CN103818978B - High-temperature gas cooled reactor nuclear electric power generation and sea water desalination device - Google Patents
High-temperature gas cooled reactor nuclear electric power generation and sea water desalination device Download PDFInfo
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- CN103818978B CN103818978B CN201410075887.0A CN201410075887A CN103818978B CN 103818978 B CN103818978 B CN 103818978B CN 201410075887 A CN201410075887 A CN 201410075887A CN 103818978 B CN103818978 B CN 103818978B
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- temperature gas
- gas cooled
- heat
- cooled reactor
- fresh water
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- 239000013535 sea water Substances 0.000 title claims abstract description 50
- 238000010248 power generation Methods 0.000 title claims abstract description 10
- 238000010612 desalination reaction Methods 0.000 title abstract 3
- 239000013505 freshwater Substances 0.000 claims abstract description 42
- 239000007789 gas Substances 0.000 claims abstract description 42
- 239000001307 helium Substances 0.000 claims abstract description 28
- 229910052734 helium Inorganic materials 0.000 claims abstract description 28
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 claims abstract description 28
- 235000002639 sodium chloride Nutrition 0.000 claims abstract description 13
- FAPWRFPIFSIZLT-UHFFFAOYSA-M Sodium chloride Chemical compound [Na+].[Cl-] FAPWRFPIFSIZLT-UHFFFAOYSA-M 0.000 claims abstract description 10
- 239000011780 sodium chloride Substances 0.000 claims abstract description 10
- 238000001704 evaporation Methods 0.000 claims description 19
- 230000008020 evaporation Effects 0.000 claims description 19
- 230000015572 biosynthetic process Effects 0.000 claims description 2
- 230000005611 electricity Effects 0.000 abstract description 4
- 150000003839 salts Chemical class 0.000 abstract description 3
- 230000008016 vaporization Effects 0.000 abstract 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 7
- 238000005516 engineering process Methods 0.000 description 4
- 230000008901 benefit Effects 0.000 description 3
- 238000010586 diagram Methods 0.000 description 3
- 230000005855 radiation Effects 0.000 description 3
- 238000004364 calculation method Methods 0.000 description 2
- 238000001816 cooling Methods 0.000 description 2
- 238000010438 heat treatment Methods 0.000 description 2
- 239000007788 liquid Substances 0.000 description 2
- 238000012827 research and development Methods 0.000 description 2
- 239000003643 water by type Substances 0.000 description 2
- 239000002028 Biomass Substances 0.000 description 1
- 239000012141 concentrate Substances 0.000 description 1
- 238000009833 condensation Methods 0.000 description 1
- 230000005494 condensation Effects 0.000 description 1
- 239000013078 crystal Substances 0.000 description 1
- 230000007613 environmental effect Effects 0.000 description 1
- 238000003912 environmental pollution Methods 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 238000001556 precipitation Methods 0.000 description 1
- 230000003014 reinforcing effect Effects 0.000 description 1
- 230000002441 reversible effect Effects 0.000 description 1
- 239000013589 supplement Substances 0.000 description 1
- 239000002918 waste heat Substances 0.000 description 1
Classifications
-
- 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
- Y02A—TECHNOLOGIES FOR ADAPTATION TO CLIMATE CHANGE
- Y02A20/00—Water conservation; Efficient water supply; Efficient water use
- Y02A20/124—Water desalination
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- Engine Equipment That Uses Special Cycles (AREA)
Abstract
The invention provides a high-temperature gas cooled reactor nuclear electric power generation and sea water desalination device. A plurality of groups of Stirling generators and heat exchangers equivalent with the Stirling generators in number are arranged on the periphery of a high-temperature gas cooled reactor. One heat exchanger is communicated with the high-temperature gas cooled reactor via a gaseous helium loop pipe; the heat inflow end air cylinder and a connecting pipe of the air cylinder and a heat regenerator of one group of Stirling generator are placed in the same heat exchanger; a heat outflow end air cylinder and a connecting pipe of the air cylinder and a heat regenerator of one group of Stirling generator are placed in the same sea water vaporizing tank; a generator is placed in a secondary sealed cavity in the center of a heat outflow end; one fresh water condenser is mounted on one sea water vaporizing tank, so that a plurality of Stirling generator units capable of independently operating are formed. Electricity, fresh water and sea salt are jointly produced, so that the device is equal to a combination of one generation plant, a sea water desalination plant and one salt field. The device avoids emission, and is high in the utilization ratio of resources, economical, safe and environmental-friendly.
Description
Art
The present invention relates to a kind of nuclear power generation and sea water desalinating plant, be specially a kind of high temperature gas cooled reactor nuclear power generation and sea water desalinating plant.
