CN105645499A - Tri-cogeneration system and tri-cogeneration method for generating power, producing hydrogen and producing fresh water by aid of high-temperature gas-cooled reactor of nuclear power plant - Google Patents
Tri-cogeneration system and tri-cogeneration method for generating power, producing hydrogen and producing fresh water by aid of high-temperature gas-cooled reactor of nuclear power plant Download PDFInfo
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- C—CHEMISTRY; METALLURGY
- C02—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F1/00—Treatment of water, waste water, or sewage
- C02F1/02—Treatment of water, waste water, or sewage by heating
- C02F1/04—Treatment of water, waste water, or sewage by heating by distillation or evaporation
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- C01B3/00—Hydrogen; Gaseous mixtures containing hydrogen; Separation of hydrogen from mixtures containing it; Purification of hydrogen
- C01B3/02—Production of hydrogen or of gaseous mixtures containing a substantial proportion of hydrogen
- C01B3/04—Production of hydrogen or of gaseous mixtures containing a substantial proportion of hydrogen by decomposition of inorganic compounds, e.g. ammonia
- C01B3/042—Decomposition of water
- C01B3/045—Decomposition of water in gaseous phase
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01D—NON-POSITIVE DISPLACEMENT MACHINES OR ENGINES, e.g. STEAM TURBINES
- F01D15/00—Adaptations of machines or engines for special use; Combinations of engines with devices driven thereby
- F01D15/10—Adaptations for driving, or combinations with, electric generators
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01K—STEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
- F01K25/00—Plants or engines characterised by use of special working fluids, not otherwise provided for; Plants operating in closed cycles and not otherwise provided for
- F01K25/08—Plants or engines characterised by use of special working fluids, not otherwise provided for; Plants operating in closed cycles and not otherwise provided for using special vapours
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- G—PHYSICS
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- C02—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
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- C02F2103/00—Nature of the water, waste water, sewage or sludge to be treated
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- Y02A20/124—Water desalination
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- 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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- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E60/00—Enabling technologies; Technologies with a potential or indirect contribution to GHG emissions mitigation
- Y02E60/30—Hydrogen technology
- Y02E60/36—Hydrogen production from non-carbon containing sources, e.g. by water electrolysis
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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
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- Y02P—CLIMATE CHANGE MITIGATION TECHNOLOGIES IN THE PRODUCTION OR PROCESSING OF GOODS
- Y02P20/00—Technologies relating to chemical industry
- Y02P20/10—Process efficiency
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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
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- Y02P—CLIMATE CHANGE MITIGATION TECHNOLOGIES IN THE PRODUCTION OR PROCESSING OF GOODS
- Y02P20/00—Technologies relating to chemical industry
- Y02P20/10—Process efficiency
- Y02P20/129—Energy recovery, e.g. by cogeneration, H2recovery or pressure recovery turbines
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Abstract
The invention discloses a tri-cogeneration system and a tri-cogeneration method for generating power, producing hydrogen and producing fresh water by the aid of a high-temperature gas-cooled reactor of a nuclear power plant. The tri-cogeneration system comprises a closed helium circulating system of the nuclear power plant, a superheater, a steam generator, a raw seawater pipeline, a flash evaporator, a steam ejector, a seawater desalting device, a water feeding pump, a solid oxide electrolytic tank and an auxiliary steam pipeline. The tri-cogeneration system and the tri-cogeneration method have the advantages that the circulating system of the nuclear power plant, steam electrolysis and hydrogen production processes and distillation seawater desalination processes are coupled with one another, the power is generated by the aid of a helium gas turbine at first, waste heat of partial exhaust gas of the helium gas turbine is used for electrolyzing steam and producing the hydrogen, low-temperature waste heat cooling water of a cooler is used for carrying out distillation seawater desalination by means of coupled flash evaporation and steam injection, and accordingly diversified water, power and hydrogen tri-cogeneration modes can be implemented; the electric power and the fresh water which are required for steam electrolysis and hydrogen production can be provided by means of seawater desalination and nuclear power generation, accordingly, the tri-cogeneration system is high in circulating heat efficiency and good in adjustment performance and has a good economic benefit, the reliability of equipment can be improved, environmental pollution can be reduced, the tri-cogeneration system and the tri-cogeneration method have excellent application prospects, and the like.
