CN103928064A - Thermally-operated conversion system - Google Patents
Thermally-operated conversion system Download PDFInfo
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- CN103928064A CN103928064A CN201310012278.6A CN201310012278A CN103928064A CN 103928064 A CN103928064 A CN 103928064A CN 201310012278 A CN201310012278 A CN 201310012278A CN 103928064 A CN103928064 A CN 103928064A
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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
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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 belongs to the technical field of nuclear reactor engineering, and in particular relates to a thermally-operated conversion system which adopts lead or lead-bismuth alloy intermediate loops. The system comprises three loops; a first loop comprises a cold pool, a main pump, a reactor core, a thermal pool and an intermediate heat exchanger arranged in a main container and connected in sequence; a second loop comprises a second loop circulating pump, the intermediate heat exchanger and a steam generator connected in sequence; a third loop comprises a water supplying pump, the steam generator and a steam turbine connected in sequence; a working medium of the first loop is liquid metallic sodium, a working medium of the second loop is liquid metallic lead or a liquid lead-bismuth alloy, and the third loop is a conventional water-steam loop. By adopting the system disclosed by the invention, heat generated by the reactor core can be safely and efficiently brought out of a reactor, so that high-temperature steam is generated in the steam generator and used for pushing the steam turbine to apply work, and heat energy generated by the reactor is converted into mechanical energy.
Description
Technical field
The invention belongs to nuclear reactor field of engineering technology, be specifically related to a kind of moving converting system of heat that adopts lead or lead bismuth alloy intermediate loop.
Background technology
The moving converting system of reactor heat is to take cooling medium as carrier, and the heat that reactor core is produced is taken reactor out of, makes it in steam generator, produce high-temperature steam, and pushing turbine acting, and the heat energy that reactor is produced is converted into the system of mechanical energy.
Compare with traditional presurized water reactor, the outstanding feature of fast neutron reactor (hereinafter to be referred as fast reactor) be exactly in heap neutron there is higher energy, make fast reactor there is fertile nuclei fuel and the high ability of putting nuclear waste of transmuting, so just can significantly improve the utilization factor of natural uranium resource, thereby realize the long-term sustainable development of nuclear energy.
Because needs maintain heap in-core harder neutron spectrum, so fast reactor can not use water that moderating power is very strong as cooling medium as presurized water reactor, and fast reactor is used liquid metal sodium as cooling medium conventionally.Because the chemical activity of sodium is stronger, so sodium-cooled fast reactor need to design the main coolant system of sealing, adopts double-deck reactor vessel design more, is filled with inert gas between double container.In heap container, free sodium liquid level top, hot sodium pond is coated with pure inert gas.General three loop designs that adopt of the moving converting system of sodium-cooled fast reactor heat, with the possibility of avoiding radiosodium in a loop directly react with water in three loops or steam generation, even if generation sodium-water reaction can not cause radioactive leak yet like this.Sodium-cooled fast reactor one loop adopts pond formula structure more, and all loop equipment is all positioned at primary tank, and such design has high hot redundancy, has guaranteed the security of reactor core.One loop is comprised of a plurality of loops, and each loop has main pump and intermediate heat exchanger, together with reactor core and sodium pond, forms a loop sodium circulation system.The moving converting system secondary circuit (intermediate loop) of heat also adopts liquid metal sodium as cooling medium, and major equipment comprises secondary sodium pump, steam generator, is positioned at the intermediate heat exchanger of primary tank etc.Three loops are water-steam-return line, steam generator and Turbo-generator Set, consist of, and steam generator is supplied water by feed pump, produce the generating of steam supply Turbo-generator Set.
Although above-mentioned design can avoid a loop sodium directly to reveal, still there is risk of leakage in the sodium in secondary circuit pipeline, and can not avoid occurring in steam generator the risk of sodium-water reaction.For these problems, all must be equipped with corresponding utility appliance, increase the complexity of whole system.
The another kind of design proposal of the moving converting system of fast reactor heat is to adopt lead or lead bismuth alloy as cooling medium.Compare with sodium, lead or lead bismuth alloy advantage are: chemical property is more stable, are difficult for and empty G&W generation chemical reaction, and therefore, Lead cooled fast breeder reactor does not need intermediate loop; Atomic number is high, a little less than neutron moderating power, makes core-spectrum harder, few to harmful absorption of neutron; Lead resource is abundant, and price is not high; In operating condition, have lower vapor pressure, boiling point is higher, makes system simpler, compact; Lead can also effectively shield gamma-rays; Density approaches fuel density, in the situation that reactor core melts, can avoid recovery of critical; Lead can also contain fission product, makes Lead cooled fast breeder reactor have better security; In addition, although plumbous fusing point is very high, lead bismuth alloy has the fusing point close with sodium, can reduce and solidify the risk that reactor is worked the mischief because of cooling medium.