Background technology
Energy shortage, the focus that the source has dried up, environmental pollution has become the universe jointly to pay close attention to, it is the only way solving energy water source problem and protection of the environment that exploitation clean energy desalinizes seawater.Except the renewable energy sources such as sun power, biomass energy, water energy, under the premise that security is guaranteed, nuclear energy is a kind of clean energy.The 4th generation of technology such as nuclear energy system high temperature gas cooled reactor is very safe thermonuclear reactor.But, become electric energy to use vapor wheel generator reactor thermal energy always.High temperature gas cooled reactor temperatures as high 1600 DEG C, primary Ioops helium outlet temperature is more than 700 DEG C.Also directly do not utilize the heat engine of so high temperature to generate electricity at present, have the potential ability that stirling generator has the so high temperature to generate electricity of efficiency utilization only.
Stirling generator can make full use of the high advantage of high temperature gas-cooled stack temperature, is because the higher efficiency of heat engine of heat source temperature of stirling generator is higher, and obtains fresh water when cooled with seawater heat outflow end.A kind of stirling generator (2014100264527) utilizing waste heat to desalinize seawater of Chinese patent provides efficiency utilization high temperature gas cooled reactor heat energy power-generating and the technology being separated seawater.
It is not that simple heat engine is replaced that stirling generator replaces vapor wheel generator, but a technology leap, maximally utilise nuclear energy and seawater resources.The combination of this high temperature gas cooled reactor and stirling generator is equivalent to a power station, a desalimtor, a salt field trinity.Be conducive to environment protection, remarkable in economical benefits.
Summary of the invention
The object of the invention is to utilize high temperature gas cooled reactor to flow into end supply heat directly to the heat of stirling generator, utilize seawater to absorb heat at the heat outflow end of stirling generator, while generating, seawater is separated into fresh water and salt.
To achieve these goals, the solution of the present invention is: its structure comprises high temperature gas cooled reactor, interchanger, helium circuit pipe, stirling generator, blower fan, evaporation of seawater tank, fresh water condenser, seawater inflow pipe, sea salt outlet valve, fresh water outlet pipe.It is characterized in that: surrounding's distribution many groups stirling generator of described high temperature gas cooled reactor and the interchanger of equal amts.An interchanger is communicated with high temperature gas cooled reactor through a helium circuit pipe; The heat of same group of stirling generator flows into end cylinder and heat flows into end cylinder and regenerator pipe connecting is placed in same interchanger; The heat outflow end cylinder of same group of stirling generator and heat outflow end cylinder thereof and regenerator pipe connecting are placed in same evaporation of seawater tank; The heat outflow end cylinder of one group of stirling generator and cylinder and regenerator pipe connecting are placed in same evaporation of seawater tank; Generator is placed in the secondary seal chamber of heat outflow end central authorities.A fresh water condenser is positioned on an evaporation of seawater tank.Fresh water condenser air inlet of air duct is in fresh water condenser central upper portion, and fresh water condenser duct outlet on fresh water condenser top ringwise.A fresh water condenser air inlet of air duct installs a Fans and a seawater inflow pipe, pacifies a fresh water outlet pipe at the bottom of a fresh water condenser.A sea salt outlet valve is installed at the bottom of an evaporation of seawater tank.Form the stirling generator group of many group energy independent operatings.
Described high temperature gas cooled reactor comprises reactor main body and Controlling System thereof.
Helium gas circulator, same group of heat inflow end cylinder and heat thereof is had to flow into end cylinder and regenerator pipe connecting in each interchanger described.
Described helium circuit pipe has the passage that helium flows into high temperature gas cooled reactor and helium outflow high temperature gas cooled reactor formation loop.
Described stirling generator is that Stirling reversible heat engine makes generator, and regenerator adopts heat-exchanger type regenerator, and Controlling System adopts the stirling engine Controlling System of working chamber supercharging, and working chamber connects employing many rings mode of connection.
Described stirling generator working medium is helium.
The invention has the advantages that: one is electricity, fresh water, sea salt coproduction, and without any discharge, resource utilization is high, economic security environmental protection; Two is that the good cooling results of cooled with seawater stirling engine heat outflow end, temperature are low, and heat engine reinforcing degree is high, and efficiency of heat engine is high; Three is that stirling generator is simpler than vapor wheel electric generator structure compact, and manufacturing cost and working cost reduce; Four is that helium replacement water makes working medium, and eliminate water treating equipment, equipment dependability improves.
Accompanying drawing explanation
Below in conjunction with accompanying drawing and embodiment, the invention will be further described:
Fig. 1 is overall structure schematic diagram of the present invention;
Fig. 2 is feature structure schematic diagram of the present invention;
Fig. 3 is calculation of thermodynamics sectional drawing of the present invention.