Description
Technical field
The invention belongs to nuclear energy applied technical field, particularly relate to a kind of nuclear power station HTGR power generating and hydrogen producing preparing fresh water three co-generation system and method thereof.
Background technology
Along with socioeconomic development, China will be likely to face the series of problems such as energy shortage, environmental pollution, fresh water is in short supply future simultaneously. Nuclear power is as a kind of clean energy resource, and all significant for meeting electricity needs, Optimization of Energy Structure, minimizing environmental pollution, China will greatly develop nuclear power from now on. HTGR in nuclear power heap-type is forth generation advanced person's nuclear power technology, has safety good, the feature that heat-economy is good, and current China better grasps this technology and progressively domesticizes. HTGR is except for efficiency power generation, its high temperature helium is also applied for process for making hydrogen. Hydrogen Energy is to have fuel and the energy carrier of development potentiality 21 century most, the advantage with calorific capacity height, cleanliness without any pollution, having application widely in national product every field, therefore HTGR has good development prospect and unique advantage for hydrogen manufacturing. Current process for making hydrogen is mainly Fossil fuel hydrogen manufacturing and water electrolysis hydrogen producing, Fossil fuel hydrogen manufacturing consumes a large amount of fossil energies, produces great amount of carbon dioxide, it is not suitable with the demand of Future Social Development, and water electrolysis hydrogen producing is the hydrogen manufacturing mode cleaned completely, having the advantages that product purity is high, easy and simple to handle, therefore water electrolysis and high-efficiency cleaning primary energy coupled hydrogen making are desirable extensive hydrogen producing technologies. Current water electrolysis hydrogen producing has three class electrolysis baths, respectively alkaline electrolytic bath, Polymer Electrolyte Membrane Electrolyzer, means of solid oxide electrolytic cell, wherein work at high temperature corresponding to the means of solid oxide electrolytic cell of high temperature steam electrolytic hydrogen manufacturing technology, part electric energy is replaced by heat energy, therefore it is most effective in three kinds of electrolysis baths, and cost is not high yet. HTGR can provide the electric energy needed for means of solid oxide electrolytic cell high temperature steam electrolytic hydrogen manufacturing and heat energy simultaneously, and carrying out high temperature steam electrolytic hydrogen manufacturing hence with HTGR is the optimal path leading to hydrogen economy.Extensive hydrogen manufacturing needs to consume substantial amounts of water resource as cost, whole world freshwater resources seawater resources in short supply are then inexhaustible, if directly using seawater electrolysis hydrogen manufacturing, electrolysis bath easily produces poisonous chlorine and becomes infeasible, and the low grade residual heat of nuclear power station is suitable as the thermal source of distillation sea water desalting technology, use water requirement hence with what nuclear desalination can meet demand of domestic water and water electrolysis hydrogen producing. Comprehensive above analysis is it can be seen that utilize nuclear power station HTGR to carry out power generating and hydrogen producing preparing fresh water three coproduction have good feasibility and superiority.
