CN106887263A - The secondary laterally opened Heat Discharging System of Chinese of once through steam generator - Google Patents
The secondary laterally opened Heat Discharging System of Chinese of once through steam generator Download PDFInfo
- Publication number
- CN106887263A CN106887263A CN201510929795.9A CN201510929795A CN106887263A CN 106887263 A CN106887263 A CN 106887263A CN 201510929795 A CN201510929795 A CN 201510929795A CN 106887263 A CN106887263 A CN 106887263A
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- water
- steam generator
- steam
- once
- reactor
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Classifications
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- 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
-
- 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
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention belongs to reactor safety technical field, and in particular to a kind of secondary laterally opened Heat Discharging System of Chinese of once through steam generator.The system design has 2 series of redundancy, and each column is including auxiliary feed-water tank, sprinkler, to water screen；The cylinder section and upper cover of containment are immersed in shielding poind, and reactor is arranged in minimum elevation location in containment；Auxiliary feed-water tank is connected by supply line with the admission port of the once through steam generator for being built in reactor pressure vessel, it is provided with to water screen on supply line and in shielding poind, the steam (vapor) outlet of built-in steam generator is connected by steam pipework with the sprinkler being arranged in shielding poind.The present invention using the initial stage it is passive be directly injected into feedwater and later stage natural circulation mode feeds water two benches operational mode, persistently fed water to steam generator secondary side, reactor waste is transferred to shielding poind, it is in hgher efficiency to take waste heat out of, more reliable.
Description
Technical field
The invention belongs to reactor safety technical field, and in particular to a kind of once through steam generator secondary side is opened
Formula Heat Discharging System of Chinese.
Background technology
Residual heat removal system is the engineered safeguards features for tackling nuclear reactor designs basis accident and major accident,
Existing nuclear power reactor security system mostly uses active residual heat removal system and passive Residual heat removal system
System, system is mostly closed circulation system, and operation characteristic is complex, and reliability is low.To being steamed using direct current
For the modular reactor of vapour generator, because power is small, the economical efficiency of scale is lost, how designed both
Simple and reliable security system, is the common difficulty of global nuclear energy circle.Once through steam generator is secondary simultaneously
Side water loading amount is small, and pulsation among tubes and flow instability are run substantially in low-power area, occurs from direct-flow steam
The emergent exhaust thermal reliability of device secondary side is relatively difficult to resolve certainly.
The content of the invention
It is an object of the invention to provide a kind of secondary laterally opened passive residual heat removal system of once through steam generator
System, reactor waste is discharged with simplest system come reliable, is not required within 7 days after being capable of achieving design basis accident
Want Operator actions.
To reach above-mentioned purpose, the technical solution used in the present invention is：
A kind of secondary laterally opened Heat Discharging System of Chinese of once through steam generator, the system design has redundancy
2 series, each column include auxiliary feed-water tank, sprinkler, to water screen；The cylinder section of containment and on
End socket is immersed in shielding poind, and reactor is arranged in minimum elevation location in containment；Auxiliary feed-water tank leads to
Cross supply line to be connected with the admission port of the once through steam generator for being built in reactor pressure vessel, in feedwater
It is provided with pipeline and in shielding poind to water screen, the steam (vapor) outlet of built-in steam generator passes through steam pipe
Road is connected with the sprinkler being arranged in shielding poind.
Described auxiliary feed-water tank water loading amount is 200m3, shield water water loading amount is 3000m3。
In initial operating stage, by being compressed in auxiliary feed-water tank, nitrogen flooding is dynamic to be sent out system through supply line to direct-flow steam
Raw device secondary side feedwater, feedwater produces steam or gas-vapor mix to reach sprinkler through steam pipework after being heated
Mix with water into shielding poind after diffusion and condensed, so as to take reactor waste and sensible heat out of；In fortune
In the row later stage, after auxiliary feed-water tank feedwater exhausts, system is transferred to natural circulation mode, the water in shielding poind
The driving force provided by the temperature difference, potential difference enters once through steam generator secondary side through supply line, and feed water quilt
Produce steam or gas-vapor mix to be reached after sprinkler spreads through steam pipework after heating and enter shielding poind and pond
Water mixing is condensed, and continues to take away reactor waste and sensible heat；The reactor that shielding poind water is exported
Evaporated after waste heat and sensible heat heating, transfer heat to ultimate heat sink air；Shielding poind can be tieed up after moisturizing
Hold the long-term Residual heat removal of reactor.
Having the beneficial effect that acquired by the present invention：
The present invention is fed water and the feedwater two benches operation of later stage natural circulation mode using initial stage passive being directly injected into
Pattern, is persistently fed water to steam generator secondary side, and reactor waste is transferred into shielding poind, than tradition
The few circulation loop of secondary side enclosed Heat Discharging System of Chinese, it is in hgher efficiency to take waste heat out of, more may be used
Lean on.(1) DC characteristic that the present invention disposably passes through according to once through steam generator secondary side current, utilizes
Compressed nitrogen provides drive ram high and preferably solves the operation of once through steam generator low-power area pulsation among tubes and stream
Dynamic instability problem；(2) present invention makes full use of shielding poind flood loading amount, can be after Residual heat removal
Phase, using natural circulation mode, constantly provide feedwater to once through steam generator secondary side；(3) originally
Invention is removed and is applied to once through steam generator secondary side discharge reactor waste, it can also be used to Natural Circulation saturation
Formula steam generator secondary side discharges reactor waste.The present invention is 200~1000MW's suitable for thermal power
Integrated module formula reactor.