In Fig. 2,1, rod drive mechanism, 2, high temperature gas cooled reactor, 3, helium circuit pipe, 4, interchanger, 5, sea salt outlet valve, 6, evaporation of seawater tank, 7, fresh water outlet pipe, 8, fresh water condenser duct outlet, 9, fresh water condenser air inlet of air duct, 10, blower motor, 11, fresh water condenser, 12, seawater inflow pipe.
Embodiment
The present embodiment makes thermal source by the 10MW high temperature gas cooled reactor of Tsing-Hua University's research and development, configures the stirling generator of four group of six working chamber biarc connecting, form a set of high temperature gas cooled reactor nuclear power generation and sea water desalinating plant.The stirling generator of four group of six working chamber biarc connecting is symmetrically distributed in around high temperature gas cooled reactor.The heat of one group of stirling generator flows into end cylinder and cylinder and regenerator pipe connecting and is placed in same interchanger; An interchanger is communicated with high temperature gas cooled reactor through a helium circuit pipe; The heat outflow end cylinder of one group of stirling generator and cylinder and regenerator pipe connecting are placed in same evaporation of seawater tank; A fresh water condenser is positioned on an evaporation of seawater tank.Fig. 1 is overall structure schematic diagram.Because four groups of stirling generators are identical.Choose wherein one group of stirling generator to illustrate with coordinating of high temperature gas cooled reactor.
Fig. 2 indicates the feature structure of this cooperation.High temperature gas cooled reactor 2 there is rod drive mechanism 1.Interchanger 4 is communicated with high temperature gas cooled reactor 2 by helium circuit pipe 3.The heat of stirling generator flows into end cylinder and cylinder and regenerator pipe connecting and is placed in interchanger 4; The heat outflow end cylinder of stirling generator and cylinder and regenerator pipe connecting are placed in evaporation of seawater tank 6; Generator is placed in the secondary seal chamber of heat outflow end central authorities.Fresh water condenser 11 is positioned on evaporation of seawater tank 6.Fresh water condenser air inlet of air duct 9 installs blower motor 10 and seawater inflow pipe 12, fresh water condenser 11 end peace fresh water outlet pipe 7.Fresh water condenser duct outlet 8 ringwise, is positioned at fresh water condenser 11 top.Sea salt outlet valve 5 is arranged on bottom evaporation of seawater tank 6.
The 10MW high temperature gas cooled reactor technical parameter of Tsing-Hua University's research and development: thermal power 10MW, helium circuit pressure 3MPa, helium temperature in 250/300 DEG C, helium outlet temperature 700/900 DEG C, fuel sphere number 27000.Thermal energy according to 35% is energy calculate, and electric power is 3.5MW.With four groups of stirling generators, often organize electric power between 0.8MW to 0.9MW.Setting working parameter: maximum working pressure P
2for 9MPa, efficiency of heat engine is 0.3, and heat flows into end temperature T
2for 973.15K, heat outflow end temperature T
1for 353.15K, rotating speed N is 900 revs/min.Determine main structure parameters: cylinder diameter 0.2m, stroke 0.15m.
Fig. 3 is the calculation of thermodynamics of a working chamber, and electromotive power output Power is 0.142MW, Endothermic power P
hfor 0.4734MW, heat radiation power P
cfor 0.3314MW, minimum operating pressure P
1for 3.244MPa.
One group of unit has six working chambers, and electromotive power output is 0.852MW, total Endothermic power 2.8404MW, total heat radiation power 1.9884MW.Have four groups of stirling generators, complete assembly electromotive power output is 3.408MW, heat radiation power is 1.3256MW.
Working process of the present invention is: the control signal that high temperature gas cooled reactor 2 Controlling System sends controls reactor core heating power through rod drive mechanism 1.Helium gas circulator running in interchanger 4, form helium in interchanger 4 and arrive high temperature gas cooled reactor 2 reactor core through helium circuit pipe 3, get back to the loop of interchanger 4 again through helium circuit pipe 3, heating heat in heat transportation to interchanger 4 is flowed into end cylinder and cylinder and regenerator pipe connecting.The helium that heat flows in end cylinder and cylinder and regenerator pipe connecting absorbs heat, and completes the heat exchange that high temperature gas cooled reactor 2 arrives stirling generator.Stirling generator six working chambers press Stirling cycle work, and heat engine rotor drives generator rotation generating.In heat outflow end cylinder and cylinder and regenerator pipe connecting, helium is because compressing heat release, and seawater enters in evaporation of seawater tank 6 by seawater inflow pipe 12, cooling heat outflow end cylinder and cylinder and regenerator pipe connecting.Start blower motor 10, air passes into below evaporation of seawater tank 6 maritime interior waters liquid level from fresh water condenser air inlet of air duct 9, is taken to by water vapour after fresh water condenser condenses into water, blows to fresh water condenser radiator element through fresh water condenser duct outlet 8.Water of condensation is flowed out by the fresh water outlet pipe 7 at fresh water condenser 11 end.Constantly supplement seawater, make evaporation of seawater tank 6 maritime interior waters liquid level keep stable.Along with seawater constantly concentrates, salinity, when the precipitation of evaporation of seawater tank 6 bottom crystal reaches a certain amount of, is opened sea salt outlet valve 5 and is discharged sea salt.Four groups of stirling generators work simultaneously, the oepration at full load of 10MW high temperature gas cooled reactor.
