CN203070789U - Thermally-operated conversion system - Google Patents
Thermally-operated conversion system Download PDFInfo
- Publication number
- CN203070789U CN203070789U CN2013200171665U CN201320017166U CN203070789U CN 203070789 U CN203070789 U CN 203070789U CN 2013200171665 U CN2013200171665 U CN 2013200171665U CN 201320017166 U CN201320017166 U CN 201320017166U CN 203070789 U CN203070789 U CN 203070789U
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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 utility model belongs to the technical field of engineering of nuclear reactors and in particular relates to a thermally-operated conversion system which adopts lead or lead-bismuth alloy intermediate loops. The system disclosed by the utility model comprises three loops, wherein 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, an intermediate heat exchanger and a steam generator connected in sequence; a third loop comprises a water supplying pump, a 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 lead-bismuth alloy; and the third loop is a conventional water-steam loop. By adopting the system disclosed by the utility model, heat generated by the reactor core is safely and efficiently taken out of the reactor, so that high-temperature steam is generated in the steam generator and used for pushing the steam turbine to work and convert heat energy generated by the reactor into mechanical energy.
Description
Technical field
The utility model belongs to the nuclear reactor field of engineering technology, is 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 be carrier with the cooling medium, and the heat that reactor core produces is taken out of reactor, makes it produce high-temperature steam in steam generator, and the pushing turbine acting, the heat energy of reactor generation 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 the heap neutron have higher energy, make fast reactor have the ability that fertile nuclei fuel and transmuting height are put nuclear waste, so just can significantly improve the utilization factor of natural uranium resource, thereby realize the long-term sustainable development of nuclear energy.
Owing to need keep neutron spectrum harder in the reactor core, so fast reactor can not use the very strong water of moderating power as cooling medium as presurized water reactor, and fast reactor uses liquid metal sodium as cooling medium usually.Because the chemical activity of sodium is stronger, so sodium-cooled fast reactor need design the main coolant system of sealing, adopts double-deck reactor vessel design more, charges into inert gas between the double container.Free sodium liquid level top, hot sodium pond is coated with pure inert gas in the heap container.The moving converting system of sodium-cooled fast reactor heat is general to adopt the design of three loops, with avoid in the loop radiosodium directly with three loops in water or the steam generation reaction may, even the generation sodium-water reaction can not cause radioactive leak yet like this.Pond formula structure is adopted in sodium-cooled fast reactor one loop more, and all loop equipment all are positioned at primary tank, and it is redundant that such design has high heat, guaranteed the security of reactor core.One loop is made up of a plurality of loops, and each loop has main pump and intermediate heat exchanger, forms a loop sodium circulation system together with reactor core and sodium pond.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, are made up of steam generator and Turbo-generator Set, and steam generator is supplied water by feed pump, produce steam and supply with the Turbo-generator Set generating.
Though above-mentioned design can avoid a loop sodium directly to reveal, still there is risk of leakage in the sodium in the secondary circuit pipeline, and can not avoid taking place in the steam generator risk of sodium-water reaction.All must be equipped with corresponding utility appliance at these problems, increase the complexity of total 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, is difficult for and empty G﹠W generation chemical reaction, and therefore, plumbous cold fast reactor does not need intermediate loop; The atomic number height a little less than the neutron moderating power, makes core-spectrum harder, and is few to harmful absorption of neutron; Lead resource is abundant, and price is not high; Lower vapor pressure is arranged in operating condition, and boiling point is higher, makes system simpler, compact; Lead can also effectively shield gamma-rays; Density can be avoided recovery of critical near fuel density under the situation that reactor core melts; Lead can also contain fission product, makes plumbous cold fast 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 because of cooling medium to solidify the risk that reactor is worked the mischief.
But simultaneously, plumbous cold fast reactor also faces very big challenge: hot rerum natura energy aspect, and than sodium, plumbous heat conductivility is relatively poor; Density is very big, at high temperature has corrosivity, and is quite serious to the corrosion of structured material, flow velocity and core exit temperature have been limited, cause plumbous cold fast reactor can not reach very high power density, and cause in the plumbous loop too high equipment being arranged, it is also very difficult to reload in the high temperature lead ring border; Can generate polonium-210 behind the irradiation, increase radiological hazard.
In sum, there are deficiencies such as system complex, power density are low in the moving converting system of existing fast reactor heat.
Summary of the invention
The purpose of this utility model 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 the pushing turbine acting, the heat energy that reactor is produced is converted into mechanical energy.
For achieving the above object, technical solution adopted in the utility model is:
A kind of heat is moved converting system, and this system comprises three loops, and a loop comprises and is arranged in the primary tank cold drop, main pump, reactor core, Re Chi, the intermediate heat exchanger that connects successively; Secondary circuit comprises secondary circuit ebullator, intermediate heat exchanger, the steam generator that connects successively; Three loops comprise feed pump, steam generator, the steam turbine that connects 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 obtained beneficial effect of the utility model is:
A kind of heat described in the utility model is moved converting system, can be safely, the heat that efficiently reactor core produced takes reactor out of, makes it produce high-temperature steam in steam generator, and the 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-conducting and very high heat redundancy;
(2) secondary circuit adopts liquid metal lead or lead bismuth alloy as cooling medium, and chemical property is stable, even 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 and liquid metal lead or lead bismuth alloy reaction can generate dystectic solid product, even intermediate heat exchanger leaks, the welding effect also can be blocked up cut certainly, keep the integrality in a loop, system is more safe and reliable;
(5) in this system, liquid metal lead or lead bismuth alloy have reduced the radiological hazard that generation polonium-210 brings without reactor core;
(6) one loops and secondary circuit all are closed loops, have only exchange heat with the external world, do not have leaking of radiomaterial.
