CN110265166A - A kind of no boron PWR nuclear power plant cvcs - Google Patents
A kind of no boron PWR nuclear power plant cvcs Download PDFInfo
- Publication number
- CN110265166A CN110265166A CN201910611851.2A CN201910611851A CN110265166A CN 110265166 A CN110265166 A CN 110265166A CN 201910611851 A CN201910611851 A CN 201910611851A CN 110265166 A CN110265166 A CN 110265166A
- Authority
- CN
- China
- Prior art keywords
- film
- heat exchanger
- power plant
- nuclear power
- boron
- 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.)
- Pending
Links
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 title claims abstract description 22
- 229910052796 boron Inorganic materials 0.000 title claims abstract description 22
- 239000002826 coolant Substances 0.000 claims abstract description 26
- 238000007872 degassing Methods 0.000 claims abstract description 25
- 230000001172 regenerating effect Effects 0.000 claims abstract description 19
- 238000000926 separation method Methods 0.000 claims abstract description 19
- 239000012535 impurity Substances 0.000 claims abstract description 8
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 claims abstract description 6
- 238000007599 discharging Methods 0.000 claims abstract description 6
- 239000001301 oxygen Substances 0.000 claims abstract description 6
- 229910052760 oxygen Inorganic materials 0.000 claims abstract description 6
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 8
- 239000007789 gas Substances 0.000 claims description 5
- 239000010808 liquid waste Substances 0.000 claims description 3
- 238000006392 deoxygenation reaction Methods 0.000 abstract description 7
- 239000001257 hydrogen Substances 0.000 abstract description 7
- 229910052739 hydrogen Inorganic materials 0.000 abstract description 7
- 230000005855 radiation Effects 0.000 abstract description 7
- 230000002285 radioactive effect Effects 0.000 abstract description 7
- 238000000034 method Methods 0.000 abstract description 5
- 239000011347 resin Substances 0.000 abstract description 5
- 229920005989 resin Polymers 0.000 abstract description 5
- 230000008569 process Effects 0.000 abstract description 4
- 239000002910 solid waste Substances 0.000 abstract description 3
- 238000000746 purification Methods 0.000 abstract description 2
- 125000004435 hydrogen atom Chemical class [H]* 0.000 abstract 1
- 150000002431 hydrogen Chemical class 0.000 description 4
- 230000008859 change Effects 0.000 description 3
- 230000007797 corrosion Effects 0.000 description 3
- 238000005260 corrosion Methods 0.000 description 3
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 description 2
- 230000004992 fission Effects 0.000 description 2
- 230000006872 improvement Effects 0.000 description 2
- 239000007787 solid Substances 0.000 description 2
- 239000012141 concentrate Substances 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 230000007812 deficiency Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 239000002360 explosive Substances 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 230000008929 regeneration Effects 0.000 description 1
- 238000011069 regeneration method Methods 0.000 description 1
- 239000002699 waste material Substances 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/08—Regulation of any parameters in the plant
- G21D3/12—Regulation of any parameters in the plant by adjustment of the reactor in response only to changes in engine demand
-
- 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
-
- 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
- Y02E30/30—Nuclear fission reactors
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Separation Using Semi-Permeable Membranes (AREA)
Abstract
It is an object of the invention to disclose a kind of no boron PWR nuclear power plant cvcs, it include regenerative heat exchanger, let down heat exchanger, lower discharging hole plate, high separation rate film, degassing film and on fill pump, reactor coolant is cooled to the suitable temperature of film work by the regenerative heat exchanger and let down heat exchanger, the reactor coolant of decrease temperature and pressure passes sequentially through high separation rate film and degassing film carries out purification and deoxygenation, returns to main system using above filling after pump pressurization heats up with regenerative heat exchanger；Compared with prior art, high separation rate film removal nucleic and impurity, reduce and use resin bed and filter, the dose of radiation that the personnel in the yield and replacement process of radioactive solid waste that reduce are subject to；Deoxygenation is carried out using degassing film, the oxygen content of reactor coolant limit value can be down to hereinafter, compared with prior art, avoiding using hydrogen, reduce nuclear power plant's danger source, personnel's operation is simplified, achieves the object of the present invention.
Description
Technical field
The present invention relates to a kind of nuclear power plant's cvcs, in particular to a kind of no boron PWR nuclear power plant
And volume control system.