HTGR, from generating angle, differ be difficult to more greatly mate owing to core exit temperature and current steam circulates the highest initial temperature, be therefore not appropriate for individually adopting steam to circulate, and adopts helium-Steam Combined Cycle not yet maturation technically further. The thermodynamic cycle that current main flow generation mode adopts is the enclosed circulated helium having backheat, and circulated helium is divided into again direct circulated helium and indirect circulated helium, and the thermal efficiency of direct circulated helium is higher has good development prospect. Along with the technical development of HTGR, core exit temperature is more and more higher, and the efficiency of enclosed circulated helium will be further enhanced. High temperature steam electrolytic hydrogen manufacturing is carried out about how utilizing HTGR, scholar is had to propose following scheme: core exit high temperature helium is first used for adding vapours and improves its temperature, it is used further to heating feedwater and produces high steam, major part high steam is for steam circulating generation, and fraction high steam continues to be heated for electrolytic hydrogen production. Known by analysis, even if the program all generated energy are all used for electrolytic hydrogen production, the quantity of steam that electrolytic hydrogen production consumes also only accounts for the only small share of total quantity of steam, sensible heat needed for this some vapor heat temperature raising numerical value compared with the latent heat of vaporization of total quantity of steam is very little, therefore most heat energy of high temperature helium still devalue utilization, being similar to HTGR individually adopts steam to circulate, meanwhile the exit water temperature of vapor-cycle condensor relatively low (about 40 DEG C) is difficult by, cause substantial amounts of cold source energy, therefore such scheme is actually and inadvisable. HTGR adopts enclosed circulated helium, core exit high temperature helium is first for helium turbine generating, itself there is higher generating efficiency, the high-temperature exhaust air of helium turbine is used further to produce the high-temperature steam needed for solid oxide electrolyte hydrogen manufacturing, it is also beneficial to the residual heat system with electrolysis bath combine, meanwhile the exit water temperature of enclosed circulated helium cooler higher (general more than 100 DEG C) also is suitable as the thermal source of desalinization, therefore adopts the HTGR of the direct circulated helium having backheat to be easier to realize power generating and hydrogen producing preparing fresh water three co-generation system.
Summary of the invention
It is an object of the invention to provide nuclear power station HTGR power generating and hydrogen producing preparing fresh water three co-generation system that a kind of thermal efficiency of cycle is high, it is good to regulate performance, improve equipment dependability.
Further object is that providing a kind of utilizes nuclear energy to realize water power hydrogen three coproduction, the method reducing environmental pollution, nuclear power station HTGR power generating and hydrogen producing preparing fresh water three coproduction that comprehensive benefit is good.
It is an object of the invention to be realized by following technical scheme:
The present invention is a kind of nuclear power station HTGR power generating and hydrogen producing preparing fresh water three co-generation system, and it includes nuclear power station enclosed circulated helium system, superheater, steam generator, former seawater pipeline, flash vessel, steam jet ejector, sea water desalinating unit, feed pump, means of solid oxide electrolytic cell, auxiliary steam pipeline.Described nuclear power station enclosed circulated helium system includes compressor, regenerator, HTGR, gas turbine generator group, regulates valve, cooler and relevant pipeline and form a single loop circulation; The air exit of described gas turbine generator group is divided into two-way: a road is connected and arranges on this pipeline adjustment valve with the helium import of regenerator high temperature side, and another road is connected with the helium import of superheater; The helium outlet of described superheater is connected with the helium import of steam generator, the steam (vapor) outlet of superheater is divided into two-way: a road is connected with auxiliary steam pipeline, and another road is connected with the steam inlet of means of solid oxide electrolytic cell and arranges control valve on this pipeline; The helium outlet of described steam generator is connected with the helium import of cooler, and the saturated vapor outlet of steam generator is connected with the steam inlet of superheater; It is connected with the sea intake of flash vessel after described former seawater pipeline spiral or tortuous traverse cooler, the flash-off steam outlet of described flash vessel is connected with the low pressure steam inlet of steam jet ejector, and the concentrated seawater outlet of flash vessel is connected with the sea intake of sea water desalinating unit; The high pressure steam inlet of described steam jet ejector is connected with auxiliary steam pipeline, and the steam (vapor) outlet of steam jet ejector is connected with the thermal source import of sea water desalinating unit; The desalination water outlet of described sea water desalinating unit is divided into two-way: a road exports as product water, and another road is connected with the feed-water inlet of steam generator and assigns water pump on this pipeline, and sea water desalinating unit is provided with sewage draining exit; Described auxiliary steam pipeline two ends are connected with the steam (vapor) outlet of superheater and the high pressure steam inlet of steam jet ejector respectively.
