CN205367779U - Nuclear energy sea water desalination - Google Patents
Nuclear energy sea water desalination Download PDFInfo
- Publication number
- CN205367779U CN205367779U CN201520669527.3U CN201520669527U CN205367779U CN 205367779 U CN205367779 U CN 205367779U CN 201520669527 U CN201520669527 U CN 201520669527U CN 205367779 U CN205367779 U CN 205367779U
- Authority
- CN
- China
- Prior art keywords
- heat exchanger
- water
- steam
- valve
- condenser
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Active
Links
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
Landscapes
- Heat Treatment Of Water, Waste Water Or Sewage (AREA)
Abstract
The utility model provides a nuclear energy sea water desalination, including steam generator, a heat exchanger, flashing device, condenser, the steam generator export is connected to through main steam line through heat exchanger inlet regulating valve a heat exchanger's first import, the first export of heat exchanger is arrived through feedwater pipeline connection through water -feeding pump, water supply isolating valve, water supplying stop valve steam generator's entry, heat exchanger second export is connected through heat exchanger export relief pressure valve flashing device, flashing device is connected to the condenser through fresh water pipeline governing valve. The utility model provides a pair of nuclear energy sea water desalination can utilize nuclear energy to provide a large amount of fresh water vapours, life or process water, and the make full use of waste heat improves heat utilization efficiency and economic nature. And set up non - active residual heat removal system, have safe and reliable advantage.
Description
Technical field
This utility model relates to nuclear power station heat supply and water supply field, more particularly to a kind of nuclear desalination system.
Background technology
Fresh water is the source that the mankind depend on for existence, along with progress and the development of human society, the demand of freshwater resources is increasing.Tellurian freshwater resources are limited, but sea water is almost inexhaustible.Therefore desalination technology also constantly develops, cost also reduction gradually, and the water for industrial uses in a lot of countries both are from desalination technology.Flash distillation is desalination technology currently mainly, so-called flash distillation is to make hot charge water be incorporated in a relatively low space of pressure, owing to ambient pressure is lower than the saturated vapor pressure corresponding to the temperature of the raw water that is heated, now raw water part vaporization hastily as superheated water, produce steam, condensed and become fresh water.
Flash system is firstly the need of by heating of seawater, and cogeneration of heat and power flash evaporation seawater desalting technology is to utilize thermoelectricity to provide heat energy.Nuclear energy is a kind of clean energy resource, it is provided that a large amount of thermals source are for desalination technology.If a kind of seawater desalination system utilizing nuclear energy can be designed, then can the advantage of nuclear energy, built in seashore, utilize desalination technology to provide fresh water in a large number, meet productive life demand.
Utility model content
The purpose of this utility model is in that to provide a kind of nuclear desalination system, including steam generator, first heat exchanger, flash distillation plant, condenser, described steam generator outlet is regulated valve through heat exchanger inlets and is connected to the first import of described first heat exchanger by main steam pipe, described first heat exchanger first exports through feed pump, feedwater isolation valve, feed water check valve is connected to the entrance of described steam generator by water-supply line, described first heat exchanger second exports and connects described flash distillation plant through the first heat exchanger outlet air relief valve, described flash distillation plant is connected to condenser through fresh water pipe line control valve.
Further, the second heat exchanger also it is connected in parallel between described steam generator and described first heat exchanger, described second heat exchanger is arranged in water tank, described second heat exchanger one end is connected to main steam pipe through isolating valve by pipeline, and the described second heat exchanger other end is connected to water-supply line by isolating valve, check-valves.
Further, described system is provided with leakage detection circuit, according to the timely insulating sea water desalination heat-exchanging loop of the Radiation monitoring signal of steam generator secondary side.
Further, it is connected in parallel to Turbo-generator Set between described second heat exchanger and described first heat exchanger, one end of described Turbo-generator Set is entered steam control valve through steam turbine and is connected to main steam pipe by steam turbine steam inlet pipe line, the other end of described Turbo-generator Set is connected to condenser, described condenser is connected to supply line through condensing Water Check Valve by condensate pipe, the import of described condenser is connected to source of seawater by water circulating pump, and the outlet of described condenser connects the second import of described first heat exchanger.
Further, recirculated water enters flash tank after the second heat exchanger, and the steam after flash distillation is supplied to steam user, is supplied to fresh water user after steam after flash distillation is condensed, the hydrophobic water inlet as next stage flash tank of flash tank, it is provided that water supply industry salt produces user.
The purpose of this utility model is in that to provide a kind of nuclear desalination system, it is possible to use nuclear energy provides a large amount of fresh water steams, life or industrial water, makes full use of waste heat and improves heat utilization efficiency and economy.And it is provided with Heat Discharging System of Chinese, there is safe and reliable advantage.