But meanwhile, Lead cooled fast breeder reactor also faces very large challenge: hot physical performance aspect, and than sodium, plumbous heat conductivility is poor; Density is very large, at high temperature has corrosivity, quite serious to the corrosion of structured material, flow velocity and core exit temperature have been limited, cause Lead cooled fast breeder reactor can not reach very high power density, and cause can not there be too high equipment in plumbous loop, in high temperature lead ring border, reload also very difficult; After irradiation, can generate polonium-210, increase radiological hazard.
In sum, there is the deficiencies such as system complex, power density are low in the moving converting system of existing fast reactor heat.
Summary of the invention
The object of the present invention is to provide a kind of heat to move converting system, the heat that this system can be safely, efficiently reactor core is produced is taken reactor out of, make it in steam generator, produce high-temperature steam, and pushing turbine acting, the heat energy that reactor is produced is converted into mechanical energy.
For achieving the above object, the technical solution used in the present invention is:
Heat is moved a converting system, and this system comprises three loops, and a loop comprises and is arranged in primary tank cold drop, main pump, reactor core, Re Chi, the intermediate heat exchanger connecting successively; Secondary circuit comprises secondary circuit ebullator, intermediate heat exchanger, the steam generator connecting successively; Three loops comprise feed pump, steam generator, the steam turbine connecting successively.
A described loop working medium is liquid metal sodium, and secondary circuit working medium is liquid metal lead or lead bismuth alloy, and three loops are traditional water-steam-return line.
The moving converting system heat conduction of described heat detailed process is as follows: in a loop primary tank, main pump sucks liquid metal sodium from cold drop, and liquid metal sodium is flowed through after reactor core is heated and entered Re Chi; Liquid metal sodium in hot pond enters intermediate heat exchanger, and heat is passed to secondary circuit, and cooled liquid metal sodium flows back to cold drop from middle heat exchanger outlet; Liquid metal lead in secondary circuit or lead bismuth alloy flow in intermediate heat exchanger and are heated; Liquid metal lead after heating or lead bismuth alloy enter steam generator heat are passed to three loops, and cooled liquid metal lead or lead bismuth alloy will again enter intermediate heat exchanger after secondary circuit ebullator; Three loop feedwater enter steam generator heating through feed pump and produce superheated vapor, the acting of Steam Actuation steam turbine, and the heat energy that reactor is produced is converted into mechanical energy.
The obtained beneficial effect of the present invention is:
A kind of heat of the present invention is moved converting system, can be safely, the heat that efficiently reactor core produced takes reactor out of, makes it in steam generator, produce high-temperature steam, and pushing turbine acting, the heat energy that reactor is produced is converted into mechanical energy.This system has following characteristics:
(1) one loop adopts liquid metal sodium as cooling medium, has good heat conductivility and very high hot redundancy;
(2) secondary circuit adopts liquid metal lead or lead bismuth alloy as cooling medium, and stable chemical nature, even if leakage hazard is also little;
(3) liquid metal lead or lead bismuth alloy do not react with water or steam generation, have guaranteed the security of steam generator;
(4) at high temperature, liquid metal sodium reacts with liquid metal lead or lead bismuth alloy and can generate dystectic solid product, even if intermediate heat exchanger leaks, welding effect also can block cut certainly, the integrality that keeps a loop, system is more safe and reliable;
(5), in this system, liquid metal lead or lead bismuth alloy, without reactor core, have reduced the radiological hazard that bring generation polonium-210;
(6) one loops and secondary circuit are all closed loops, only have exchange heat with the external world, do not have leaking of radiomaterial.
Accompanying drawing explanation
Fig. 1 is the moving converting system structural drawing of heat of the present invention;
In figure: 1, cold drop; 2, Re Chi; 3, main pump; 4, reactor core; 5, intermediate heat exchanger; 6, liquid metal sodium; 7, secondary circuit ebullator; 8, lead bismuth alloy; 9, steam generator; 10, steam turbine; 11, feed pump; 12, primary tank.
Embodiment
Below in conjunction with the drawings and specific embodiments, the present invention is described in detail.