The delivery temperature of described gas turbine generator group is between 550��650 DEG C; The injection temperature of described flash vessel is between 100��150 DEG C, and the flash-off steam outlet temperature of flash vessel is between 40��50 DEG C; The saturated vapor outlet temperature of described steam generator is between 200��374 DEG C; The steam exit temperature of described superheater is at 520��620 DEG C.
The present invention is a kind of method of nuclear power station HTGR power generating and hydrogen producing preparing fresh water three coproduction, and it includes procedure below:
1) form hot sea water after the cooled device heat absorption of the sea water in former seawater pipeline and enter flash vessel generation flash process. The flash-off steam of flash vessel enters steam jet ejector to be carried out injection by the high steam from auxiliary steam pipeline and is mixed into the steam of higher temperature and goes to sea water desalinating unit as driving heat source, and the concentrated seawater of flash vessel delivers to sea water desalinating unit as charging sea water. The desalination water of sea water desalinating unit output is divided into two-way: a road exports as product water, and another is routed to water pump and is delivered to steam generator as feedwater. Feedwater heat absorption evaporation in steam generator forms high steam, high steam forms superheated steam through the further heat temperature raising of superheater, a part of superheated steam goes to means of solid oxide electrolytic cell to carry out electrolytic hydrogen production, and another part superheated steam goes to steam jet ejector as injection vapour by auxiliary steam pipeline;
2) the high temperature helium of HTGR core exit enters helium turbine generator group work done generating, and part generated energy provides the electric power of electrolytic hydrogen production. The high-temperature exhaust air of helium turbine group is divided into two-way, one tunnel goes to regenerator high temperature side to carry out waste heat recovery, another road successively delivers to superheater and steam generator is sequentially carried out heat release, two-way helium after heat release again merges together and enters cooler and cools down, and the helium after cooling successively reenters HTGR after compressor compression and the heating of regenerator low temperature side and carries out next round circulation.
After adopting such scheme, the method have the advantages that
1) water power hydrogen three coproduction is realized. The high temperature helium of enclosed circulated helium is used for generating electricity, and middle high-temperature exhaust air waste heat is used for steam electrolytic hydrogen manufacturing, and low temperature exhaust heat cooling water is for desalinization, it is achieved that the function of Joint Production while of fresh water, hydrogen, three kinds of products of electric power.
2) thermal efficiency of cycle is high. The high-temperature exhaust air of helium turbine is used for the thermal efficiency of steam electrolytic hydrogen manufacturing up to 80 ~ 90%, is used for the thermal efficiency of steam circulating generation far above high-temperature exhaust air, and saves steam turbine and auxiliary equipment; Fully recycling and reusing it addition, the enclosed circulated helium cooling waste heat taken out of of water substantially carries out waste heat for the desalinization mode of the present invention, therefore the thermal efficiency of cycle of whole system is very high.
3) performance is regulated good. The present invention can be controlled the desalination water yield of sea water desalinating unit output and the hydrogen output of electrolysis bath and power consumption by control valve; The flow regulating feed pump can control ratio and the power consumption of fresh water and hydrogen; Operation regulates valve can regulate cost of electricity-generating and net electric generation, by above-mentioned synergism, it is possible to meet the requirement of water power hydrogen difference changes in demand simultaneously. It addition, the flow regulating feed pump can realize water hydrogen coproduction mode, closing control valve can switch to water-electricity cogeneration pattern, and therefore the method for operation is flexible and changeable, strong adaptability.
4) equipment dependability is improved. The high-temperature exhaust air of helium turbine only has partial discharge to pass through regenerator, hence it is evident that reduce the size of regenerator, solves that regenerator in the enclosed circulated helium of backheat is bulky, complex process, the engineering difficult point that involves great expense.
5) environmental pollution is reduced. Nuclear energy power generation and steam electrolytic hydrogen manufacturing that the present invention adopts are all the cleaning modes of production, do not result in air pollution, whole system only has a small amount of concentrated seawater discharged to extraneous and can be used for salt manufacturing, still needs to general kernel power station condenser to compared with environmental emission in a large number temperature sea water, polluting and reduce further.
