CN205028667U - Thermoelectric cogeneration system of marine nuclear energy - Google Patents
Thermoelectric cogeneration system of marine nuclear energy Download PDFInfo
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- CN205028667U CN205028667U CN201520682747.XU CN201520682747U CN205028667U CN 205028667 U CN205028667 U CN 205028667U CN 201520682747 U CN201520682747 U CN 201520682747U CN 205028667 U CN205028667 U CN 205028667U
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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
- Y02E20/00—Combustion technologies with mitigation potential
- Y02E20/14—Combined heat and power generation [CHP]
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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
- Y02P—CLIMATE CHANGE MITIGATION TECHNOLOGIES IN THE PRODUCTION OR PROCESSING OF GOODS
- Y02P80/00—Climate change mitigation technologies for sector-wide applications
- Y02P80/10—Efficient use of energy, e.g. using compressed air or pressurized fluid as energy carrier
- Y02P80/15—On-site combined power, heat or cool generation or distribution, e.g. combined heat and power [CHP] supply
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Abstract
The utility model relates to a thermoelectric cogeneration system of marine nuclear energy, its characterized in that: steam turbine, catch water, condenser, condensate pump, low pressure feed water heater, oxygen -eliminating device, user heat exchanger, main feed pump and generator that it includes nuclear reactor in the marine floating nuclear power plant, steam generator, comprises steam turbine high pressure cylinder and steam turbine low pressure jar, nuclear reactor passes through the pipeline and is connected with steam generator, steam generator's export and steam turbine high pressure cylinder are connected, and after steam turbine high pressure cylinder one end connected gradually catch water, steam turbine low pressure jar, condenser, condensate pump, low pressure feed water heater, oxygen -eliminating device and main feed pump, with steam generator's entry linkage, wherein the generator passed through the pipeline and is connected with steam turbine high pressure cylinder and steam turbine low pressure jar respectively, drives the generator electricity generation by steam turbine high pressure cylinder and steam turbine low pressure jar. The back is connected with user heat exchanger, oxygen -eliminating device and main feed pump in proper order to the steam turbine high pressure cylinder other end, with steam generator's entry linkage. The utility model discloses can the wide application in the development field of offshore oil and gas field.
Description
Technical field
The utility model relates to nuclear energy technology application, particularly about the marine nuclear energy thermoelectric co-generation system of one.
Background technology
Along with China constantly strengthens the oil to coastal waters, the development and utilization of natural gas source, marine oil and gas exploitation electric power supply problem becomes increasingly conspicuous.Because each exploitation of oil-gas field in sea needs a large amount of electric power, and for a large amount of vapours of need of viscous oil recovery, the crude oil that adopts carries out generating electricity and heat supply as fuel more both at home and abroad at present.There is following problem in this power supply heat-supplying mode: 1, due to conventional offshore oil and gas field exploitation pattern, to be substantially that each oil gas field central platform or floating production storage unit build a power station independently-powered.Be converted into heat energy by fuel oil, combustion gas or electrical heating, the thermal efficiency is low.2, genset adopts fossil fuel, and cost of electricity-generating is higher.3, adopt burning crude oil to produce heat energy, be unfavorable for energy-saving and emission-reduction, marine environment is polluted.4, power station power supply capacity is less than normal, is unfavorable for the Oilfield Group rolling development in later stage, affects sustainable development.
Summary of the invention
For the problems referred to above, the purpose of this utility model be to provide a kind of compact conformation, efficiency high, pollute little marine nuclear energy thermoelectric co-generation system.
For achieving the above object, the utility model takes following technical scheme: a kind of marine nuclear energy thermoelectric co-generation system, is characterized in that: it comprises nuclear reactor, steam generator, the steam turbine be made up of steam turbine high-pressure cylinder and turbine low pressure cylinder, steam-water separator, condenser, condensate pump, low-pressure heater, oxygen-eliminating device, user's heat exchanger, main feed pump and generator in floating nuclear power plant; Described nuclear reactor connects and composes nuclear steam supply system by pipeline and described steam generator; The outlet of described steam generator is connected with described steam turbine high-pressure cylinder, after described steam turbine high-pressure cylinder one end connects described steam-water separator, turbine low pressure cylinder, condenser, condensate pump, low-pressure heater, oxygen-eliminating device and main feed pump successively, generating major loop is connected and composed with the entrance of described steam generator, wherein said generator is connected with described steam turbine high-pressure cylinder and turbine low pressure cylinder respectively by pipeline, drives described electrical power generators by described steam turbine high-pressure cylinder and turbine low pressure cylinder; The described steam turbine high-pressure cylinder other end connects and composes heat supply major loop with the entrance of described steam generator after being connected with described user's heat exchanger, oxygen-eliminating device and main feed pump successively.