Background technique
In traditional pressurized-water reactor nuclear power plant, the major functions of cvcs (hereinafter referred to as change appearance system) it
First is that the water chemistry condition of control reactor coolant, controls boron concentration, pH value and oxygen content in reactor coolant as required,
Corrosion product and fission product in reactor coolant are removed, to reduce the corrosion of primary Ioops, guarantees the complete of equipment and material
Whole property reduces reactor coolant radioactive level.
In general, reactor coolant is cooled down by change appearance system by heat exchanger, resin bed and filter removal corrosion are produced
Object and fission product control dissolved oxygen content by adding hydrogen, return to main system after regenerative heat exchanger heats.
Hydrogen is flammable explosive gas, and it is special that medium is both needed to carry out for pipe valve, equipment and the room of installation etc. of hydrogen
Explosion-proof Design, corresponding special regulation is also used in personnel's operation.Changing appearance system can be directly to reactor using degassing film
Coolant deoxygenation can reduce danger source in nuclear island and simplify personnel's operation.
Since reactor core is without boron, reactor coolant is that can remove reactor using high separation rate film with radioactive water
Nucleic and impurity in coolant.It is useless to reduce the solid radiations such as resin and filter core for the use for reducing resin bed and filter
The yield of object, while also reducing personnel's suffered dose of radiation during replacing resin and filter core.
It is accordingly required in particular to a kind of no boron PWR nuclear power plant cvcs, to solve above-mentioned existing deposit
The problem of.
Summary of the invention
The purpose of the present invention is to provide a kind of no boron PWR nuclear power plant cvcs, for existing skill
The deficiency of art is avoided using hydrogen, reduces nuclear power plant's danger source, simplifies personnel's operation, it is useless to reduce solid radiation
The dose of radiation that personnel are subject in the yield and replacement process of object.
Technical problem solved by the invention can be realized using following technical scheme:
A kind of no boron PWR nuclear power plant cvcs, which is characterized in that it include regenerative heat exchanger,
Let down heat exchanger, lower discharging hole plate, high separation rate film, degassing film and on fill pump, the regenerative heat exchanger and under expel the heat-evil exchange
Reactor coolant is down to suitable temperature by device, then is successively connected with high separation rate film and degassing film, and the degassing film goes out
Mouthful by above filling pump and regenerative heat exchanger is connected with main system.
In one embodiment of the invention, pass through lower discharging hole between the let down heat exchanger and the high separation rate film
Plate interconnects.
In one embodiment of the invention, the high separation rate film is used to remove the radioactive nucleus in reactor coolant
Element and impurity.
In one embodiment of the invention, the concentrated water side of the high separation rate film is connected with liquid waste system.
In one embodiment of the invention, the degassing film is used to remove the dissolved oxygen in reactor coolant.
In one embodiment of the invention, the output end of the degassing film is by above filling pump and the regenerative heat exchanger
It is connected.
In one embodiment of the invention, the gas phase side of the degassing film is connected with vacuum pump.
Of the invention utilizes heat exchange compared with prior art without boron PWR nuclear power plant cvcs
After device cools down to reactor coolant, nucleic and impurity are removed through high separation rate film, degassing film is passed through and carries out deoxygenation, after deoxygenation
Reactor coolant above filled pump pressurization and regenerative heat exchanger heating after return to main system, reduce radioactive solid waste
Yield and replacement process in the dose of radiation that is subject to of personnel, avoid using hydrogen, reduce nuclear power plant's danger source, simplify
Personnel operations, achieve the object of the present invention.
The features of the present invention sees the detailed description of the drawings of the present case and following preferable embodiment and obtains clearly
Solution.
Detailed description of the invention
Fig. 1 is the flow diagram of no boron PWR nuclear power plant cvcs of the invention.
Specific embodiment
In order to be easy to understand the technical means, the creative features, the aims and the efficiencies achieved by the present invention, tie below
Conjunction is specifically illustrating, and the present invention is further explained.
Embodiment
As shown in Figure 1, no boron PWR nuclear power plant cvcs of the invention, it includes regeneration heat exchange
Device 1, let down heat exchanger 2, high separation rate film 4 and degassing film 5, the hot side inlet duct of regenerative heat exchanger 1 are connected to principal series
The hot side outlet of system, regenerative heat exchanger 1 is successively connected with high separation rate film 4 and degassing film 5 by let down heat exchanger 2,
The outlet of degassing film 5 is connected by 1 cold side of regenerative heat exchanger with main system.
In the present embodiment, it is interconnected between let down heat exchanger 2 and high separation rate film 4 by lower discharging hole plate 3.
