CN205789133U - A kind of passive nuclear power station secondary buck system - Google Patents
A kind of passive nuclear power station secondary buck system Download PDFInfo
- Publication number
- CN205789133U CN205789133U CN201620259332.6U CN201620259332U CN205789133U CN 205789133 U CN205789133 U CN 205789133U CN 201620259332 U CN201620259332 U CN 201620259332U CN 205789133 U CN205789133 U CN 205789133U
- Authority
- CN
- China
- Prior art keywords
- valve
- pressure
- nuclear power
- power station
- passive
- 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.)
- Expired - Fee Related
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
- 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
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
A kind of passive nuclear power station secondary buck system, it includes the independent discharge of steam pipeline being arranged on the cover head of reactor pressure vessel, discharge pipe line is in series with isolating valve and pressure relief valve, described isolating valve is for keeping zero leakage under normal operation and fully opening under emergency conditions, and the release pressure of described pressure relief valve is adjusted to the water level pressure head value of the built-in material-changing water tank of containment.
Description
Technical field
This utility model relates to a kind of secondary buck system, in particular to a kind of passive nuclear power station secondary buck system
System.
Background technology
The nuclear power of safety is the clean energy resource of a kind of high-energy source density, to preserving the ecological environment, readjust the energy structure and protecting
Barrier energy security has important effect.But once there is safety problem in nuclear power station, then can to staff, nearby residents and
Ecological environment brings huge threat.For this nuclear plant safety problem be people apply nuclear power time must the problem that considers of emphasis.
Nuclear power station tends to use non-passive safety technical finesse accident at present.So-called non-passive safety technology refers in the feelings that have an accident
Utilizing natural agent to complete various refrigerating function under condition, wherein natural agent can be produced by gravity, pressure accumulation gas pressure, Natural Circulation
Driving forces etc. produce, it is not necessary to pump and external power source.Therefore, it is greatly simplified while improve the security reliability of nuclear power station
The security system of nuclear power station.
Existing nuclear power station includes primary heat transport system and the reactor core emergency cooling system communicated therewith, reactor
The reactor that core emergency cooling system produces for taking away reactor core remnants in primary heat transport system to fission when having an accident
Residual heat of nuclear core.
In the case of nuclear power station generation minor break accident, the cooling water in primary heat transport system from minor break in containment
Spurting, the pressure in reactor pressure vessel declines, and the cooling water in primary heat transport system reduces, and causes the water level in manostat to drop
Low, reactor shutdown safety signal, reactor core stopped reaction will be triggered, main pump is shut down, the main steaming of steam generator outlet
Main steam isolation valve on steam pipe line is closed.Owing to main steam isolation valve is closed, the saturation water in the secondary side of steam generator
The steam that evaporation produces cannot flow to steam turbine, and the secondary side of steam generator cannot utilize normal operation mode to take away instead
Answer heap reactor core remnants fission produce reactor core waste heat.
Along with the development of accident process, due to minor break and the input of reactor core emergency cooling system, major loop system
Temperature and pressure in system constantly declines, thus steam generator secondary side is become thermal source from hot trap originally, on the contrary to leading back
Road system release heat, this cooling being obviously unfavorable for primary heat transport system and blood pressure lowering.Fig. 4 shows and sends out cold section of primary heat transport system
In the case of raw about 5cm minor break accident, the pressure in primary heat transport system and two steam generator secondary side is sent out at cut
Time history plot after life.In Fig. 4, solid line is primary heat transport system pressure, and dotted line is two steam generators two respectively
The pressure of secondary side.As seen in Figure 4, initial primary heat transport system pressure P0Higher than the pressure in steam generator secondary side,
But it is as the closedown of main steam isolation valve 13 under emergency conditions, by the Natural Circulation of primary heat transport system, partial reaction heap heap
Core waste heat passes to the saturated cooling water in steam generator secondary side, and saturated cooling water evaporation makes steam generator secondary side
Interior pressure raises.As shown in Figure 4, primary heat transport system is made due to the input of minor break and reactor core emergency cooling system
Temperature and pressure gradually reduce, the pressure in steam generator secondary side will be above the pressure of primary heat transport system.Accordingly, steam
The temperature of the heat transferring medium in vapour generator secondary side will be above the temperature of heat transferring medium in primary heat transport system, and U-tube is due to complete
Entirely it is placed in steam generator secondary side space, superheated steam therefore will be caused at U-tube accumulated inside, be no longer participate in major loop
Cooling circulation, this is unfavorable for primary heat transport system cooling and blood pressure lowering.