Described floating nuclear power plant adopts thermoelectricity co-generating heat supplying unit.
Described steam turbine adopts adjustable steam extraction type, and high-low pressure divides cylinder structure; Described steam turbine high-pressure cylinder adopts inside and outside double shell structure, and high-pressure section is that forward is arranged; Described turbine low pressure cylinder adopts double split flow double shell structure.
Described oxygen-eliminating device adopts horizontal type structure.
Described user's heat exchanger adopts shell-and-tube heat exchanger.
The utility model is owing to taking above technical scheme, it has the following advantages: 1, the utility model due to arrange nuclear steam supply system output electric energy while also can export heat energy, compared to independent nuclear power generating system, the total efficiency of system is highly improved.2, the utility model is owing to adopting mode heating steam demand of drawing gas, and improves whole efficiency improve efficiency by energy cascade application.3, the utility model carries out generating electricity and heat supply owing to utilizing nuclear energy, and required volume of fuel is little, and convenient transport, decreases the consumption of fossil fuel simultaneously, reduces carbon dioxide and waste discharge.4, the utility model all adopts closed circuit due to heat supply major loop and generating major loop, is allly hydrophobicly all back to oxygen-eliminating device, without the need to outside moisturizing when system is normally run.5, the utility model is due to using nuclear reactor as thermal source, and technology maturation is reliable, and operating experience is enriched, and construction cost is low.6, the utility model is due to steam turbine employing adjustable steam extraction type, and heating load can adjust with user's request, can also isolate turbine low pressure cylinder simultaneously, meet the operating mode of a large amount of heat supply.7, the utility model is owing to being provided with steam-water separator, its wet steam that effectively can reduce steam turbine high-pressure cylinder discharge is to the erosion of turbine low pressure cylinder blade, increase exerting oneself of turbine low pressure cylinder simultaneously, ensure that the safe reliability of Steam Turbine, improve the effective efficiency of Steam Turbine.The utility model whole system composition simplifies, and compact conformation, is more suitable for the environment of limited space, can be widely used in the development field of offshore oil and gas field.
Accompanying drawing explanation
Fig. 1 is the utility model structural representation, and wherein dotted line represents the hydrophobic of system and draws gas, and solid line represents main steam or main feedwater.
Embodiment
Below in conjunction with drawings and Examples, the utility model is described in detail.
As shown in Figure 1, the utility model comprises nuclear reactor 1, steam generator 2, the steam turbine 3 be made up of steam turbine high-pressure cylinder 31 and turbine low pressure cylinder 32, steam-water separator 4, condenser 5, condensate pump 6, low-pressure heater 7, oxygen-eliminating device 8, user's heat exchanger 9, main feed pump 10 and the generator 11 in floating nuclear power plant.Nuclear reactor 1 connects and composes nuclear steam supply system by pipeline and steam generator 2.The outlet of steam generator 2 is connected with steam turbine high-pressure cylinder 31 entrance, steam turbine high-pressure cylinder 31 exit end connects and composes generating major loop with the entrance of steam generator 2 after being connected with steam-water separator 4, turbine low pressure cylinder 32, condenser 5, condensate pump 6, low-pressure heater 7, oxygen-eliminating device 8 and main feed pump 10 successively.Steam turbine high-pressure cylinder 31 exports after the other end is connected with user's heat exchanger 9, oxygen-eliminating device 8 and main feed pump 10 successively, connects and composes heat supply major loop with the entrance of steam generator 2.Generator 11 is connected with steam turbine high-pressure cylinder 31 and turbine low pressure cylinder 32 respectively by pipeline, is generated electricity by steam turbine high-pressure cylinder 31 and turbine low pressure cylinder 32 drive electrical generators 11.
In above-described embodiment, floating nuclear power plant builds the small-sized nuclear energy power generation and heat supply station at sea moveable floating platform.Floating nuclear power plant adopts thermoelectricity co-generating heat supplying unit, and its capacity sets according to actual needs, such as can be set to offshore oilfield group produce load 70% and more than.