Claims (4)
1. a high temperature gas cooled reactor nuclear power generation and sea water desalinating plant, comprise high temperature gas cooled reactor, interchanger, helium circuit pipe, stirling generator, blower fan, evaporation of seawater tank, fresh water condenser, seawater inflow pipe, sea salt outlet valve, fresh water outlet pipe, it is characterized in that: surrounding's distribution many groups stirling generator of described high temperature gas cooled reactor and the interchanger of equal amts, an interchanger is communicated with high temperature gas cooled reactor through a helium circuit pipe, the heat of same group of stirling generator flows into end cylinder and heat flows into end cylinder and regenerator pipe connecting is placed in same interchanger, the heat outflow end cylinder of same group of stirling generator and heat outflow end cylinder thereof and regenerator pipe connecting are placed in same evaporation of seawater tank, generator is placed in the secondary seal chamber of heat outflow end central authorities, a fresh water condenser is positioned on an evaporation of seawater tank, fresh water condenser air inlet of air duct is in fresh water condenser central upper portion, fresh water condenser duct outlet on fresh water condenser top ringwise, a fresh water condenser air inlet of air duct installs a Fans and a seawater inflow pipe, a fresh water outlet pipe is pacified at the bottom of a fresh water condenser, a sea salt outlet valve is installed at the bottom of an evaporation of seawater tank, form the stirling generator group of many group energy independent operatings.
2. a kind of high temperature gas cooled reactor nuclear power generation according to claim 1 and sea water desalinating plant, is characterized in that: described high temperature gas cooled reactor comprises reactor main body and Controlling System thereof.
3. a kind of high temperature gas cooled reactor nuclear power generation according to claim 1 and sea water desalinating plant, is characterized in that: have helium gas circulator, same group of heat inflow end cylinder and heat thereof to flow into end cylinder and regenerator pipe connecting in each interchanger described.
4. a kind of high temperature gas cooled reactor nuclear power generation according to claim 1 and sea water desalinating plant, is characterized in that: described helium circuit pipe has the passage that helium flows into high temperature gas cooled reactor and helium outflow high temperature gas cooled reactor formation loop.
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| Application Number | Priority Date | Filing Date | Title |
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| CN201410075887.0A CN103818978B (en) | 2014-03-03 | 2014-03-03 | High-temperature gas cooled reactor nuclear electric power generation and sea water desalination device |
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| CN201410075887.0A CN103818978B (en) | 2014-03-03 | 2014-03-03 | High-temperature gas cooled reactor nuclear electric power generation and sea water desalination device |
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| CN103818978B true CN103818978B (en) | 2015-04-08 |
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Cited By (2)
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|---|---|---|---|---|
| US11855324B1 (en) | 2022-11-15 | 2023-12-26 | Rahul S. Nana | Reverse electrodialysis or pressure-retarded osmosis cell with heat pump |
| US12040517B2 (en) | 2022-11-15 | 2024-07-16 | Rahul S. Nana | Reverse electrodialysis or pressure-retarded osmosis cell and methods of use thereof |
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|---|---|---|---|---|
| CN104966535A (en) * | 2015-06-26 | 2015-10-07 | 上海核工程研究设计院 | Sea water desalination and residual heat removal dual-purpose system of floating nuclear power plant |
| 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 |
| US11502323B1 (en) | 2022-05-09 | 2022-11-15 | Rahul S Nana | Reverse electrodialysis cell and methods of use thereof |
| US11502322B1 (en) | 2022-05-09 | 2022-11-15 | Rahul S Nana | Reverse electrodialysis cell with heat pump |
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| US12040517B2 (en) | 2022-11-15 | 2024-07-16 | Rahul S. Nana | Reverse electrodialysis or pressure-retarded osmosis cell and methods of use thereof |
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| CN103818978A (en) | 2014-05-28 |
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