As shown in Figure 1, the moving converting system of a kind of heat of the present invention comprises three loops, and a loop comprises and is arranged on cold drop 1, main pump 3, reactor core 4, hot pond 2, the intermediate heat exchanger 5 connecting successively in primary tank 12; Secondary circuit comprises secondary circuit ebullator 7, intermediate heat exchanger 5, the steam generator 9 connecting successively; Three loops comprise feed pump 11, steam generator 9, the steam turbine 10 connecting successively; One loop working medium is liquid metal sodium 6, and secondary circuit working medium is that liquid metal lead or lead bismuth alloy 8, three loops are traditional water-steam-return line;
The moving converting system heat conduction of this heat detailed process is as follows:
In a loop primary tank 12, main pump 3 sucks liquid metal sodium 6 from cold drop 1, and liquid metal sodium 6 is flowed through after reactor core 4 is heated and entered hot pond 2; Liquid metal sodium 6 in hot pond enters intermediate heat exchanger 5, and heat is passed to secondary circuit, and cooled liquid metal sodium 6 flows back to cold drop 1 from intermediate heat exchanger 5 outlets; Liquid metal lead in secondary circuit or lead bismuth alloy 8 flow in intermediate heat exchanger 5 and are heated; Liquid metal lead after heating or lead bismuth alloy 8 enter steam generator 9 heat are passed to three loops, and cooled liquid metal lead or lead bismuth alloy 8 will again enter intermediate heat exchanger 5 after secondary circuit ebullator 7; Three loop feedwater enter steam generator 9 heating through feed pump 11 and produce superheated vapor, 10 actings of Steam Actuation steam turbine, and the heat energy that reactor is produced is converted into mechanical energy.
Claims (3)
1. the moving converting system of heat, is characterized in that: this system comprises three loops, and a loop comprises and is arranged on cold drop (1), main pump (3), reactor core (4), hot pond (2), the intermediate heat exchanger (5) connecting successively in primary tank (12); Secondary circuit comprises secondary circuit ebullator (7), intermediate heat exchanger (5), the steam generator (9) connecting successively; Three loops comprise feed pump (11), steam generator (9), the steam turbine (10) connecting successively.
2. the moving converting system of heat according to claim 1, is characterized in that: a described loop working medium is liquid metal sodium (6), and secondary circuit working medium is liquid metal lead or lead bismuth alloy (8), and three loops are traditional water-steam-return line.
3. heat according to claim 2 is moved converting system, it is characterized in that: the moving converting system heat conduction of described heat detailed process is as follows: in a loop primary tank (12), main pump (3) sucks liquid metal sodium (6) from cold drop (1), and liquid metal sodium (6) is flowed through after reactor core (4) is heated and entered Re Chi (2); Liquid metal sodium in hot pond (6) enters intermediate heat exchanger (5), and heat is passed to secondary circuit, and cooled liquid metal sodium (6) flows back to cold drop (1) from intermediate heat exchanger (5) outlet; Liquid metal lead in secondary circuit or lead bismuth alloy (8) flow in intermediate heat exchanger (5) and are heated; Liquid metal lead after heating or lead bismuth alloy (8) enter steam generator (9) heat are passed to three loops, and cooled liquid metal lead or lead bismuth alloy (8) will again enter intermediate heat exchanger (5) after secondary circuit ebullator (7); Three loop feedwater enter steam generator (9) heating through feed pump (11) and produce superheated vapor, Steam Actuation steam turbine (10) acting, and the heat energy that reactor is produced is converted into mechanical energy.
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Cited By (15)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104200852A (en) * | 2014-09-16 | 2014-12-10 | 中国科学院合肥物质科学研究院 | Condensed liquid heavy metal choke valve |
| CN104409109A (en) * | 2014-09-26 | 2015-03-11 | 吕应中 | Ultrahigh specific power thermal neutron thorium breeder reactor apparatus and method for nuclear fuel propagation |
| CN104409115A (en) * | 2014-12-17 | 2015-03-11 | 中国科学院合肥物质科学研究院 | Complex device for auxiliary heating and waste heat discharging of pool-type liquid heavy metal cooled reactor |