Brief description of the drawings
Fig. 1 is the secondary laterally opened Heat Discharging System of Chinese structure chart of once through steam generator of the present invention；
In figure：1st, shielding poind；2nd, auxiliary feed-water tank；3rd, sprinkler；4th, to water screen；5th, direct current
Steam generator；6th, reactor；7th, metal containment；8th, supply line；9th, steam pipework.
Specific embodiment
The present invention is described in detail with specific embodiment below in conjunction with the accompanying drawings.
As shown in figure 1, the secondary laterally opened Heat Discharging System of Chinese of once through steam generator of the present invention
2 series of redundancy are designed with, each column passes through including auxiliary feed-water tank 2, sprinkler 3, to water screen 4
The secondary side of once through steam generator 5 excludes the waste heat of reactor 6 to shielding poind 1.
The cylinder section and upper cover of containment 7 are immersed in shielding poind 1, and reactor 6 is arranged in containment 7
Interior minimum elevation location；Auxiliary feed-water tank 2 passes through supply line 8 and is built in the straight of reactor pressure vessel
The admission port connection of steam generator 5 is flowed, feedwater filter is provided with supply line 8 and in shielding poind 1
Net 4, the steam (vapor) outlet of built-in steam generator 5 passes through steam pipework 9 and the spray being arranged in shielding poind 1
Device 3 is spilt to connect.
The water loading amount of auxiliary feed-water tank 2 is about 200m3, the water loading amount of shielding poind 1 is about 3000m3, by steaming
Vapour generator secondary side excludes reactor waste to shielding poind 1, is capable of achieving 7 after power-off class design basis accident
It does not need Operator actions.The steam or carbonated drink that sprinkler 3 is responsible for producing steam generator secondary side are mixed
Compound spreads apart to be condensed after being sufficiently mixed so as to the water with shielding poind 1.It is main to water screen 4
Foreign matter that may be present enters steam generator blocking heat-transfer pipe in for intercepting shielding poind 1.
System is steamed through supply line 8 by compression nitrogen flooding is dynamic in auxiliary feed-water tank 2 in initial operating stage to direct current
The secondary side of vapour generator 5 feeds water, and feedwater produces steam or gas-vapor mix to be arrived through steam pipework 9 after being heated
Mix with water into shielding poind 1 after being spread up to sprinkler 3 and condensed, so as to take reactor more than 6 out of
Heat and sensible heat.
After operation the phase, after the feedwater of auxiliary feed-water tank 2 exhausts, system is transferred to natural circulation mode.Shield water
Water in pond 1 enters once through steam generator 5 by the driving force that the temperature difference, potential difference are provided through supply line 8
Secondary side, feedwater produces steam or gas-vapor mix to be spread through the arrival sprinkler 3 of steam pipework 9 after being heated
Mix with water into shielding poind 1 afterwards and condensed, continue to take away the waste heat of reactor 6 and sensible heat.
The reactor waste and sensible heat that the water of shielding poind 1 is exported evaporate after heating, and transfer heat to most
Whole hot trap-air.Shielding poind 1 can the long-term Residual heat removal of maintenance reaction heap after moisturizing.
Claims (3)
1. the secondary laterally opened Heat Discharging System of Chinese of a kind of once through steam generator, it is characterised in that：Should
System design has 2 series of redundancy, and each column includes auxiliary feed-water tank (2), sprinkler (3), feedwater filter
Net (4)；The cylinder section and upper cover of containment (7) are immersed in shielding poind (1), reactor (6)
It is arranged in minimum elevation location in containment (7)；Auxiliary feed-water tank (2) by supply line (8) with it is interior
The admission port connection of the once through steam generator (5) of reactor pressure vessel is placed in, in supply line (8)
It is provided with upper and shielding poind (1) and gives water screen (4), the steam (vapor) outlet of built-in steam generator (5)
It is connected with the sprinkler (3) being arranged in shielding poind (1) by steam pipework (9).
