CN103928064B - Thermally-operated conversion system - Google Patents
Thermally-operated conversion system Download PDFInfo
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- CN103928064B CN103928064B CN201310012278.6A CN201310012278A CN103928064B CN 103928064 B CN103928064 B CN 103928064B CN 201310012278 A CN201310012278 A CN 201310012278A CN 103928064 B CN103928064 B CN 103928064B
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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, and in particular to a kind of employing lead or lead bismuth alloy intermediate loop
The dynamic converting system of heat.
Background technology
The dynamic converting system of reactor heat is, with coolant as carrier, the heat that reactor core is produced to be taken out of reactor,
It is set to produce high-temperature steam in a vapor generator, and pushing turbine does work, and the heat energy that reactor is produced is converted into into machinery
The system of energy.
Compared with conventional pressurized water heap, fast neutron reactor（Hereinafter referred to as fast reactor）Most outstanding feature is exactly neutron tool in heap
There is higher energy, the ability for making fast reactor that there is propagation nuclear fuel and transmuting height to put nuclear waste thus can be significantly improved natural
The utilization rate of uranium resource, so as to the long-term sustainable for realizing nuclear energy develops.
Due to the neutron energy spectrum for needing to maintain heap in-core harder, therefore fast reactor can not use moderating power as presurized water reactor
Used as coolant, usual fast reactor uses liquid metal sodium as coolant to very strong water.Due to the chemism of sodium it is stronger, therefore
Sodium-cooled fast reactor needs the main coolant system of design sealing, more using double-deck reactor vessel design, is filled between double container
Noble gases.The free sodium ullage in heap container interior-heat sodium pond is coated with pure noble gases.The dynamic conversion system of sodium-cooled fast reactor heat
As unification using three loops design, with avoid the radiosodium in primary Ioops directly with three loops in water or steam generation reaction
Possibility, accordingly even when occur sodium-water reaction be also not result in escape of radioactivity.Pool structure is adopted sodium-cooled fast reactor primary Ioops more,
All primary Ioops equipment are respectively positioned in primary tank, and such design has high hot redundancy, it is ensured that the safety of reactor core.One time
Multiple loop compositions are route, each loop is equipped with main pump and intermediate heat exchanger, together with reactor core and sodium pond composition primary Ioops sodium
Blood circulation.The dynamic converting system secondary circuit of heat（Intermediate loop）Liquid metal sodium is also adopted by as coolant, capital equipment includes
Secondary sodium pump, steam generator, intermediate heat exchanger in primary tank etc..Three loops are water-steam-return line, are sent out by steam
Raw device and Turbo-generator Set composition, steam generator is produced steam supply Turbo-generator Set and is generated electricity by the water supplying pump that feeds water.
Although above-mentioned design can avoid primary Ioops sodium from directly revealing, still there is leakage wind in the sodium in secondary circuit pipeline
Danger, and cannot be avoided the risk that sodium-water reaction occurs in steam generator.All must be equipped with for these problems corresponding auxiliary
Equipment is helped, the complexity of whole system is increased.
The dynamic converting system another kind design of fast reactor heat is as coolant using lead or lead bismuth alloy.Compared with sodium,
Lead or lead bismuth alloy advantage are：Chemical property is more stable, is difficult that chemical reaction occurs with air and water, therefore, Lead cooled fast breeder reactor
Intermediate loop is not needed；Atomic number is high, weak to neutron moderating power, makes core-spectrum harder, few to the unwanted absorption of neutron；
Lead resource enriches, inexpensive；There is relatively low steam pressure in operating condition, boiling point is higher, make system simpler, compact；
Lead can also effectively shield gamma-rays；The close fuel density of density, in the case where reactor core melts recovery of critical is avoided that；Lead is also
Fission product can be contained, make Lead cooled fast breeder reactor that there is more preferable safety；Additionally, although the fusing point of lead is very high, lead bismuth alloy
With the fusing point close with sodium, the risk worked the mischief to reactor because of coolant solidification can be reduced.
But meanwhile, Lead cooled fast breeder reactor also faces very big challenge：Hot physical performance aspect, compared to sodium, the heat conductivility of lead compared with
Difference；Density is very big, and at high temperature with corrosivity, the corrosion to structural material is quite serious, limits flow velocity and core exit
Temperature, causes Lead cooled fast breeder reactor to reach very high power density, and causes can not have too high equipment, high temperature in lead loop
Reloaded in lead ring border also highly difficult；Polonium -210 can be generated after irradiation, increases radiological hazard.