6) good in economic efficiency. The present invention adopts sea water hydrogen manufacturing need not spend any cost of material, coupling nuclear energy can effectively save fuel cost, between the multi-mode of water power hydrogen Poly-generation, flexible handover operation is conducive to improving the market competitiveness, increase overall economic efficiency.
In sum, nuclear power station enclosed circulated helium system and senior middle school's temperature steam electrolytic hydrogen manufacturing technique and distillation sea water desalting technique are coupled by the present invention, it is truly realized the various modes of water power hydrogen three coproduction, have thermal efficiency of cycle height, to regulate performance good, improve equipment dependability, reduce environmental pollution, the feature such as good in economic efficiency, has significantly high economic worth and good application prospect.
Below in conjunction with the drawings and specific embodiments, the present invention is further illustrated.
Accompanying drawing explanation
Fig. 1 is the system structure schematic diagram of the present invention.
Detailed description of the invention
One, device
As shown in Figure 1, the present invention is a kind of nuclear power station HTGR power generating and hydrogen producing preparing fresh water three co-generation system, and it includes nuclear power station enclosed circulated helium system 1, superheater 2, steam generator 3, former seawater pipeline 4, flash vessel 5, steam jet ejector 6, sea water desalinating unit 7, feed pump 8, means of solid oxide electrolytic cell 9, auxiliary steam pipeline 10. Described nuclear power station enclosed circulated helium system 1 includes compressor 11, regenerator 12, HTGR 13, gas turbine generator group 14, regulates valve 15, cooler 16 and relevant pipeline and form a single loop circulation;The air exit 141 of described gas turbine generator group 14 is divided into two-way: a road is connected with the helium import 121 of regenerator 12 high temperature side and arranges adjustment valve 15 on this pipeline, and another road is connected with the helium import 21 of superheater 2; The helium outlet 22 of described superheater 2 is connected with the helium import 31 of steam generator 3, the steam (vapor) outlet 23 of superheater 2 is divided into two-way: a road is connected with auxiliary steam pipeline 10, and another road is connected with the steam inlet 91 of means of solid oxide electrolytic cell 9 and arranges control valve 92 on this pipeline; The helium outlet 32 of described steam generator 3 is connected with the helium import 161 of cooler 16, and the saturated vapor outlet 33 of steam generator 3 is connected with the steam inlet 24 of superheater 2; It is connected with the sea intake 51 of flash vessel 5 after described former seawater pipeline 4 spiral or tortuous traverse cooler 16, the flash-off steam outlet 52 of described flash vessel 5 is connected with the low pressure steam inlet 61 of steam jet ejector 6, and the concentrated seawater outlet 53 of flash vessel 5 is connected with the sea intake 71 of sea water desalinating unit 7; The high pressure steam inlet 62 of described steam jet ejector 6 is connected with auxiliary steam pipeline 10, and the steam (vapor) outlet 63 of steam jet ejector 6 is connected with the thermal source import 72 of sea water desalinating unit 7; The desalination water outlet 73 of described sea water desalinating unit 7 is divided into two-way: a road exports as product water, and another road is connected with the feed-water inlet 34 of steam generator 3 and assigns water pump 8 on this pipeline, and sea water desalinating unit 7 is provided with sewage draining exit 74; Described auxiliary steam pipeline 10 two ends are connected with the steam (vapor) outlet 23 of superheater 2 and the high pressure steam inlet 62 of steam jet ejector 6 respectively.
The delivery temperature of described gas turbine generator group 14 is between 550��650 DEG C; Sea intake 51 temperature of described flash vessel 5 is between 100��150 DEG C, and the flash-off steam of flash vessel 5 exports 52 temperature between 40��50 DEG C; The saturated vapor of described steam generator 3 exports 33 temperature between 200��374 DEG C; Steam (vapor) outlet 23 temperature of described superheater 2 is at 520��620 DEG C.