In the various embodiments described above, steam turbine 3 adopts adjustable steam extraction type (band rotary separator), and high-low pressure divides cylinder structure.Steam turbine high-pressure cylinder 31 adopts inside and outside double shell structure, and high-pressure section is that forward is arranged; Turbine low pressure cylinder 32 adopts double split flow double shell structure.
In the various embodiments described above, oxygen-eliminating device 8 adopts horizontal type structure.
In the various embodiments described above, user's heat exchanger 9 adopts shell-and-tube heat exchanger.The quantity of user's heat exchanger 9 according to actual total heat duties need determine, such as if desired the thermal efficiency reaches 98%, then arrange 3 user's heat exchangers, every platform heat interchanger heating load is not less than 60% of total heat duties, and what ensure that user's heat exchanger can be redundant.
Below principle of work of the present utility model is described in detail.
The utility model has three kinds of operational modes: 100% power generation mode, a large amount of heat supply mode and a small amount of heat supply mode.
During the 100% power generation mode method of operation: from the main steam of nuclear steam supply system, be sent to steam turbine high-pressure cylinder 31 by pipeline.Main steam, in steam turbine high-pressure cylinder 31, becomes low-pressure steam after flowing through leaf blade expansion at different levels acting and is expelled to steam-water separator 4.Be expelled to turbine low pressure cylinder 32 after steam-water separator 4 pairs of low-pressure steam dehumidify, continue the generating of acting drive electrical generators in turbine low pressure cylinder 32 after, be expelled to condenser 5.In the steam that turbine low pressure cylinder 32 is discharged by condenser 5 and thermodynamic cycle, the steam condensation Cheng Shuihou in other various source is expelled to condensate pump 6.Low-pressure heater 7 is expelled to after condensate pump 6 pairs of condensate water boostings.Low-pressure heater 7 is expelled to oxygen-eliminating device 8 after heating the condensate water after boosting.Oxygen-eliminating device 8 is expelled to main feed pump 10 by after the main feedwater deoxidation in water storage tank, and main feed pump 10 is sent to the entrance of steam generator 2 after boosting further to main feedwater, completes vapour-water seal circulation.In the 100% power generation mode method of operation, main steam is used for generating electricity completely, and the vapor stream now circulated in whole system is called solidifying air-flow.
A small amount of heat supply mode method of operation is as follows: from the main steam of nuclear steam supply system, is sent to steam turbine high-pressure cylinder 31 by pipeline.Main steam, in steam turbine high-pressure cylinder 31, becomes low-pressure steam after flowing through leaf blade expansion at different levels acting.A small amount of low-pressure steam enters user's heat exchanger 9 by drawing gas, and the cool water heating entering user's heat exchanger 9 is become hot water for user's heat supply, hydrophobic, is expelled to oxygen-eliminating device 8.Remain most of low-pressure steam to be then expelled to steam-water separator 4 and to dehumidify, then enter after turbine low pressure cylinder 32 continues the generating of acting drive electrical generators and be expelled to condenser 5.In the steam that turbine low pressure cylinder 32 is discharged by condenser 5 and thermodynamic cycle, the steam condensation in other various source becomes water and is expelled to condensate pump 6.Condensate pump 6 is expelled to low-pressure heater 7 after condensate water being boosted.Low-pressure heater 7 is expelled to oxygen-eliminating device 8 after heating the condensate water after boosting.Oxygen-eliminating device 8 is expelled to main feed pump 10 by after the main feedwater deoxidation of water storage tank, and main feed pump 10 is sent to the entrance of steam generator 2 after boosting further to main feedwater, completes vapour-water seal circulation.In a small amount of heat supply mode method of operation, the main steam part that nuclear steam supply system produces is used for generating, and a part is used for heat supply, and the vapor stream now circulated in whole system is called for hot-fluid.
