid sodium electrode compartment (3) and the molten alloy electrode compartment (5) are at the same temperature.
5. A molten alloy electrode alkali metal thermoelectric conversion nuclear reactor system as recited in claim 1 wherein the heat absorption side working fluid of said condenser (10) is one of seawater, fresh water or air.
6. The molten alloy electrode alkali-metal thermoelectric conversion nuclear reactor system according to claim 1, wherein a circulation loop constituted by the liquid sodium electrode chamber (3), the BASE (4), the molten alloy electrode chamber (5), the load (6), the first regenerator (7), the sodium distillation separation chamber (8), the second regenerator (9), the condenser (10), and the electromagnetic pump (11) is provided in plural numbers as necessary.
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| Application Number | Priority Date | Filing Date | Title |
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| CN202110241398.8A CN113035382B (en) | 2021-03-04 | 2021-03-04 | Nuclear reactor system for alkali metal thermoelectric conversion of molten alloy electrode |
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| CN202110241398.8A CN113035382B (en) | 2021-03-04 | 2021-03-04 | Nuclear reactor system for alkali metal thermoelectric conversion of molten alloy electrode |
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| CN113035382A CN113035382A (en) | 2021-06-25 |
| CN113035382B true CN113035382B (en) | 2022-06-17 |
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Citations (3)
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| JP2007033128A (en) * | 2005-07-25 | 2007-02-08 | Japan Atomic Energy Agency | Liquid metal-cooled reactor equipped with alkali metal thermoelectric generator |
| CN101630931A (en) * | 2009-08-13 | 2010-01-20 | 哈尔滨工程大学 | Combined power-generation device of nuclear power and alkali metal thermoelectricity conversion device |
| CN111600512A (en) * | 2020-06-04 | 2020-08-28 | 哈尔滨工程大学 | Nuclear reactor power supply system with energy gradient utilization function |
Family Cites Families (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP4008392B2 (en) * | 2003-07-15 | 2007-11-14 | 独立行政法人 日本原子力研究開発機構 | Alkali metal thermoelectric generator |
| CN103277157A (en) * | 2013-05-24 | 2013-09-04 | 成都昊特新能源技术股份有限公司 | Solar ORC power generation system and power generation method thereof |
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- 2021-03-04 CN CN202110241398.8A patent/CN113035382B/en active Active
Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2007033128A (en) * | 2005-07-25 | 2007-02-08 | Japan Atomic Energy Agency | Liquid metal-cooled reactor equipped with alkali metal thermoelectric generator |
| CN101630931A (en) * | 2009-08-13 | 2010-01-20 | 哈尔滨工程大学 | Combined power-generation device of nuclear power and alkali metal thermoelectricity conversion device |
| CN111600512A (en) * | 2020-06-04 | 2020-08-28 | 哈尔滨工程大学 | Nuclear reactor power supply system with energy gradient utilization function |
Non-Patent Citations (2)
| Title |
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| 用于空间堆的碱金属热电转换技术研究;马明阳，等;《航天器工程》;20181231;第27卷(第6期);第102-108页 * |
| 碱金属热电转换器（AMTEC）的新技术;张来福，等;《能源技术》;20010228;第22卷(第1期);第21-23页 * |
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