For realizing described purpose nuclear desalination system, there is following main feature:
Electricity consumption needed for utilizing steam-electric power unit to provide for native system, is provided with heat-exchanging loop between the steam and water-supply line of steam generator, and by the heat-exchanging loop of steam generator secondary side, the heat that nuclear reactor produces is transferred to desalinization loop.It is provided with leakage detection circuit, according to the timely insulating sea water desalination heat-exchanging loop of the Radiation monitoring signal of steam generator secondary side.Steam condensed water after over-heat-exchanger enters water-supply line, and sends into steam generator and recycle.The circulation water outlet of condenser is as the water source in desalinization loop, thus improving heat utilization efficiency and economy.Recirculated water enters flash tank after heat exchanger, and the steam after flash distillation is provided to steam user.Recirculated water enters flash tank after heat exchanger, is provided to fresh water user after steam after flash distillation is condensed.The hydrophobic of flash tank can as the water inlet of next stage flash tank, it is also possible to is supplied to water and wastewater industry salt and produces user.It is provided with Heat Discharging System of Chinese.When losing feedwater, reactor core heat is taken out of Heat Discharging System of Chinese.
Accompanying drawing explanation
Fig. 1 nuclear desalination system flow sketch.
Accompanying drawing labelling
1-reactor 2-reactor coolant pipe 3-reactor coolant pump 4-steam generator
5-main steam pipe 6-steam discharge line 7-steam release valve 8-main steam isolation valve
null9-Waste heat isolation valve discharge line entrance 10-11 - waste heat discharge waste heat discharge pipe heat exchanger 12-13 - waste heat water tank discharge pipe outlet isolation valve 14 - waste heat discharge pipe outlet check valve 15 - feed lines 16 - radiation monitoring instrument 17-18 - turbine inlet steam turbine inlet steam pipeline regulator 19-20 - turbine exhaust steam turbo-generator set 21-22 - condenser water check 23-24 - feed pump condensate pipe 25-26 - feed check water supply isolation valve valve 27-28 heat exchanger import control valve leakage isolation signal 29 - heat exchanger inlet check valve 30-31 - sea water circulating pump 32 - circulating water drain drainage isolation valves 34 and 33 - circulating water heat exchanger inlet isolation valve 35 heat exchanger heat exchanger outlet pressure reducing valve 36 37 flash tank 38 - flash tank steam pipeline 39 - flash steam regulator 40 - user 41 - flash fresh water pipeline 42-43 - fresh water pipeline valve 45 - fresh water users 46-44 - condenser cooling water flash tank drain pipe 48-47 - flash tank drain valve industrial salt users or lower level flash tank
Detailed description of the invention
Understandable for enabling above-mentioned purpose of the present utility model, feature and advantage to become apparent from, below in conjunction with the drawings and specific embodiments, this utility model is described in further detail.
The present embodiment is carried out premised on technical solutions of the utility model, gives detailed embodiment and concrete operating process, but protection domain of the present utility model is not limited to following embodiment.
For apparent understanding this utility model, operate to example with nuclear desalination system below, in conjunction with Fig. 1, nuclear desalination system of the present utility model is described further.
Nuclear desalination system is arranged on outside the containment of reactor, the electricity consumption needed for utilizing steam-electric power unit to provide for native system, by the heat-exchanging loop between steam pipe line and water-supply line, carries substantial amounts of heat to sea water.When system is properly functioning, isolated with main steam pipe 5 and water-supply line 15 by Residual heat removal piping inlet isolating valve 9, Residual heat removal pipeline outlet isolating valve 13 and Residual heat removal pipeline outlet check-valves 14.Heat in reactor 1 passes to steam generator 4 by reactor coolant pipe 2 and reactor coolant pump 3, steam in main steam pipe 5 enters steam control valve 18 by steam turbine steam inlet pipe line 17 and steam turbine and enters Turbo-generator Set 19, the electric energy of output is for whole nuclear desalination system, and turbine discharge 20 enters water-supply line 15 through condensate pipe 23 after entering condenser 21 condensation.Opening heat exchanger inlets and regulate valve 27, part main steam enters heat exchanger 37, after transferring heat to sea water, enters steam generator 4 through feed pump 24, feedwater isolation valve 25 and feed-regulating valve 26 and water-supply line 15, forms closed circulation.Source of seawater 30 enters heat exchanger 35 after water circulating pump 31 pressurizes in condenser 21 after heat absorption, by recirculated water draining isolating valve 33 isolation cycle water drain pipe 32, enter flash tank 37 through heat exchanger outlet air relief valve 36 after sea water is heated.Sea water flash distillation in flash tank 37 of heating, the steam flashed off enters flash tank steam pipe line 38.Flash-off steam can regulate through flash-off steam and be supplied to steam user 40 after valve 39, it is also possible to enter flash distillation fresh water pipeline 41, enters condenser 44, after fresh water pipe line control valve 42 after supercooled water 43 cools down, it is provided that to fresh water user 45.The hydrophobic of flash tank 37 can through the hydrophobic air relief valve 47 of flash tank drain pipe 46 and flash tank, it is provided that to Nacl user or next stage flash tank 48.