A large amount of heat supply mode method of operation is as follows: from the main steam of nuclear steam supply system, is sent to steam turbine high-pressure cylinder 31 by pipeline.Main steam, in steam turbine high-pressure cylinder 31, becomes low-pressure steam after flowing through leaf blade expansion at different levels acting.Major part low-pressure steam enters user's heat exchanger 9 by drawing gas, and is user's heat supply after the cool water heating entering user's heat exchanger 9 being become hot water, hydrophobic, is expelled to oxygen-eliminating device 8.Residue fraction low-pressure steam is expelled to after steam-water separator 4 dehumidifies from steam turbine high-pressure cylinder 31 exhaust stage blade, is expelled to oxygen-eliminating device 8.Oxygen-eliminating device 8 is expelled to main feed pump 10 by after the main feedwater deoxidation in water storage tank, and main feed pump 10 is sent to the entrance of steam generator 2 after boosting further to main feedwater, completes vapour-water seal circulation.Equally, in a large amount of heat supply mode method of operation, the main steam that nuclear steam supply system produces also is that a part is used for generating, and a part is used for heat supply, and the vapor stream now circulated in whole system is called for hot-fluid.
The various embodiments described above are only for illustration of the utility model; wherein the structure of each parts, connected mode and manufacture craft etc. all can change to some extent; every equivalents of carrying out on the basis of technical solutions of the utility model and improvement, all should not get rid of outside protection domain of the present utility model.
Claims (7)
1. a marine nuclear energy thermoelectric co-generation system, is characterized in that: it comprises nuclear reactor, steam generator, the steam turbine be made up of steam turbine high-pressure cylinder and turbine low pressure cylinder, steam-water separator, condenser, condensate pump, low-pressure heater, oxygen-eliminating device, user's heat exchanger, main feed pump and generator in floating nuclear power plant;
Described nuclear reactor connects and composes nuclear steam supply system by pipeline and described steam generator; The outlet of described steam generator is connected with described steam turbine high-pressure cylinder, after described steam turbine high-pressure cylinder one end connects described steam-water separator, turbine low pressure cylinder, condenser, condensate pump, low-pressure heater, oxygen-eliminating device and main feed pump successively, generating major loop is connected and composed with the entrance of described steam generator, wherein said generator is connected with described steam turbine high-pressure cylinder and turbine low pressure cylinder respectively by pipeline, drives described electrical power generators by described steam turbine high-pressure cylinder and turbine low pressure cylinder; The described steam turbine high-pressure cylinder other end connects and composes heat supply major loop with the entrance of described steam generator after being connected with described user's heat exchanger, oxygen-eliminating device and main feed pump successively.
2. a kind of marine nuclear energy thermoelectric co-generation system as claimed in claim 1, is characterized in that: described floating nuclear power plant adopts thermoelectricity co-generating heat supplying unit.
3. a kind of marine nuclear energy thermoelectric co-generation system as claimed in claim 1, is characterized in that: described steam turbine adopts adjustable steam extraction type, and high-low pressure divides cylinder structure; Described steam turbine high-pressure cylinder adopts inside and outside double shell structure, and high-pressure section is that forward is arranged; Described turbine low pressure cylinder adopts double split flow double shell structure.
4. a kind of marine nuclear energy thermoelectric co-generation system as claimed in claim 2, is characterized in that: described steam turbine adopts adjustable steam extraction type, and high-low pressure divides cylinder structure; Described steam turbine high-pressure cylinder adopts inside and outside double shell structure, and high-pressure section is that forward is arranged; Described turbine low pressure cylinder adopts double split flow double shell structure.
5. the marine nuclear energy thermoelectric co-generation system of one as claimed in claim 1 or 2 or 3 or 4, is characterized in that: described oxygen-eliminating device adopts horizontal type structure.
6. the marine nuclear energy thermoelectric co-generation system of one as claimed in claim 1 or 2 or 3 or 4, is characterized in that: described user's heat exchanger adopts shell-and-tube heat exchanger.
7. a kind of marine nuclear energy thermoelectric co-generation system as claimed in claim 5, is characterized in that: described user's heat exchanger adopts shell-and-tube heat exchanger.