Accordingly, it is desirable to provide a kind of passive nuclear power station secondary buck system, it is effectively improved primary heat transport system cooling and fall
Pressure, it is ensured that primary heat transport system obtains moisturizing and sufficiently cool in time, reduces or eliminates reactor core cooling down risk, contribute to
Improve nuclear power station and resist the ability of minor break accident.
Utility model content
The purpose of this utility model is to provide a kind of novel secondary buck system, needs to compensate in passive nuclear power station
Or when strengthening blood pressure lowering ability, under the conditions of making full use of passive nuclear power plant accident, vapours is assembled in system or equipment eminence
Characteristic, utilizes secondary buck system, discharge or condensation heat steam, reaches the most effectively to reduce the purpose of system pressure, in order to weight
Power-actuated safety injection system (IRWST gravity safety injection) can start smoothly, it is ensured that system obtains moisturizing and sufficiently cool in time, disappears
Except Core uncovering risk, for improving the ability of nuclear power station reply beyond design basis accident, promote security of system allowance, towards not
Carry out more power heap-type technological development and all there is beneficial effect.
According to preferred embodiment of the present utility model, it is proposed that a kind of secondary buck system for passive nuclear power station,
It is characterized in that, it includes the independent discharge of steam pipeline being arranged on the cover head of reactor pressure vessel, at discharge pipe line
On be in series with isolating valve and pressure relief valve, described isolating valve is for keeping zero leakage and at emergency conditions under normal operation
Under fully open, the release pressure of described pressure relief valve is adjusted to the water level pressure head value of the built-in material-changing water tank of containment.
According to preferred embodiment of the present utility model, described isolating valve is explosion valve.
According to preferred embodiment of the present utility model, when system generation cut passive system order puts into, receive the 4th
Level Automatic Depressurization System valve confirms to open signal, after time delay in 40 seconds, starts secondary buck system, wherein by discharge pipe line
On isolating valve open, if system pressure is not also reduced to the water level pressure head value of the built-in material-changing water tank of containment, then pressure release
Valve is opened, and is discharged by vapours, aid system blood pressure lowering, reduces the water level pressure to the built-in material-changing water tank of containment at system pressure
Below header value, containment built-in material-changing water tank peace note starts, and pressure relief valve closes, and secondary buck quits work.
According to preferred embodiment of the present utility model, it is proposed that a kind of secondary buck system for passive nuclear power station,
It is characterized in that, it includes the independent discharge of steam pipeline being arranged on the cover head of reactor pressure vessel, at discharge pipe line
On be in series with spray thrower, isolating valve and elevated tank, described elevated tank connects with the pressure-equalizing line of Core makeup tank, institute
State isolating valve for keeping zero leakage under normal operation and fully opening under emergency conditions.
According to preferred embodiment of the present utility model, described spray thrower is the spray thrower of falling J-type.
According to preferred embodiment of the present utility model, when system generation cut passive system order puts into, receive the 4th
Level Automatic Depressurization System valve confirms to open signal, after time delay in 40 seconds, starts secondary buck system, wherein by discharge pipe line
On isolating valve open, connect pipeline by elevated tank and upper cover carried out cools down water inject.
According to preferred embodiment of the present utility model, according to steam latent heat value, steam and cooling water density, enter according to the following formula
The estimation of row cooling water injection rate:, wherein, m is required cooling water inflow, and V is upper cover volume,For steaming
Vapour density,For latent heat enthalpy,For injecting the supercool enthalpy of cooling water.
According to preferred embodiment of the present utility model, it is proposed that a kind of secondary buck system for passive nuclear power station,
It is characterized in that, it includes the sprinkler being arranged in the integrated cover head device of reactor pressure vessel, described sprinkler
Spraying allotter including one or more groups, sprinkler is connected to isolating valve, and described isolating valve is for keeping zero under normal operation
Leaking and fully open under emergency conditions, isolating valve is connected to water source, and described integration cover head device includes bottom
Air inlet and the air outlet at top, it utilizes air inlet and air outlet to be taken out of by the steam spraying evaporation generation.
According to preferred embodiment of the present utility model, described water source is elevated tank, the water source being separately provided, or existing
The built-in material-changing water tank of containment.