When running without seawater desalination system, regulate valve 27 by heat exchanger inlets and heat exchanger 35 is isolated with main steam pipe 5 and water-supply line 15 by heat exchanger outlet check-valves 29.Simultaneously close off heat exchanger water inlet isolating valve 34, open recirculated water draining isolating valve 33, allow recirculated water discharge from recirculated water drain pipe 32.
When primary Ioops generator leaks, send leakage isolation signals 28 by the Radiation monitoring instrument 16 on steam generator 4, close main steam isolation valve 8 and feedwater isolation valve 25, thus effectively preventing radioactivity from entering Turbo-generator Set and desalinization loop.Now, open Residual heat removal piping inlet isolating valve 9 and Residual heat removal pipeline outlet isolating valve 13, transfer heat to the water in water tank 12 by residual heat removal exchanger 11, and be ultimately transferred to air, it is achieved take away reactor core heat.
When there is to lose feedwater event, close main steam isolation valve 8 and feedwater isolation valve 25, open Residual heat removal piping inlet isolating valve 9 and Residual heat removal pipeline outlet isolating valve 13, the water in water tank 12 is transferred heat to by residual heat removal exchanger 11, and it is ultimately transferred to air, it is achieved residual heat removal system function.
Said process utilizes nuclear energy to provide a large amount of fresh water steams, life or industrial water, makes full use of waste heat and improves heat utilization efficiency and economy.And it is provided with Heat Discharging System of Chinese, there is safe and reliable advantage.
The connection of former components is only exemplary illustration of the present utility model non-limitative illustration, it is also possible to be other connected modes.
Although accompanying drawing describes example comprehensively, but various diagram can illustrate exemplary architecture or other configurations of the disclosure, and it is used for helping to understand the feature that can include in the disclosure and function.The disclosure is not limited to the exemplary architecture or the configuration that illustrate, but available various substituting frameworks and configuration are implemented.Although it addition, describe the disclosure above with respect to various examples and realization, it should be appreciated that the various features of one or more description in the example shown and function are not limited to describe their specific examples in their suitability.But, one or more in other examples of the disclosure, they can be employed individually or in some combination, and no matter whether such example is described, and no matter such feature as a part for the example described by this place.Again, the scope of the present disclosure should not by any one restriction of above-mentioned example.
In this specification, each embodiment adopts the mode gone forward one by one to describe, and what each embodiment stressed is the difference with other embodiments, between each embodiment identical similar portion mutually referring to.For system disclosed in embodiment, owing to corresponding to the method disclosed in Example, so what describe is fairly simple, relevant part illustrates referring to method part.
Those skilled in the art specifically can should be used for using different methods to realize described function to each, but this realization is it is not considered that exceed scope of the present utility model.
Obviously, utility model can be carried out various change and modification without deviating from spirit and scope of the present utility model by those skilled in the art.So, if these amendments of the present utility model and modification belong within the scope of this utility model claim and equivalent technologies thereof, then this utility model is also intended to include these change and modification.
Claims (5)
1. a nuclear desalination system, it is characterized in that, including steam generator, first heat exchanger, flash distillation plant, condenser, described steam generator outlet is regulated valve through heat exchanger inlets and is connected to the first import of described first heat exchanger by main steam pipe, described first heat exchanger first exports through feed pump, feedwater isolation valve, feed water check valve is connected to the entrance of described steam generator by water-supply line, described first heat exchanger second exports and connects described flash distillation plant through the first heat exchanger outlet air relief valve, described flash distillation plant is connected to condenser through fresh water pipe line control valve.
2. nuclear desalination system as claimed in claim 1, it is characterized in that, the second heat exchanger also it is connected in parallel between described steam generator and described first heat exchanger, described second heat exchanger is arranged in water tank, described second heat exchanger one end is connected to main steam pipe through isolating valve by pipeline, and the described second heat exchanger other end is connected to water-supply line by isolating valve, check-valves.
3. nuclear desalination system as claimed in claim 1, it is characterised in that described system is provided with leakage detection circuit, according to the timely insulating sea water desalination heat-exchanging loop of the Radiation monitoring signal of steam generator secondary side.