2. the secondary laterally opened Heat Discharging System of Chinese of once through steam generator according to claim 1,
It is characterized in that：Described auxiliary feed-water tank (2) water loading amount is 200m3, shielding poind (1) water loading amount is
3000m3。
3. the secondary laterally opened Heat Discharging System of Chinese of once through steam generator according to claim 1,
It is characterized in that：System is dynamic through supply line by compression nitrogen flooding in auxiliary feed-water tank (2) in initial operating stage
(8) fed water to once through steam generator (5) secondary side, feedwater produces steam or steam mixing after being heated
Thing is reached to mix with water into shielding poind (1) after sprinkler (3) spreads through steam pipework (9) and is able to
Condensation, so as to take reactor (6) waste heat and sensible heat out of；Phase after operation, auxiliary feed-water tank (2) feedwater
After exhausting, system is transferred to natural circulation mode, and the inner water of shielding poind (1) is provided by the temperature difference, potential difference
Driving force through supply line (8) enter once through steam generator (5) secondary side, feedwater be heated after produce
Raw steam or gas-vapor mix are reached after sprinkler (3) spreads through steam pipework (9) and enter shielding poind (1)
Mix with water and condensed, continue to take away reactor (6) waste heat and sensible heat；Shielding poind (1) water
Evaporated after reactor waste and the sensible heat heating being exported, transfer heat to ultimate heat sink air；Shield water
Pond (1) can the long-term Residual heat removal of maintenance reaction heap after moisturizing.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201510929795.9A CN106887263A (en) | 2015-12-15 | 2015-12-15 | The secondary laterally opened Heat Discharging System of Chinese of once through steam generator |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201510929795.9A CN106887263A (en) | 2015-12-15 | 2015-12-15 | The secondary laterally opened Heat Discharging System of Chinese of once through steam generator |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN106887263A true CN106887263A (en) | 2017-06-23 |
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201510929795.9A Pending CN106887263A (en) | 2015-12-15 | 2015-12-15 | The secondary laterally opened Heat Discharging System of Chinese of once through steam generator |
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| CN (1) | CN106887263A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107644693A (en) * | 2017-08-01 | 2018-01-30 | 中广核研究院有限公司 | Naval reactor and once through steam generator Passive residual heat removal system |
| CN109801722A (en) * | 2019-01-25 | 2019-05-24 | 中广核工程有限公司 | The heat transfer experiments method and system of nuclear power plant SEU system plate heat exchanger |
Citations (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN202549318U (en) * | 2012-02-29 | 2012-11-21 | 上海核工程研究设计院 | Residual heat removable system of nuclear reactor |
| CN202948739U (en) * | 2012-10-25 | 2013-05-22 | 中国核动力研究设计院 | Integrated pressurized water reactor coolant system |
| WO2013107790A1 (en) * | 2012-01-18 | 2013-07-25 | Societe Technique Pour L'energie Atomique Technicatome | System for discharging the residual power of a pressurised water nuclear reactor |
| CN103489488A (en) * | 2012-06-11 | 2014-01-01 | 中国核动力研究设计院 | Module type pressurized water reactor |
| CN103778976A (en) * | 2012-10-22 | 2014-05-07 | 中国核动力研究设计院 | Passive waste heat discharging system on secondary side of steam generator |
| CN104183284A (en) * | 2013-05-22 | 2014-12-03 | 中国核电工程有限公司 | ''Passive forced circulation'' heat exporting system |
| CN204242602U (en) * | 2014-11-19 | 2015-04-01 | 中科华核电技术研究院有限公司 | Secondary side passive residual heat guiding system |
| CN205354672U (en) * | 2015-12-15 | 2016-06-29 | 中国核动力研究设计院 | Active residual heat removal system of open non - of direct current steam generator secondary side |
-
2015
- 2015-12-15 CN CN201510929795.9A patent/CN106887263A/en active Pending
Patent Citations (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2013107790A1 (en) * | 2012-01-18 | 2013-07-25 | Societe Technique Pour L'energie Atomique Technicatome | System for discharging the residual power of a pressurised water nuclear reactor |
| CN202549318U (en) * | 2012-02-29 | 2012-11-21 | 上海核工程研究设计院 | Residual heat removable system of nuclear reactor |
| CN103489488A (en) * | 2012-06-11 | 2014-01-01 | 中国核动力研究设计院 | Module type pressurized water reactor |
| CN103778976A (en) * | 2012-10-22 | 2014-05-07 | 中国核动力研究设计院 | Passive waste heat discharging system on secondary side of steam generator |
| CN202948739U (en) * | 2012-10-25 | 2013-05-22 | 中国核动力研究设计院 | Integrated pressurized water reactor coolant system |
| CN104183284A (en) * | 2013-05-22 | 2014-12-03 | 中国核电工程有限公司 | ''Passive forced circulation'' heat exporting system |
| CN204242602U (en) * | 2014-11-19 | 2015-04-01 | 中科华核电技术研究院有限公司 | Secondary side passive residual heat guiding system |
| CN205354672U (en) * | 2015-12-15 | 2016-06-29 | 中国核动力研究设计院 | Active residual heat removal system of open non - of direct current steam generator secondary side |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107644693A (en) * | 2017-08-01 | 2018-01-30 | 中广核研究院有限公司 | Naval reactor and once through steam generator Passive residual heat removal system |
| CN109801722A (en) * | 2019-01-25 | 2019-05-24 | 中广核工程有限公司 | The heat transfer experiments method and system of nuclear power plant SEU system plate heat exchanger |
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| SE01 | Entry into force of request for substantive examination | ||
| RJ01 | Rejection of invention patent application after publication |
Application publication date: 20170623 |
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| RJ01 | Rejection of invention patent application after publication |