| CN104658620A (en) * | 2015-02-05 | 2015-05-27 | 中国科学院合肥物质科学研究院 | Main loop circulating device for pool type liquid heavy metal cooling reactor |
| CN105225715A (en) * | 2015-08-24 | 2016-01-06 | 中国科学院合肥物质科学研究院 | A kind of trunk type nuclear energy power generation device based on Stirling cycle |
| CN105261404A (en) * | 2015-11-19 | 2016-01-20 | 中国核动力研究设计院 | Sodium cooled fast reactor power generation system using supercritical carbon dioxide working medium |
| CN106653105A (en) * | 2016-12-29 | 2017-05-10 | 中科瑞华原子能源技术有限公司 | Small-sized movable nuclear reactor double-container support system |
| CN106847350A (en) * | 2017-02-13 | 2017-06-13 | 中国科学院合肥物质科学研究院 | A kind of liquid-metal cooled reactor integrated test set |
| CN107464588A (en) * | 2016-06-03 | 2017-12-12 | 泰拉能源有限责任公司 | Internal container for reactor |
| CN108122623A (en) * | 2017-12-25 | 2018-06-05 | 中国科学院合肥物质科学研究院 | A kind of deep-sea nuclear power apparatus |
| CN109737365A (en) * | 2018-12-29 | 2019-05-10 | 中核霞浦核电有限公司 | A kind of cuboid sodium-sodium-water one steam generator |
| CN111415764A (en) * | 2020-03-29 | 2020-07-14 | 孙厚才 | Nuclear energy thermodynamic system with pressure monitoring and emergency waste heat discharging functions |
| CN111899903A (en) * | 2019-05-05 | 2020-11-06 | 中国科学院理化技术研究所 | Liquid metal reactor, liquid metal power generation device and liquid metal heat exchange device |
| CN113744899A (en) * | 2021-06-02 | 2021-12-03 | 上海核工程研究设计院有限公司 | Starting heating system of nuclear reactor |
| CN116378794A (en) * | 2023-03-29 | 2023-07-04 | 中国原子能科学研究院 | Reactor fused salt energy storage power generation system |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN104200852B (en) * | 2014-09-16 | 2017-01-25 | 中国科学院合肥物质科学研究院 | Condensed liquid heavy metal choke valve |
| CN104200852A (en) * | 2014-09-16 | 2014-12-10 | 中国科学院合肥物质科学研究院 | Condensed liquid heavy metal choke valve |
| CN104409109A (en) * | 2014-09-26 | 2015-03-11 | 吕应中 | Ultrahigh specific power thermal neutron thorium breeder reactor apparatus and method for nuclear fuel propagation |
| CN104409115A (en) * | 2014-12-17 | 2015-03-11 | 中国科学院合肥物质科学研究院 | Complex device for auxiliary heating and waste heat discharging of pool-type liquid heavy metal cooled reactor |
| CN104658620A (en) * | 2015-02-05 | 2015-05-27 | 中国科学院合肥物质科学研究院 | Main loop circulating device for pool type liquid heavy metal cooling reactor |
| CN105225715A (en) * | 2015-08-24 | 2016-01-06 | 中国科学院合肥物质科学研究院 | A kind of trunk type nuclear energy power generation device based on Stirling cycle |
| CN105225715B (en) * | 2015-08-24 | 2017-12-19 | 中国科学院合肥物质科学研究院 | A kind of trunk type nuclear energy power generation device based on Stirling cycle |
| CN105261404A (en) * | 2015-11-19 | 2016-01-20 | 中国核动力研究设计院 | Sodium cooled fast reactor power generation system using supercritical carbon dioxide working medium |
| CN107464588A (en) * | 2016-06-03 | 2017-12-12 | 泰拉能源有限责任公司 | Internal container for reactor |
| CN106653105A (en) * | 2016-12-29 | 2017-05-10 | 中科瑞华原子能源技术有限公司 | Small-sized movable nuclear reactor double-container support system |
| CN106653105B (en) * | 2016-12-29 | 2017-10-13 | 中科瑞华原子能源技术有限公司 | A kind of removable nuclear reactor twin containers support system |
| CN106847350B (en) * | 2017-02-13 | 2017-12-12 | 中国科学院合肥物质科学研究院 | A kind of liquid-metal cooled reactor integrated test set |
| CN106847350A (en) * | 2017-02-13 | 2017-06-13 | 中国科学院合肥物质科学研究院 | A kind of liquid-metal cooled reactor integrated test set |
| CN108122623A (en) * | 2017-12-25 | 2018-06-05 | 中国科学院合肥物质科学研究院 | A kind of deep-sea nuclear power apparatus |
| CN108122623B (en) * | 2017-12-25 | 2020-10-16 | 中国科学院合肥物质科学研究院 | Deep sea nuclear power device |
| CN109737365A (en) * | 2018-12-29 | 2019-05-10 | 中核霞浦核电有限公司 | A kind of cuboid sodium-sodium-water one steam generator |
| CN111899903A (en) * | 2019-05-05 | 2020-11-06 | 中国科学院理化技术研究所 | Liquid metal reactor, liquid metal power generation device and liquid metal heat exchange device |
| CN111415764A (en) * | 2020-03-29 | 2020-07-14 | 孙厚才 | Nuclear energy thermodynamic system with pressure monitoring and emergency waste heat discharging functions |
| CN113744899A (en) * | 2021-06-02 | 2021-12-03 | 上海核工程研究设计院有限公司 | Starting heating system of nuclear reactor |
| CN116378794A (en) * | 2023-03-29 | 2023-07-04 | 中国原子能科学研究院 | Reactor fused salt energy storage power generation system |
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