In sum, there is the low deficiency of system complex, power density in the dynamic converting system of existing fast reactor heat.
The content of the invention
It is an object of the invention to provide a kind of heat moves converting system, the system can produce reactor core with safe and efficient
Heat take reactor out of so as to produce high-temperature steam in a vapor generator, and pushing turbine does work, and reactor is produced
Heat energy be converted into mechanical energy.
To reach above-mentioned purpose, the technical solution used in the present invention is：
A kind of heat moves converting system, and the system includes three loops, and primary Ioops include being arranged in primary tank being sequentially connected
Cold drop, main pump, reactor core, Re Chi, intermediate heat exchanger；Secondary circuit includes that the secondary circuit circulating pump being sequentially connected, intermediate heat are handed over
Parallel operation, steam generator；Three loops include feed pump, steam generator, the steam turbine being sequentially connected.
The primary Ioops 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.
It is as follows that the heat moves converting system heat conduction detailed process：In primary Ioops primary tank, main pump is inhaled from cold drop
Enter liquid metal sodium, liquid metal sodium is flowed through after reactor core is heated and enters hot pond；Liquid metal sodium in hot pond enters intermediate heat
Exchanger, transfers heat to secondary circuit, and the liquid metal sodium after cooling flows back to cold drop from middle heat exchanger outlet；Secondary circuit
In liquid metal lead or lead bismuth alloy flow into intermediate heat exchanger in be heated；Liquid metal lead or lead bismuth alloy after heating
Three loops are transferred heat to into steam generator, the liquid metal lead or lead bismuth alloy after cooling is through secondary circuit circulating pump
After will be again introduced into intermediate heat exchanger；The feedwater of three loops enters steam generator heating and produces superheated steam through feed pump,
Steam Actuation steam turbine is done work, and the heat energy that reactor is produced is converted into into mechanical energy.
Having the beneficial effect that acquired by the present invention：
A kind of heat of the present invention moves converting system, the heat that reactor core is produced can be taken out of reactor with safe and efficient,
It is set to produce high-temperature steam in a vapor generator, and pushing turbine does work, and the heat energy that reactor is produced is converted into into machinery
Energy.The system has the characteristics that：
（1）Primary Ioops adopt liquid metal sodium as coolant, with good heat conductivility and very high hot redundancy；
（2）Secondary circuit is using liquid metal lead or lead bismuth alloy as coolant, stable chemical nature, even if leakage hazard
Also it is little；
（3）Liquid metal lead or lead bismuth alloy do not react with water or steam generation, it is ensured that the safety of steam generator；
（4）At high temperature, liquid metal sodium can generate dystectic solid and produce with liquid metal lead or lead bismuth alloy reaction
Thing, even if intermediate heat exchanger is leaked, can also block cut from welding effect, keep the integrity of primary Ioops, system
It is more safe and reliable；
（5）In the system, liquid metal lead or lead bismuth alloy reduce the radiation that generation polonium -210 brings without reactor core
Property harm；
（6）Primary Ioops and secondary circuit are all closed circuits, there was only heat exchange with extraneous, do not have radioactive substance
Leak.
Description of the drawings
Fig. 1 is the dynamic conversion system structure figure of heat of the present invention；
In figure：1st, cold drop；2nd, Re Chi；3rd, main pump；4th, reactor core；5th, intermediate heat exchanger；6th, liquid metal sodium；7th, secondary circuit
Circulating pump；8th, lead bismuth alloy；9th, steam generator；10th, steam turbine；11st, feed pump；12nd, primary tank.
Specific embodiment
Below in conjunction with the accompanying drawings the present invention is described in detail with specific embodiment.