In the present embodiment, high separation rate film 4 is used to remove the radionuclide and impurity in reactor coolant；High score
Concentrated water side from rate film 4 is connected with liquid waste system.
In the present embodiment, 5 dissolved oxygen in removal reactor coolant of degassing film；The outlet of degassing film 5 passes through
On fill pump 6 and above fill to pump and 7 be connected with regenerative heat exchanger 1；The gas phase side of degassing film 5 is connected with vacuum pump.
The course of work without boron PWR nuclear power plant cvcs of the invention is as follows:
After reactor coolant comes out from main system, after regenerative heat exchanger 1, let down heat exchanger 2 are cooling, let out by down
Orifice plate 3 is depressurized to the unfavourable pressure of film work.
Reactor is no boron reactor core, and reactor coolant is that can be gone with radioactive demineralized water by high separation rate film 4
Except the nucleic and impurity in reactor coolant, the concentrated water side of high separation rate film 4 is nucleic and impurity concentrate, drains into waste liquid system
System；Reactor coolant by purification then enters degassing film 5 and carries out deoxygenation, and the gas phase side of degassing film 5 is taken out by vacuum pump
Vacuum.
Reactor coolant after deoxygenation fills pump 6 from above and above fills 7 pressurization of pump to be returned to after regenerative heat exchanger 1 heats up
Main system.
It is of the invention without the production for reducing radioactive solid waste in boron PWR nuclear power plant cvcs
The dose of radiation that personnel are subject in raw amount and replacement process avoids reducing danger source in nuclear island using hydrogen, simplifies personnel behaviour
Make.
The above shows and describes the basic principles and main features of the present invention and the advantages of the present invention.The technology of the industry
Personnel are it should be appreciated that the present invention is not limited to the above embodiments, and the above embodiments and description only describe this
The principle of invention, without departing from the spirit and scope of the present invention, various changes and improvements may be made to the invention, these changes
Change and improvement all fall within the protetion scope of the claimed invention, the claimed scope of the invention by appended claims and its
Equivalent thereof.
Claims (7)
1. a kind of no boron PWR nuclear power plant cvcs, which is characterized in that it include regenerative heat exchanger, under
Expel the heat-evil exchanger, lower discharging hole plate, high separation rate film, degassing film and on fill pump, the regenerative heat exchanger and let down heat exchanger
Reactor coolant is down to suitable temperature, then is successively connected with high separation rate film and degassing film, the outlet of the degassing film
It is connected by above filling pump and regenerative heat exchanger with main system.
2. as described in claim 1 without boron PWR nuclear power plant cvcs, which is characterized in that let out under described
It is interconnected between heat exchanger and the high separation rate film by lower discharging hole plate.
3. as described in claim 1 without boron PWR nuclear power plant cvcs, which is characterized in that the high score
It is used to remove the radionuclide and impurity in reactor coolant from rate film.
4. as described in claim 1 without boron PWR nuclear power plant cvcs, which is characterized in that the high score
Concentrated water side from rate film is connected with liquid waste system.
5. as described in claim 1 without boron PWR nuclear power plant cvcs, which is characterized in that the degassing
Film is used to remove the dissolved oxygen in reactor coolant.
6. as described in claim 1 without boron PWR nuclear power plant cvcs, which is characterized in that the degassing
The output end of film is connected by above filling pump with the regenerative heat exchanger.