Two, method
The present invention is a kind of method of nuclear power station HTGR power generating and hydrogen producing preparing fresh water three coproduction, and it includes procedure below:
1) form hot sea water entrance flash vessel 5 after cooled device 16 heat absorption of the sea water in former seawater pipeline 4 and flash process occurs. The flash-off steam of flash vessel 5 enters steam jet ejector 6 to be carried out injection by the high steam from auxiliary steam pipeline 10 and is mixed into the steam of higher temperature and goes to sea water desalinating unit 7 as driving heat source, and the concentrated seawater of flash vessel 5 delivers to sea water desalinating unit 7 as charging sea water. The desalination water of sea water desalinating unit 7 output is divided into two-way: a road exports as product water, and another is routed to water pump 8 and is delivered to steam generator 3 as feedwater. Feedwater heat absorption evaporation in steam generator 3 forms high steam, high steam forms superheated steam through the further heat temperature raising of superheater 2, a part of superheated steam goes to means of solid oxide electrolytic cell 9 to carry out electrolytic hydrogen production, and another part superheated steam goes to steam jet ejector 6 as injection vapour by auxiliary steam pipeline 10;
2) the high temperature helium of HTGR 13 core exit enters helium turbine generator group 14 work done generating, and part generated energy provides the electric power of electrolytic hydrogen production. The high-temperature exhaust air of helium turbine generator group 14 is divided into two-way, one tunnel goes to regenerator 12 high temperature side to carry out waste heat recovery, another road successively delivers to superheater 2 and steam generator 3 is sequentially carried out heat release, two-way helium after heat release again merges together and enters cooler 16 and cools down, and the helium after cooling successively reenters HTGR 13 after compressor 11 compression and the heating of regenerator 12 low temperature side and carries out next round circulation.
The above is only the better embodiment to the present invention, not the present invention is done any pro forma restriction, every any simple modification embodiment of above done according to the technical spirit of the present invention, equivalent variations and modification, belong in the scope of technical solution of the present invention.
Claims (3)
1. nuclear power station HTGR power generating and hydrogen producing preparing fresh water three co-generation system, it is characterised in that: it includes nuclear power station enclosed circulated helium system, superheater, steam generator, former seawater pipeline, flash vessel, steam jet ejector, sea water desalinating unit, feed pump, means of solid oxide electrolytic cell, auxiliary steam pipeline; Described nuclear power station enclosed circulated helium system includes compressor, regenerator, HTGR, gas turbine generator group, regulates valve, cooler and relevant pipeline and form a single loop circulation; The air exit of described gas turbine generator group is divided into two-way: a road is connected and arranges on this pipeline adjustment valve with the helium import of regenerator high temperature side, and another road is connected with the helium import of superheater; The helium outlet of described superheater is connected with the helium import of steam generator, the steam (vapor) outlet of superheater is divided into two-way: a road is connected with auxiliary steam pipeline, and another road is connected with the steam inlet of means of solid oxide electrolytic cell and arranges control valve on this pipeline; The helium outlet of described steam generator is connected with the helium import of cooler, and the saturated vapor outlet of steam generator is connected with the steam inlet of superheater; It is connected with the sea intake of flash vessel after described former seawater pipeline spiral or tortuous traverse cooler; The flash-off steam outlet of described flash vessel is connected with the low pressure steam inlet of steam jet ejector, and the concentrated seawater outlet of flash vessel is connected with the sea intake of sea water desalinating unit; The high pressure steam inlet of described steam jet ejector is connected with auxiliary steam pipeline, and the steam (vapor) outlet of steam jet ejector is connected with the thermal source import of sea water desalinating unit; The desalination water outlet of described sea water desalinating unit is divided into two-way: a road exports as product water, and another road is connected with the feed-water inlet of steam generator and assigns water pump on this pipeline, and sea water desalinating unit is provided with sewage draining exit; Described auxiliary steam pipeline two ends are connected with the steam (vapor) outlet of superheater and the high pressure steam inlet of steam jet ejector respectively.