Description of drawings
Fig. 1 is the moving converting system structural drawing of heat described in the utility model;
Among the 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 utility model is elaborated.
As shown in Figure 1, the moving converting system of a kind of heat described in the utility model 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 that connects successively in the primary tank 12; Secondary circuit comprises secondary circuit ebullator 7, intermediate heat exchanger 5, the steam generator 9 that connects successively; Three loops comprise feed pump 11, steam generator 9, the steam turbine 10 that connects 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 and entered hot pond 2 after reactor core 4 is heated; Liquid metal sodium 6 in the 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 middle heat exchanger 5 outlets; Liquid metal lead in the secondary circuit or lead bismuth alloy 8 flow in the intermediate heat exchanger 5 and are heated; Liquid metal lead after the heating or lead bismuth alloy 8 enter steam generator 9 heat are passed to three loops, will enter intermediate heat exchanger 5 again behind cooled liquid metal lead or the lead bismuth alloy 8 process secondary circuit ebullators 7; The feedwater of three loops enters steam generator 9 heating through feed pump 11 and produces superheated vapor, 10 actings of steam pushing turbine, and the heat energy that reactor is produced is converted into mechanical energy.
Claims (2)
1. the moving converting system of a heat, it is characterized in that: this system comprises three loops, a loop comprises and is arranged on cold drop (1), main pump (3), reactor core (4), hot pond (2), the intermediate heat exchanger (5) that connects successively in the primary tank (12); Secondary circuit comprises secondary circuit ebullator (7), intermediate heat exchanger (5), the steam generator (9) that connects successively; Three loops comprise feed pump (11), steam generator (9), the steam turbine (10) that connects successively.
2. heat according to claim 1 is moved converting system, and it 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.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2013200171665U CN203070789U (en) | 2013-01-14 | 2013-01-14 | Thermally-operated conversion system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2013200171665U CN203070789U (en) | 2013-01-14 | 2013-01-14 | Thermally-operated conversion system |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN203070789U true CN203070789U (en) | 2013-07-17 |
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| Application Number | Title | Priority Date | Filing Date |
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| CN2013200171665U Withdrawn - After Issue CN203070789U (en) | 2013-01-14 | 2013-01-14 | Thermally-operated conversion system |
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| CN (1) | CN203070789U (en) |
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103839600A (en) * | 2014-03-18 | 2014-06-04 | 中国科学院合肥物质科学研究院 | Flow measurement device and flow measurement method for pond type natural circulation reactor |
| CN103928064A (en) * | 2013-01-14 | 2014-07-16 | 上海核工程研究设计院 | Thermally-operated conversion system |
| CN106531247A (en) * | 2016-12-23 | 2017-03-22 | 中国核动力研究设计院 | Spraying type condensation device and reactor simulation test device secondary circuit system formed by same |
| CN107110486A (en) * | 2014-12-19 | 2017-08-29 | 韩国生产技术研究院 | Electricity generation system using liquid metal as the boiler of working media and including it |
| CN108518663A (en) * | 2018-03-30 | 2018-09-11 | 清华大学天津高端装备研究院 | A kind of steam generator and nuclear equipment suitable for lead bismuth heap |
-
2013
- 2013-01-14 CN CN2013200171665U patent/CN203070789U/en not_active Withdrawn - After Issue
Cited By (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103928064A (en) * | 2013-01-14 | 2014-07-16 | 上海核工程研究设计院 | Thermally-operated conversion system |
| CN103928064B (en) * | 2013-01-14 | 2017-05-17 | 上海核工程研究设计院 | Thermally-operated conversion system |
| CN103839600A (en) * | 2014-03-18 | 2014-06-04 | 中国科学院合肥物质科学研究院 | Flow measurement device and flow measurement method for pond type natural circulation reactor |
| CN103839600B (en) * | 2014-03-18 | 2016-03-02 | 中国科学院合肥物质科学研究院 | A kind of flow measurement device for pool natural circulation reactor and measuring method |
| CN107110486A (en) * | 2014-12-19 | 2017-08-29 | 韩国生产技术研究院 | Electricity generation system using liquid metal as the boiler of working media and including it |
| US10605448B2 (en) | 2014-12-19 | 2020-03-31 | Korea Institute Of Industrial Technology | Boiler using liquid metal as working medium and power generation system comprising same |
| CN106531247A (en) * | 2016-12-23 | 2017-03-22 | 中国核动力研究设计院 | Spraying type condensation device and reactor simulation test device secondary circuit system formed by same |
| CN108518663A (en) * | 2018-03-30 | 2018-09-11 | 清华大学天津高端装备研究院 | A kind of steam generator and nuclear equipment suitable for lead bismuth heap |
| CN108518663B (en) * | 2018-03-30 | 2019-10-29 | 清华大学天津高端装备研究院 | A kind of steam generator and nuclear equipment suitable for lead bismuth heap |
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| Date | Code | Title | Description |
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| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| AV01 | Patent right actively abandoned |
Granted publication date: 20130717 Effective date of abandoning: 20170517 |
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| AV01 | Patent right actively abandoned |