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| CN201520682747.XU CN205028667U (en) | 2015-09-06 | 2015-09-06 | Thermoelectric cogeneration system of marine nuclear energy |
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| CN201520682747.XU CN205028667U (en) | 2015-09-06 | 2015-09-06 | Thermoelectric cogeneration system of marine nuclear energy |
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Cited By (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106898400A (en) * | 2017-03-27 | 2017-06-27 | 中核核电运行管理有限公司 | The remote region thermal energy supply system of large commercial nuclear energy mesohigh steam and method |
| CN107355260A (en) * | 2016-05-09 | 2017-11-17 | 中核辽宁核电有限公司 | A kind of co-generation unit based on large commercial nuclear power generating sets |
| CN107355261A (en) * | 2016-05-09 | 2017-11-17 | 中核辽宁核电有限公司 | A kind of cogeneration method based on large commercial nuclear power generating sets |
| CN109524141A (en) * | 2018-10-16 | 2019-03-26 | 中广核研究院有限公司 | Seawater desalination system and its small-sized powered by nuclear energy output device and power output method |
| CN110160112A (en) * | 2019-04-24 | 2019-08-23 | 中国船舶重工集团公司第七一九研究所 | The marine floating heap nuclear energy heating system of carrying vapour storage heater |
| CN110206602A (en) * | 2019-05-23 | 2019-09-06 | 中国能源建设集团广东省电力设计研究院有限公司 | A kind of heat and power system and its control method based on nuclear power station |
| CN111262273A (en) * | 2020-03-02 | 2020-06-09 | 西安交通大学 | Wind energy reactor system and working method thereof |
| CN111997699A (en) * | 2020-08-13 | 2020-11-27 | 山东电力工程咨询院有限公司 | Heating nuclear reactor and conventional energy coupling power generation and heating system and method |
| CN114777104A (en) * | 2022-04-13 | 2022-07-22 | 清华大学 | Superheated steam system and pressurized water reactor |
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2015
- 2015-09-06 CN CN201520682747.XU patent/CN205028667U/en active Active
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN107355260B (en) * | 2016-05-09 | 2024-03-19 | 中核辽宁核电有限公司 | Cogeneration system based on large commercial nuclear power unit |
| CN107355260A (en) * | 2016-05-09 | 2017-11-17 | 中核辽宁核电有限公司 | A kind of co-generation unit based on large commercial nuclear power generating sets |
| CN107355261A (en) * | 2016-05-09 | 2017-11-17 | 中核辽宁核电有限公司 | A kind of cogeneration method based on large commercial nuclear power generating sets |
| CN106898400A (en) * | 2017-03-27 | 2017-06-27 | 中核核电运行管理有限公司 | The remote region thermal energy supply system of large commercial nuclear energy mesohigh steam and method |
| CN109524141A (en) * | 2018-10-16 | 2019-03-26 | 中广核研究院有限公司 | Seawater desalination system and its small-sized powered by nuclear energy output device and power output method |
| CN109524141B (en) * | 2018-10-16 | 2020-09-08 | 中广核研究院有限公司 | Seawater desalination system, small nuclear power output device and power output method thereof |
| CN110160112A (en) * | 2019-04-24 | 2019-08-23 | 中国船舶重工集团公司第七一九研究所 | The marine floating heap nuclear energy heating system of carrying vapour storage heater |
| CN110206602A (en) * | 2019-05-23 | 2019-09-06 | 中国能源建设集团广东省电力设计研究院有限公司 | A kind of heat and power system and its control method based on nuclear power station |
| CN111262273A (en) * | 2020-03-02 | 2020-06-09 | 西安交通大学 | Wind energy reactor system and working method thereof |
| CN111997699B (en) * | 2020-08-13 | 2022-10-28 | 山东电力工程咨询院有限公司 | Heating nuclear reactor and conventional energy coupling power generation and heating system and method |
| CN111997699A (en) * | 2020-08-13 | 2020-11-27 | 山东电力工程咨询院有限公司 | Heating nuclear reactor and conventional energy coupling power generation and heating system and method |
| CN114777104A (en) * | 2022-04-13 | 2022-07-22 | 清华大学 | Superheated steam system and pressurized water reactor |
| CN114777104B (en) * | 2022-04-13 | 2024-03-29 | 清华大学 | Superheated steam system and pressurized water reactor |
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Address after: 100010 Beijing, Chaoyangmen, North Street, No. 25, No. Co-patentee after: CNOOC research institute limited liability company Patentee after: China Offshore Oil Group Co., Ltd. Co-patentee after: Zhongkehua Nuclear Power Technology Institute Co., Ltd. Co-patentee after: China General Nuclear Power Corporation Address before: 100010 Beijing, Chaoyangmen, North Street, No. 25, No. Co-patentee before: CNOOC Research Institute Patentee before: China National Offshore Oil Corporation Co-patentee before: Zhongkehua Nuclear Power Technology Institute Co., Ltd. Co-patentee before: China General Nuclear Power Corporation |