2. nuclear power station HTGR power generating and hydrogen producing preparing fresh water three co-generation system according to claim 1, it is characterised in that: the delivery temperature of described gas turbine generator group is between 550��650 DEG C; The injection temperature of described flash vessel is between 100��150 DEG C, and the flash-off steam outlet temperature of flash vessel is between 40��50 DEG C; The saturated vapor outlet temperature of described steam generator is between 200��374 DEG C; The steam exit temperature of described superheater is at 520��620 DEG C.
3. the method for nuclear power station HTGR power generating and hydrogen producing preparing fresh water three co-generation system according to claim 1, it is characterised in that include procedure below:
1) form hot sea water after the cooled device heat absorption of the sea water in former seawater pipeline and enter flash vessel generation flash process; The flash-off steam of flash vessel enters steam jet ejector to be carried out injection by the high steam from auxiliary steam pipeline and is mixed into the steam of higher temperature and goes to sea water desalinating unit as driving heat source, and the concentrated seawater of flash vessel delivers to sea water desalinating unit as charging sea water; The desalination water of sea water desalinating unit output is divided into two-way: a road exports as product water, and another is routed to water pump and is delivered to steam generator as feedwater; Feedwater heat absorption evaporation in steam generator forms high steam, high steam forms superheated steam through the further heat temperature raising of superheater, a part of superheated steam goes to means of solid oxide electrolytic cell to carry out electrolytic hydrogen production, and another part superheated steam goes to steam jet ejector as injection vapour by auxiliary steam pipeline;
2) the high temperature helium of HTGR core exit enters the generating of helium turbine work done drive electrical generators, and part generated energy provides the electric power of electrolytic hydrogen production;The high-temperature exhaust air of helium turbine is divided into two-way: a road goes to regenerator high temperature side to carry out waste heat recovery, another road successively delivers to superheater and steam generator is sequentially carried out heat release, two-way helium after heat release again merges together and enters cooler and cools down, and the helium after cooling successively reenters HTGR after compressor compression and the heating of regenerator low temperature side and carries out next round circulation.
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201610115011.3A CN105645499A (en) | 2016-03-02 | 2016-03-02 | Tri-cogeneration system and tri-cogeneration method for generating power, producing hydrogen and producing fresh water by aid of high-temperature gas-cooled reactor of nuclear power plant |
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| CN107017634A (en) * | 2017-04-11 | 2017-08-04 | 赫普热力发展有限公司 | The system that a kind of electrolytic hydrogen production is combined with nuclear power station flexibility peak regulation |
| CN107034480A (en) * | 2017-04-11 | 2017-08-11 | 赫普热力发展有限公司 | The system that a kind of utilization thermal power plant peak regulation electric power passes through high-temp solid electrolytic cell hydrogen manufacturing |
| CN107100808A (en) * | 2017-05-27 | 2017-08-29 | 集美大学 | Solar energy supercritical carbon dioxide circulating generation couples water vapour electrolytic hydrogen production system |
| CN107355272A (en) * | 2017-08-14 | 2017-11-17 | 西安热工研究院有限公司 | A kind of helium Steam Combined Cycle thermoelectric cold triple supply system and method |
| CN108277047A (en) * | 2018-01-26 | 2018-07-13 | 中国科学院上海高等研究院 | A kind of zero carbon emission system and method for nuclear energy-coal production fuel chemicals |