As shown in figure 1, a kind of heat of the present invention moves converting system includes three loops, primary Ioops include being arranged on main appearance
Cold drop 1, main pump 3, reactor core 4, hot pond 2, the intermediate heat exchanger 5 being sequentially connected in device 12；Secondary circuit includes two for being sequentially connected
Loop circulator pump 7, intermediate heat exchanger 5, steam generator 9；Three loops include the feed pump 11, steam generator being sequentially connected
9th, steam turbine 10；Primary Ioops 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；
The dynamic converting system heat conduction detailed process of the heat is as follows：
In primary Ioops primary tank 12, main pump 3 sucks liquid metal sodium 6 from cold drop 1, and liquid metal sodium 6 flows through reactor core 4
Hot pond 2 is entered after being heated；Liquid metal sodium 6 in hot pond enters intermediate heat exchanger 5, transfers heat to secondary circuit, cold
But the liquid metal sodium 6 after flows back to cold drop 1 from the outlet of intermediate heat exchanger 5；Liquid metal lead or lead bismuth alloy 8 in secondary circuit
Flow in intermediate heat exchanger 5 and be heated；Liquid metal lead or lead bismuth alloy 8 after heating enters steam generator 9 by heat
Three loops are transferred to, the liquid metal lead or lead bismuth alloy 8 after cooling will be again introduced into intermediate heat after secondary circuit circulating pump 7
Exchanger 5；The feedwater of three loops enters the heating of steam generator 9 and produces superheated steam, Steam Actuation steam turbine through feed pump 11
10 actings, by the heat energy that reactor is produced mechanical energy is converted into.
Claims (2)
1. a kind of heat moves converting system, it is characterised in that：The system includes three loops, and primary Ioops include being arranged on primary tank
(12) cold drop (1), main pump (3), reactor core (4), hot pond (2), the intermediate heat exchanger (5) being sequentially connected in；Secondary circuit include according to
The secondary circuit circulating pump (7) of secondary connection, intermediate heat exchanger (5), steam generator (9)；Three loops include be sequentially connected to
Water pump (11), steam generator (9), steam turbine (10)；The primary Ioops working medium is liquid metal sodium (6), and secondary circuit working medium is
Liquid metal lead or lead bismuth alloy (8), three loops are traditional water-steam-return line.
2. heat according to claim 1 moves converting system, it is characterised in that：It is concrete that the heat moves the conduction of converting system heat
Process is as follows：In primary Ioops primary tank (12), main pump (3) suction liquid metal sodium (6), liquid metal sodium from cold drop (1)
(6) flow through after reactor core (4) is heated and enter hot pond (2)；Liquid metal sodium (6) in hot pond, will into intermediate heat exchanger (5)
Heat transfer to secondary circuit, the liquid metal sodium (6) after cooling flow back to cold drop (1) from intermediate heat exchanger (5) outlet；Secondary circuit
In liquid metal lead or lead bismuth alloy (8) flow in intermediate heat exchanger (5) and be heated；Liquid metal lead or lead after heating
Bismuth alloy (8) transfers heat to three loops into steam generator (9), the liquid metal lead or lead bismuth alloy (8) after cooling
Intermediate heat exchanger (5) will be again introduced into after secondary circuit circulating pump (7)；The feedwater of three loops is entered through feed pump (11) steams
Vapour generator (9) heating produces superheated steam, and the heat energy that reactor is produced is converted into machine by Steam Actuation steam turbine (10) acting
Tool energy.
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| Application Number | Priority Date | Filing Date | Title |
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| CN201310012278.6A CN103928064B (en) | 2013-01-14 | 2013-01-14 | Thermally-operated conversion system |
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| Application Number | Priority Date | Filing Date | Title |
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| CN201310012278.6A CN103928064B (en) | 2013-01-14 | 2013-01-14 | Thermally-operated conversion system |
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| CN103928064A CN103928064A (en) | 2014-07-16 |
| CN103928064B true CN103928064B (en) | 2017-05-17 |
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| CN104409115B (en) * | 2014-12-17 | 2016-11-30 | 中国科学院合肥物质科学研究院 | A kind of auxiliary for pool liquid heavy metal cooled reactor heats and Residual heat removal hybrid device |
| CN104658620B (en) * | 2015-02-05 | 2017-03-01 | 中国科学院合肥物质科学研究院 | A kind of major loop circulating device for pool liquid heavy metal cooled reactor |
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| 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 |
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| 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 |
| 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 |
| CN109737365B (en) * | 2018-12-29 | 2020-10-23 | 中核霞浦核电有限公司 | Cuboid sodium-water integrated 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 |
| 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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| CN1039141A (en) * | 1989-08-24 | 1990-01-24 | 清华大学 | Forced-natural circulation bath-type heat-supplying reactor |
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| CN103928064A (en) | 2014-07-16 |
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Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee after: Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd. Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE |