CN203826018U - Multipurpose floating nuclear energy device - Google Patents
Multipurpose floating nuclear energy device Download PDFInfo
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- CN203826018U CN203826018U CN201420265652.3U CN201420265652U CN203826018U CN 203826018 U CN203826018 U CN 203826018U CN 201420265652 U CN201420265652 U CN 201420265652U CN 203826018 U CN203826018 U CN 203826018U
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- reactor
- heating
- steam turbine
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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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Abstract
The utility model discloses a multipurpose floating nuclear energy device. The device comprises a reactor installed in a containment vessel. A hot pipe of the reactor is conveyed to a steam turbine. The steam turbine drives an electric generator to generate power. The hot pipe of the reactor is directly connected to a sea water desalination system, a civil heating system and a heavy oil exploitation system. A high-temperature hot gas discharged by the steam turbine is conveyed to the sea water desalination system, the civil heating system and the heavy oil exploitation system via a secondary pipeline. The reactor carried by a barge is served as a power source and generated power is guided and is used for seawater desalination, heating, heavy oil exploitation and the like besides power generation of the steam turbine. Kinetic energy of the nuclear reactor is processed in a diversified mode. A current floating nuclear power station can only used for power generation. By using the device of the utility model, the above problem is solved. Kinds of energy are enriched. The device is good for combined energy providing of special projects, such as offshore operation and the like. The energy which drives the steam turbine is used again so that an utilization rate of the nuclear reactor is greatly increased.
Description
Technical field
The utility model relates to floating type reactor, specifically a kind of multiduty unsteady nuclear-energy plant.
Background technology
Floating nuclear power plant can be used on does not have electrical network, hard to get to, near extra large place, be included in the oil development of the South Pole and Arctic.It also can not need the backcountry of building large-scale power grid system that electric power is provided, and is used in the desalinization field of energy intensive.The Middle East belongs to structural water-deficient area, and water is the most vital thing in locality, and floating nuclear power plant is exactly the answer addressing this problem.China shore line is very long, and territorial waters area is huge, and the South Sea and Along Zhejiang Coast have many island, and ocean resources are abundant, is exactly the energy and first the exploitation of ocean resources needs.Fossil fuel, due to the restriction of the conditions such as transport, is unfavorable for providing the enough diversified energy for marine resources development.The U-235 of the one kilogram energy that all fission is emitted is suitable with 2700 tons of standard coal equivalents, and for nuclear reactor, the acquisition of same energy needs to pay any transport cost hardly.Nuclear reactor, in energy supply, especially in transport inconvenience, or has the incomparable unique advantage of fossil fuel in the energy supply of remote districts.
1963, the U.S. was transformed into floating type nuclear power unit (10MW) by a World War II with ship, and 1967, retrofit work completed, and this ship is deployed near the Panama Canal, was military base power supply, and retired in 1976.Only have in the world at present a country of Russia building floating type nuclear power station KLT-40S, be designed for the energy resource supplies from far-off regions such as east, Siberia, expectation will realize in 2016 generating.The floating type nuclear power station that Russia builds is mainly used in providing electric power and heat energy to solve the needed energy of the Far East Area's natural resources exploitation.No matter be the U.S. or Muscovite floating type nuclear power station, it builds object is mainly for remote areas provides electric power, does not give full play to the peculiar advantage of floating type nuclear power station.Current floating nuclear power plant is all only for generating, and its utilization factor is low, and energy dissipation is larger.
Utility model content
The purpose of this utility model is to provide and is applied to a kind of multiduty unsteady nuclear-energy plant, solves the problem that the energy is single, utilization factor is low that the floating type nuclear power station of current Russian KLT-40S exists, and reaches the object that improves its utilization factor, increases energy form.
The purpose of this utility model is achieved through the following technical solutions:
A kind of multiduty unsteady nuclear-energy plant, comprise the reactor being arranged in containment, the hot channel of reactor is transported to steam turbine, steam turbine drives generator generating, the hot channel of reactor is also directly connected to seawater desalination system, civilian heating system and thickened oil recovery system, and the high temperature hot gas that steam turbine is discharged is transported to seawater desalination system, civilian heating system and thickened oil recovery system through secondary pipeline.The utility model is using the reactor of barge carrying as power source, the power of its generation is carried out to water conservancy diversion, except for steam turbine power generation, also for desalinization, heating, thickened oil recovery etc., the kinetic energy of nuclear reactor has been carried out to diversified processing, solved the problem that current floating type nuclear power station can only be used for generating electricity, enriched the kind of the energy, the compound type energy that is conducive to the special items such as offshore operation provides; Adopt through the energy of driving steam turbine and carry out secondary utilization, greatly improved the utilization factor of nuclear reactor.
Described seawater desalination system comprises the secondary heat exchanger T1 being connected on hot channel and secondary pipeline, secondary heat exchanger T1 connects evaporation of seawater tank R1, evaporation of seawater tank R2, evaporation of seawater tank R3 and fresh water condenser successively, the heating tube of evaporation of seawater tank R1 bottom is connected to the upper circulating-heating that forms of secondary heat exchanger T1, and the high concentration seawater of evaporation of seawater tank R2, evaporation of seawater tank R3 bottom is directly discharged.Concretely, the thermal source of inputting from hot channel and secondary pipeline carries out heat interchange in secondary heat exchanger T1, the steady heat that heat interchange is formed is input in evaporation of seawater tank R1 seawater is heated, the heat energy that seawater herein obtains is higher, can form water vapor and enter into evaporation of seawater tank R2, through again entering evaporation of seawater tank R3 after evaporation, after evaporation for the third time, form pure water vapor and be input to fresh water condenser, condensation forms fresh water.
Described civilian heating system comprises the secondary heat exchanger T2 being connected on hot channel and secondary pipeline, secondary heat exchanger T2 carries heating installation to civilian defeated heating coil net, and the chilled water forming after the heat exchange of civilian defeated heating coil net is transported to secondary heat exchanger T2 by recovery pump M3 and carries out heat interchange.The gas that belongs to High Temperature High Pressure of discharging from steam turbine, it contains huge energy, set it as power, or it is mixed with the outputting power source of a part of reactor as the common energy, after adjusting pressure valve, just can carry out heat interchange with secondary heat exchanger T2, the coolant-temperature gage that obtains heat is higher, can be for the heating of civilian defeated heating coil net, and the water at low temperature after heating flows to secondary heat exchanger T2 through recovery pump M3 and forms circulation heating.
Described thickened oil recovery system comprises the multi-stage booster heating device being connected on hot channel and secondary pipeline, the high-temperature high pressure water of multi-stage booster heating device output flows to thickened oil recovery well, and the water at low temperature after thickened oil recovery well is used is input to multi-stage booster heating device through recovery pump M4 and carries out secondary utilization.By the secondary utilization of steam turbine waste gas, can reduce the high-temperature-hot-water energy consumption of thickened oil recovery, directly improve the energy utilization rate of reactor.
Also comprise cooling system, cooling system comprises the heat interchanger, the condenser that are connected with reactor by pipeline, the cold water of condenser is delivered to clarifier through condensate pump M2, the pure cold water of clarifier is delivered to heat interchanger by feedwater M1, and through heat interchanger, heat absorption is delivered to condenser formation circulating cooling to cold water after heating up.By cooling system is set, can control the temperature of reactor, it is operated in comparatively stable temperature range.
Described condenser is also connected with the secondary pipeline of steam turbine output high-temperature gas.For the temperature control of secondary pipeline, can adopt condenser as unified control center, by the valve controlling flow amount of each pipeline, just can adjust the input and output amount of each pipeline.
The utility model compared with prior art, has following advantage and beneficial effect:
A kind of multiduty unsteady nuclear-energy plant of 1 the utility model, using the reactor of barge carrying as power source, the power of its generation is carried out to water conservancy diversion, except for steam turbine power generation, also, for desalinization, heating, thickened oil recovery etc., the kinetic energy of nuclear reactor is carried out to diversified processing, solved the problem that current floating type nuclear power station can only be used for generating electricity, the kind of having enriched the energy, the compound type energy that is conducive to the special items such as offshore operation provides; Adopt through the energy of driving steam turbine and carry out secondary utilization, greatly improved the utilization factor of nuclear reactor;
A kind of multiduty unsteady nuclear-energy plant of 2 the utility model, the gas that belongs to High Temperature High Pressure of discharging from steam turbine, it contains huge energy, set it as power, or it is mixed with the outputting power source of a part of reactor as the common energy, after adjusting pressure valve, just can carry out heat interchange with secondary heat exchanger T2, the coolant-temperature gage that obtains heat is higher, can be for the heating of civilian defeated heating coil net, the water at low temperature after heating flows to secondary heat exchanger T2 through recovery pump M3 and forms circulation heating;
A kind of multiduty unsteady nuclear-energy plant of 3 the utility model, can be applicable to marine energy exploitation, isolated island energy supply, can be used for providing power, generate electricity, desalinize seawater, heating, supply steam etc., can meet the special requirement of the region heat such as off-lying sea, polar region or remote districts, isolated island, electricity, water, vapour coproduction.
Brief description of the drawings
Fig. 1 is the utility model principle schematic.
Mark and corresponding parts title in accompanying drawing:
1-reactor, 2-containment, 3-steam turbine, 4-generator, 5-fresh water condenser, 6-civilian defeated heating coil net, 7-multi-stage booster heating device, 8-thickened oil recovery well, 9-heat interchanger, 10-condenser, 11-clarifier.
Embodiment
Below in conjunction with embodiment, the utility model is described in further detail, but embodiment of the present utility model is not limited to this.
Embodiment
Schematic diagram as shown in Figure 1, a kind of multiduty unsteady nuclear-energy plant of the utility model, comprise the reactor 1 being arranged in containment 2, the hot channel of reactor 1 is transported to steam turbine 3, steam turbine 3 drives generator 4 to generate electricity, the hot channel of reactor 1 is also directly connected to seawater desalination system, civilian heating system and thickened oil recovery system, and the high temperature hot gas that steam turbine 3 is discharged is transported to seawater desalination system, civilian heating system and thickened oil recovery system through secondary pipeline, wherein, seawater desalination system comprises the secondary heat exchanger T1 being connected on hot channel and secondary pipeline, secondary heat exchanger T1 connects evaporation of seawater tank R1 successively, evaporation of seawater tank R2, evaporation of seawater tank R3, and fresh water condenser 5, the heating tube of evaporation of seawater tank R1 bottom is connected to the upper circulating-heating that forms of secondary heat exchanger T1, evaporation of seawater tank R2, the high concentration seawater of evaporation of seawater tank R3 bottom is directly discharged, in secondary heat exchanger T1, carry out heat interchange, the steady heat that heat interchange is formed is input in evaporation of seawater tank R1 seawater is heated, the heat energy that seawater herein obtains is higher, can form water vapor and enter into evaporation of seawater tank R2, through again entering evaporation of seawater tank R3 after evaporation, after evaporation for the third time, form pure water vapor and be input to fresh water condenser 5, condensation forms fresh water, civilian heating system comprises the secondary heat exchanger T2 being connected on hot channel and secondary pipeline, secondary heat exchanger T2 carries heating installation to civilian defeated heating coil net 6, and the chilled water forming after civilian defeated heating coil net 6 heat exchange is transported to secondary heat exchanger T2 by recovery pump M3 and carries out heat interchange, thickened oil recovery system comprises the multi-stage booster heating device 7 being connected on hot channel and secondary pipeline, the high-temperature high pressure water that multi-stage booster heating device 7 is exported flows to thickened oil recovery well 8, and the water at low temperature after thickened oil recovery well 8 use is input to multi-stage booster heating device 7 through recovery pump M4 and carries out secondary utilization, also comprise cooling system, cooling system comprises the heat interchanger 9, the condenser 10 that are connected with reactor 1 by pipeline, the cold water of condenser 10 is delivered to clarifier 11 through condensate pump M2, the pure cold water of clarifier 11 is delivered to heat interchanger by feedwater M1, through heat interchanger 9, heat absorption is delivered to condenser 10 after heating up and forms circulating cooling cold water, and the secondary pipeline that condenser 10 is also exported high-temperature gas with steam turbine 3 is connected, at the upstream end of each thermal technology's original paper, be all installed on flow control valve K, as the K1～K10 in figure, for regulating the input and output amount of each thermal technology's device, it is operated in rational scope.
The above; it is only preferred embodiment of the present utility model; not the utility model is done to any pro forma restriction, any simple modification, the equivalent variations in every foundation technical spirit of the present utility model, above embodiment done, within all falling into protection domain of the present utility model.
Claims (6)
1. a multiduty unsteady nuclear-energy plant, comprise the reactor (1) being arranged in containment (2), the hot channel of reactor (1) is transported to steam turbine (3), steam turbine (3) drives generator (4) generating, it is characterized in that: the hot channel of reactor (1) is also directly connected to seawater desalination system, civilian heating system and thickened oil recovery system, and the high temperature hot gas that steam turbine (3) is discharged is transported to seawater desalination system, civilian heating system and thickened oil recovery system through secondary pipeline.
2. the multiduty unsteady nuclear-energy plant of one according to claim 1, it is characterized in that: described seawater desalination system comprises the secondary heat exchanger T1 being connected on hot channel and secondary pipeline, secondary heat exchanger T1 connects evaporation of seawater tank R1, evaporation of seawater tank R2, evaporation of seawater tank R3 and fresh water condenser (5) successively, the heating tube of evaporation of seawater tank R1 bottom is connected to the upper circulating-heating that forms of secondary heat exchanger T1, and the high concentration seawater of evaporation of seawater tank R2, evaporation of seawater tank R3 bottom is directly discharged.
3. the multiduty unsteady nuclear-energy plant of one according to claim 1, it is characterized in that: described civilian heating system comprises the secondary heat exchanger T2 being connected on hot channel and secondary pipeline, secondary heat exchanger T2 carries heating installation to civilian defeated heating coil net (6), and the chilled water forming after civilian defeated heating coil net (6) heat exchange is transported to secondary heat exchanger T2 by recovery pump M3 and carries out heat interchange.