According to preferred embodiment of the present utility model, when system generation cut passive system order puts into, receive the 4th
Level Automatic Depressurization System valve confirms to open signal, after time delay in 40 seconds, starts secondary buck system, wherein by discharge pipe line
On isolating valve open, when the built-in material-changing water tank of containment inject start, ascending pipe linear flow rate > 500t/h time, close isolating valve.
Accompanying drawing explanation
Above and other aspect of the present utility model is discussed in detail, in accompanying drawing below in conjunction with accompanying drawing:
Fig. 1 shows the primary heat transport system of passive nuclear power station.
Fig. 2 is the schematic diagram of passive nuclear power station reactor core emergency cooling system.
Fig. 3 is the signal that the melt pit of passive nuclear power station reactor core emergency cooling system cools down cyclic process for a long time
Figure.
Fig. 4 shows the pressure in the case of minor break accident in primary heat transport system and two steam generator secondary side
Time history plot after cut occurs.
Fig. 5 is in 2 inches of minor break accident transient processes of ACME test-bed, the mixing liquid level in reactor pressure vessel
Highly change over curve.
Fig. 6 is in 2 inches of minor break accident transient processes of ACME test-bed, in the upper cover in reactor pressure vessel
Portion's temperature changes over curve.
Fig. 7 is the structural representation of the spray thrower of falling J-type.
Fig. 8 shows the embodiment according to passive nuclear power station secondary buck system of the present utility model.
Fig. 9 shows another embodiment according to passive nuclear power station secondary buck system of the present utility model.
Figure 10 shows another embodiment according to passive nuclear power station secondary buck system of the present utility model.
Attached body tag list
| 1 | Reactor core |
| 2 | Reactor pressure vessel |
| 3 | Cold section of primary heat transport system |
| 4 | Primary heat transport system hot arc |
| 5 | U-tube |
| 6 | Steam generator |
| 7 | Steam generator cold chamber compartment |
| 8 | Steam generator hot chamber compartment |
| 9 | Main pump |
| 10 | Surge line piping |
| 11 | Manostat |
| 12 | Main steam pipe |
| 13 | Main steam isolation valve |
| 14 | Passive residual heat removal heat exchanger |
| 15 | First water supply tank |
| 16 | Second water supply tank |
| 17 | Main water supply tank |
| 18 | Direct safety injection pipe |
| 19 | Pressure-equalizing line |
| 20 | The automatic dropping valve of the first order |
| 21 | The automatic dropping valve in the second level |
| 22 | The automatic dropping valve of the third level |
| 23 | Main automatic dropping valve |
| 24 | Melt pit filter screen |
| 51-53 | Check valve |
| 54-55 | Explosive valve |
| 56 | Stop valve |
| 60 | Bubbler |
| 65 | Steam generator secondary side relief valve |
| 66 | Steam generator shell heat exchanger |
| 67 | Heat-exchanging loop pipeline |
| 68 | Shell external heat exchanger |
| 69 | Isolating valve |
| 70 | Pressure maintaining valve |
| 100 | First connecting line |
| 102 | Second connecting line |
| 104 | 3rd connecting line |
| 105 | Melt pit |
| 106 | Melt pit reflux pipe |
Detailed description of the invention
Following description describes optional embodiment of the present utility model with reference to the accompanying drawings to instruct ordinary skill people
How member implements and reproduces this utility model.In order to instruct technical solutions of the utility model, simplify or eliminated some routines
Aspect.It should be understood by one skilled in the art that and be derived from the modification of these embodiments or replace will fall of the present utility model
In protection domain.It should be understood by one skilled in the art that following characteristics can combine to form this practicality in every way new
Multiple modification of type.Thus, this utility model is not limited to following optional embodiment, and only by claim and they
Equivalent limits.
Coolant can be such as cooling water in this article.Being suitable in nuclear power plant system use of refrigerating function can be realized
Other coolants also in the range of this utility model.In the art, general large break refers to that Break size is more than or equal to
10 square feet, minor break refers to that Break size is less than the cut of 10 square feet.