7. as described in claim 1 without boron PWR nuclear power plant cvcs, which is characterized in that the degassing
The gas phase side of film is connected with vacuum pump.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201910611851.2A CN110265166A (en) | 2019-07-08 | 2019-07-08 | A kind of no boron PWR nuclear power plant cvcs |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201910611851.2A CN110265166A (en) | 2019-07-08 | 2019-07-08 | A kind of no boron PWR nuclear power plant cvcs |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN110265166A true CN110265166A (en) | 2019-09-20 |
Family
ID=67925041
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201910611851.2A Pending CN110265166A (en) | 2019-07-08 | 2019-07-08 | A kind of no boron PWR nuclear power plant cvcs |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN110265166A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN111180096A (en) * | 2020-02-21 | 2020-05-19 | 三门核电有限公司 | Physical deoxygenation method for primary circuit of pressurized water reactor nuclear power plant |
Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103405945A (en) * | 2013-07-31 | 2013-11-27 | 中科华核电技术研究院有限公司 | Degasser for removing dissolved gases in reactor coolant of nuclear power station, and method thereof |
| CN105551534A (en) * | 2015-11-13 | 2016-05-04 | 中国核动力研究设计院 | Reactor coolant chemical and volume control system and control method thereof |
| CN208225533U (en) * | 2018-05-09 | 2018-12-11 | 上海核工程研究设计院有限公司 | A kind of radioactive liquid waste removes the device of boron |
-
2019
- 2019-07-08 CN CN201910611851.2A patent/CN110265166A/en active Pending
Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103405945A (en) * | 2013-07-31 | 2013-11-27 | 中科华核电技术研究院有限公司 | Degasser for removing dissolved gases in reactor coolant of nuclear power station, and method thereof |
| CN105551534A (en) * | 2015-11-13 | 2016-05-04 | 中国核动力研究设计院 | Reactor coolant chemical and volume control system and control method thereof |
| CN208225533U (en) * | 2018-05-09 | 2018-12-11 | 上海核工程研究设计院有限公司 | A kind of radioactive liquid waste removes the device of boron |
Non-Patent Citations (5)
| Title |
|---|
| 宋均轲等: "放射性废水处理技术研究进展", 《能源环境保护》 * |
| 徐瑞引等: "核电站常规岛辅助给水系统安装膜除氧装置的可行性浅析", 《电站系统工程》 * |
| 李悦等: "第三代核电站与二代核电站的化学与容积控制系统的对比", 《科技资讯》 * |
| 王凤军等: "压水堆核电厂一回路水化学控制", 《硅谷》 * |
| 王志刚等: "主泵密封流量分配对化学和容积控制系统设计的影响分析", 《核动力工程》 * |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN111180096A (en) * | 2020-02-21 | 2020-05-19 | 三门核电有限公司 | Physical deoxygenation method for primary circuit of pressurized water reactor nuclear power plant |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN105023621B (en) | The implementation and its nuclear reactor of fast heap-type coupling nuclear reaction | |
| US5112569A (en) | Intrinsic-safety nuclear reactor of the pressurized water type | |
| CN107393605A (en) | The passive air-cooling apparatus and method of a kind of modular small nuclear reactor | |
| CN106229015B (en) | A kind of high-temperature molten salt pressure pipe and pipe tube type graphite high-temperature molten salt reactor | |
| CN105551534A (en) | Reactor coolant chemical and volume control system and control method thereof | |
| CN108417277A (en) | A reactor body system and a chlorine-salt reactor system | |
| CN107293341A (en) | Pool reactor | |
| CN109273112A (en) | A kind of direct cooling passive residual heat removal system of anti-gravity direction flowing | |
| CN204455305U (en) | A kind of containing tritium heavy water self-circulation electrolytic system | |
| CN114121313A (en) | Passive safety system of compact reactor | |
| CN110265166A (en) | A kind of no boron PWR nuclear power plant cvcs | |
| CN116364318A (en) | Sodium cooled reactor system | |
| CN106158052B (en) | Concentric spherical iris type spherical shape primary tank | |
| US3222255A (en) | Method of purifying primary fluid of nuclear reactor circuit | |
| CN205388908U (en) | Ordinary pressure heat transfer system of deep well formula reactor | |
| CN201838341U (en) | Radioactive water pollution purification device for one-mega kilowatt pressurized water reactor nuclear power station | |
| US3303098A (en) | Nuclear-power sea-water conversion plant | |
| CN205282105U (en) | Reactor coolant ization appearance control system | |
| CN216997789U (en) | Purification device for secondary water of nuclear power plant | |
| CN105575449A (en) | Deep-well normal-pressure nuclear heating system | |
| CN205541975U (en) | Deep well formula ordinary pressure nuclear heating system | |
| CN216623785U (en) | Passive safety system of compact reactor | |
| CN209401323U (en) | Million kilowatt nuclear power station Spent Fuel Pool cooling system | |
| CN104157319B (en) | Nuclear reactor primary coolant circuit coolant water quality cyclone purifying method and device | |
| CN116525154A (en) | Passive residual heat removal system of small lead-cooled ocean pool type natural circulation reactor and use method thereof |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| CB02 | Change of applicant information |
Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai Applicant after: Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd. Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai Applicant before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd. |
|
| CB02 | Change of applicant information | ||
| WD01 | Invention patent application deemed withdrawn after publication |
Application publication date: 20190920 |
|
| WD01 | Invention patent application deemed withdrawn after publication |