| CN108439336A (en) * | 2018-05-08 | 2018-08-24 | 上海发电设备成套设计研究院有限责任公司 | A kind of zero-emission cogeneration of hydrogen and electricity system |
| CN108715435A (en) * | 2018-05-23 | 2018-10-30 | 哈尔滨工业大学 | Spentnuclear fuel reuse means based on plasma electric power generation and biomass pyrolytic hydrogen manufacturing |
| CN109485044A (en) * | 2017-09-12 | 2019-03-19 | 陈志强 | Submarine fresh water air safeguards system and its method |
| CN110923738A (en) * | 2019-12-02 | 2020-03-27 | 中国科学院上海应用物理研究所 | Device and method for preparing hydrogen by electrolyzing seawater at high temperature |
| CN112562879A (en) * | 2020-12-03 | 2021-03-26 | 东北大学 | Energy cascade utilization multi-element energy supply system based on nuclear energy |
| CN113086945A (en) * | 2021-04-14 | 2021-07-09 | 中核能源科技有限公司 | High-temperature gas cooled reactor hydrogen-electricity-water heat cogeneration system |
| CN113417703A (en) * | 2021-05-31 | 2021-09-21 | 南京航空航天大学 | Solar wet helium turbine circulation electricity-water-salt three-coproduction zero-emission system and method |
| CN113782233A (en) * | 2021-09-10 | 2021-12-10 | 南京航空航天大学 | Space nuclear power circulation system based on integration of pulse heat exchange and water-oxygen decarbonization |
| CN114481163A (en) * | 2022-01-26 | 2022-05-13 | 西安热工研究院有限公司 | High-temperature gas cooled reactor direct hydrogen production coupling steam circulation power generation system |
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| CN107017634A (en) * | 2017-04-11 | 2017-08-04 | 赫普热力发展有限公司 | The system that a kind of electrolytic hydrogen production is combined with nuclear power station flexibility peak regulation |
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| CN109485044A (en) * | 2017-09-12 | 2019-03-19 | 陈志强 | Submarine fresh water air safeguards system and its method |
| CN108277047A (en) * | 2018-01-26 | 2018-07-13 | 中国科学院上海高等研究院 | A kind of zero carbon emission system and method for nuclear energy-coal production fuel chemicals |
| CN108439336A (en) * | 2018-05-08 | 2018-08-24 | 上海发电设备成套设计研究院有限责任公司 | A kind of zero-emission cogeneration of hydrogen and electricity system |
| CN108439336B (en) * | 2018-05-08 | 2024-02-02 | 上海发电设备成套设计研究院有限责任公司 | Zero-emission hydrogen electric cogeneration system |
| CN108715435A (en) * | 2018-05-23 | 2018-10-30 | 哈尔滨工业大学 | Spentnuclear fuel reuse means based on plasma electric power generation and biomass pyrolytic hydrogen manufacturing |
| CN108715435B (en) * | 2018-05-23 | 2021-08-24 | 哈尔滨工业大学 | Spent fuel recycling device based on plasma power generation and biomass pyrolysis hydrogen production |
| CN110923738A (en) * | 2019-12-02 | 2020-03-27 | 中国科学院上海应用物理研究所 | Device and method for preparing hydrogen by electrolyzing seawater at high temperature |
| CN110923738B (en) * | 2019-12-02 | 2021-02-05 | 中国科学院上海应用物理研究所 | Device and method for preparing hydrogen by electrolyzing seawater at high temperature |
| CN112562879A (en) * | 2020-12-03 | 2021-03-26 | 东北大学 | Energy cascade utilization multi-element energy supply system based on nuclear energy |
| CN113086945A (en) * | 2021-04-14 | 2021-07-09 | 中核能源科技有限公司 | High-temperature gas cooled reactor hydrogen-electricity-water heat cogeneration system |
| CN113417703A (en) * | 2021-05-31 | 2021-09-21 | 南京航空航天大学 | Solar wet helium turbine circulation electricity-water-salt three-coproduction zero-emission system and method |
| CN113782233A (en) * | 2021-09-10 | 2021-12-10 | 南京航空航天大学 | Space nuclear power circulation system based on integration of pulse heat exchange and water-oxygen decarbonization |
| CN113782233B (en) * | 2021-09-10 | 2024-03-22 | 南京航空航天大学 | Spatial nuclear power circulation system based on pulse heat exchange and water oxygen carbon removal integration |
| CN114481163A (en) * | 2022-01-26 | 2022-05-13 | 西安热工研究院有限公司 | High-temperature gas cooled reactor direct hydrogen production coupling steam circulation power generation system |
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