4. nuclear desalination system as claimed in claim 2, it is characterized in that, it is connected in parallel to Turbo-generator Set between described second heat exchanger and described first heat exchanger, one end of described Turbo-generator Set is entered steam control valve through steam turbine and is connected to main steam pipe by steam turbine steam inlet pipe line, the other end of described Turbo-generator Set is connected to condenser, described condenser is connected to supply line through condensing Water Check Valve by condensate pipe, the import of described condenser is connected to source of seawater by water circulating pump, the outlet of described condenser connects the second import of described first heat exchanger.
5. nuclear desalination system as claimed in claim 4, it is characterized in that, recirculated water enters flash tank after the second heat exchanger, steam after flash distillation is supplied to steam user, it is supplied to fresh water user after steam after flash distillation is condensed, the hydrophobic water inlet as next stage flash tank of flash tank, it is provided that water supply industry salt produces user.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201520669527.3U CN205367779U (en) | 2015-08-31 | 2015-08-31 | Nuclear energy sea water desalination |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201520669527.3U CN205367779U (en) | 2015-08-31 | 2015-08-31 | Nuclear energy sea water desalination |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN205367779U true CN205367779U (en) | 2016-07-06 |
Family
ID=56260261
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201520669527.3U Active CN205367779U (en) | 2015-08-31 | 2015-08-31 | Nuclear energy sea water desalination |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN205367779U (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105060378A (en) * | 2015-08-31 | 2015-11-18 | 上海核工程研究设计院 | Nuclear energy seawater desalination 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 |
| CN114738065A (en) * | 2022-03-17 | 2022-07-12 | 西安热工研究院有限公司 | Fast neutron reactor thermoelectric water trigeminy supplies system |
-
2015
- 2015-08-31 CN CN201520669527.3U patent/CN205367779U/en active Active
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105060378A (en) * | 2015-08-31 | 2015-11-18 | 上海核工程研究设计院 | Nuclear energy seawater desalination 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 |
| CN112562879B (en) * | 2020-12-03 | 2024-05-14 | 东北大学 | Energy cascade utilization multi-element energy supply system based on nuclear energy |
| CN114738065A (en) * | 2022-03-17 | 2022-07-12 | 西安热工研究院有限公司 | Fast neutron reactor thermoelectric water trigeminy supplies system |
| CN114738065B (en) * | 2022-03-17 | 2023-09-12 | 西安热工研究院有限公司 | Thermal electric water triple supply system of fast neutron reactor |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN104021829B (en) | A kind of multiduty unsteady nuclear-energy plant | |
| CN103351034B (en) | High-temperature gas cooled reactor and low-temperature multiple-effect distillation seawater desalinization coupling device | |
| WO2012060510A1 (en) | Ocean geothermal power system using multi-step reheating rankine cycle | |
| CN103993922B (en) | A kind of low temperature exhaust heat CO 2rankine cycle system | |
| CN205367779U (en) | Nuclear energy sea water desalination | |
| CN110454764A (en) | A kind of the thermoelectricity decoupled system and operation method of cogeneration units | |
| CN204757076U (en) | Steam power plant's heat supply hydrophobic waste heat recovery system of drawing gas | |
| CN104075442A (en) | Water tank waste water heat recovery heat pump water heater | |
| CN205013056U (en) | Water and electricity cogeneration system | |
| CN204939171U (en) | A kind of portable nuclear desalination system | |
| CN207797210U (en) | A kind of waste heat recovery heat-exchange system reducing condensed water exhaust temperature | |
| CN202102727U (en) | Closed type cooling water system for nuclear power plant | |
| CN105060378A (en) | Nuclear energy seawater desalination system | |
| CN103034221B (en) | thermal power plant circulating water system | |
| KR20130000914A (en) | High efficiency differential temperature power system using the thermal effluents of power plant condenser | |
| CN104966535A (en) | Sea water desalination and residual heat removal dual-purpose system of floating nuclear power plant | |
| CN205035104U (en) | Nuclear power station sea water desalination | |
| CN110726132B (en) | Method and system for supplying water to steam generator of nuclear power station under low-power working condition | |
| RU170194U1 (en) | NUCLEAR POWER PLANT | |
| CN209083347U (en) | A kind of cooling system of indirect air cooling formula Turbo-generator Set | |
| CN102374692B (en) | Power-plant waste-heat recovering device | |
| KR101339676B1 (en) | District cooling and heating system connected to sewage disposal plant and incineration plant | |
| RU96283U1 (en) | PASSIVE HEAT REMOVAL SYSTEM THROUGH A STEAM GENERATOR | |
| CN207674551U (en) | A kind of cooling tower antifreezing system for the solidifying pumping back of the body heat supply of steam turbine | |
| CN205038970U (en) | Nuclear power station seawater desalination and residual heat removal system |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| CP01 | Change in the name or title of a patent holder |
Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee after: Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd. Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE |
|
| CP01 | Change in the name or title of a patent holder |