4. the multiduty unsteady nuclear-energy plant of one according to claim 1, it is characterized in that: described thickened oil recovery system comprises the multi-stage booster heating device (7) being connected on hot channel and secondary pipeline, the high-temperature high pressure water of multi-stage booster heating device (7) output flows to thickened oil recovery well (8), and the water at low temperature after thickened oil recovery well (8) is used is input to multi-stage booster heating device (7) through recovery pump M4 and carries out secondary utilization.
5. according to the multiduty unsteady nuclear-energy plant of the one described in any one in claim 1 to 4, it is characterized in that: also comprise cooling system, cooling system comprises the heat interchanger (9), the condenser (10) that are connected with reactor (1) by pipeline, the cold water of condenser (10) is delivered to clarifier (11) through condensate pump M2, the pure cold water of clarifier (11) is delivered to heat interchanger by feedwater M1, and through heat interchanger (9), heat absorption is delivered to condenser (10) formation circulating cooling to cold water after heating up.
6. the multiduty unsteady nuclear-energy plant of one according to claim 5, is characterized in that: described condenser (10) is also connected with the secondary pipeline of steam turbine (3) output high-temperature gas.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201420265652.3U CN203826018U (en) | 2014-05-23 | 2014-05-23 | Multipurpose floating nuclear energy device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201420265652.3U CN203826018U (en) | 2014-05-23 | 2014-05-23 | Multipurpose floating nuclear energy device |
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| Publication Number | Publication Date |
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| CN203826018U true CN203826018U (en) | 2014-09-10 |
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| Application Number | Title | Priority Date | Filing Date |
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| CN201420265652.3U Withdrawn - After Issue CN203826018U (en) | 2014-05-23 | 2014-05-23 | Multipurpose floating nuclear energy device |
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Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104021829A (en) * | 2014-05-23 | 2014-09-03 | 中国核动力研究设计院 | Multifunctional floating nuclear energy device |
| CN105509122A (en) * | 2016-01-20 | 2016-04-20 | 新核（北京）能源科技有限公司 | Urban pipeline network system for low-temperature nuclear heating reactors |
| CN109572974A (en) * | 2018-10-16 | 2019-04-05 | 中广核研究院有限公司 | A kind of small floating nuclear power system and its propulsion and electricity-generating method |
| CN105509121B (en) * | 2016-01-20 | 2019-04-26 | 启迪新核（北京）能源科技有限公司 | Low-temperature nuclear heat supplying pile secondary circuit thermal energy partition equilibrium heat-exchange system |
| CN112562879A (en) * | 2020-12-03 | 2021-03-26 | 东北大学 | Energy cascade utilization multi-element energy supply system based on nuclear energy |
-
2014
- 2014-05-23 CN CN201420265652.3U patent/CN203826018U/en not_active Withdrawn - After Issue
Cited By (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104021829A (en) * | 2014-05-23 | 2014-09-03 | 中国核动力研究设计院 | Multifunctional floating nuclear energy device |
| CN104021829B (en) * | 2014-05-23 | 2016-05-11 | 中国核动力研究设计院 | A kind of multiduty unsteady nuclear-energy plant |
| CN105509122A (en) * | 2016-01-20 | 2016-04-20 | 新核（北京）能源科技有限公司 | Urban pipeline network system for low-temperature nuclear heating reactors |
| CN105509121B (en) * | 2016-01-20 | 2019-04-26 | 启迪新核（北京）能源科技有限公司 | Low-temperature nuclear heat supplying pile secondary circuit thermal energy partition equilibrium heat-exchange system |
| CN105509122B (en) * | 2016-01-20 | 2019-08-06 | 启迪新核（北京）能源科技有限公司 | Low-temperature nuclear heat supplying pile urban pipe network system |
| CN109572974A (en) * | 2018-10-16 | 2019-04-05 | 中广核研究院有限公司 | A kind of small floating nuclear power system and its propulsion and electricity-generating method |
| CN109572974B (en) * | 2018-10-16 | 2021-02-05 | 中广核研究院有限公司 | Small floating nuclear energy system and propelling and power generating method thereof |
| CN112562879A (en) * | 2020-12-03 | 2021-03-26 | 东北大学 | Energy cascade utilization multi-element energy supply system based on nuclear energy |
| CN112562879B (en) * | 2020-12-03 | 2024-05-14 | 东北大学 | Energy cascade utilization multi-element energy supply system based on nuclear energy |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| AV01 | Patent right actively abandoned |
Granted publication date: 20140910 Effective date of abandoning: 20160511 |
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| C25 | Abandonment of patent right or utility model to avoid double patenting |