Fig. 1 shows the primary heat transport system of passive nuclear power station.As it is shown in figure 1, the major loop of current passive nuclear power station
System includes that steam generator 6, U-tube 5, primary heat transport system cold section 3, primary heat transport system hot arc 4, main pump 9, reactor pressure hold
Device 2, being positioned at the reactor core 1 of reactor pressure vessel 2, Surge line piping 10 and manostat 11, wherein U-tube 5 is arranged on steaming
In vapour generator 6, the U-tube port of export is pooled to the cold chamber compartment 7 of steam generator bottom, and cold chamber compartment 7 is by main pump 9
Connecting for cold with primary heat transport system section 3, primary heat transport system connects with reactor pressure vessel 2 for cold section 3, and reactor pressure vessel 2 is also
Connecting with primary heat transport system hot arc 4, primary heat transport system hot arc 4 is connected with manostat 11 by Surge line piping 10 and is passed through steam generation
Hot chamber compartment 8 bottom device connects with the arrival end of U-tube 5, and coolant enters reactor pressure for cold section 3 by primary heat transport system
Force container 2, arrives the entrance of reactor core 1, takes away the nuclear reaction energy that reactor core produces when flowing through reactor core 1
Amount, heated coolant (such as temperature is of about 321 DEG C) flows through primary heat transport system hot arc 4, arrives steam generator bottom
Hot chamber compartment 8 and enter the arrival end of U-tube 5, in transferring heat to steam generator 6 by U-tube 5 and U-tube 5
Outer coolant, the coolant temperature in U-tube 5 reduces (such as coolant temperature is 280 DEG C) and by the port of export of U-tube
Collecting in steam generator bottom cold chamber compartment 7, in cold chamber compartment, the coolant of 7 pumps into primary heat transport system by main pump 9
Cold section 3, turn again to reactor pressure vessel 2, form the enclosed cooling circulation of primary heat transport system.In Fig. 1, arrow F1 is temperature
Relatively low coolant flows to, and arrow F2 is that the coolant that temperature is higher flows to.
For the pressure of stable primary heat transport system, primary heat transport system hot arc 4 is connected with manostat 11, surely by Surge line piping 10
It is saturated solution and saturated vapor (for example, cooling water saturation liquid and saturated vapor) in depressor 11, meets the steady of primary heat transport system
Pressure request.Manostat 11 is used for maintaining the pressure of primary heat transport system properly functioning high pressure conditions (such as about 15.5MPa),
During making reactor core 1 reaction in normal operation, the coolant in reactor pressure vessel 2 does not haves boiling
Rise.The cooling water of reacted heap reactor core 1 heating is when flowing through U-tube 5, in transferring heat to steam generator 6 and U-tube 5
Outer cooling water so that the cooling water evaporation in steam generator 6 forms steam, and in steam generator 6, steam passes through main steam
Pipeline 12, is fed to steam turbine (not shown in figure 1) by normally opened main steam isolation valve 13, drives steam turbine to send out
Electricity, thus the heat that reactor core produces is changed into electric energy.
Fig. 2 is the schematic diagram of passive nuclear power station reactor core emergency cooling system.Wherein, chilling answered by reactor core
But system includes that the first single storage of water supply tank 15(has the cooling water of about 70 tons), the second single storage of water supply tank 16(has greatly
The cooling water of about 57 tons and the gas of about 5MPa), main water supply tank 17(storage have the water of about 2100 tons), be positioned at main water supply tank
Passive residual heat removal heat exchanger 14 in 17 and bubbler 60, level Four Automatic Depressurization System, melt pit 105, melt pit filter screen 24,
Melt pit reflux pipe 106 and the explosive valve 55 being arranged on melt pit reflux pipe.First water supply tank the 15, second water supply tank 16,
Main water supply tank 17 passes through first connecting line the 100, second connecting line the 102, the 3rd connecting line 104 respectively and is arranged on each
Check valve 51-53 on individual connecting line and being connected with reactor pressure vessel 2 by direct reaction heap peace note pipe 18, Qi Zhong
One connecting line 100 can be provided with stop valve 56, and the 3rd connecting line 104 can be provided with explosive valve 54, stop valve 56 He
Explosive valve 54 is all used for preventing the improper injection of water tank inner cooling water.First water supply tank top by pressure-equalizing line 19 with
Cold section 3 connection of primary heat transport system, so that the pressure in the first water supply tank 15 keeps consistent with the pressure of primary heat transport system, four
Level Automatic Depressurization System include the automatic dropping valve of the first order 20, the automatic dropping valve in the second level 21, the automatic dropping valve of the third level 22 with
And main automatic dropping valve 23, the automatic dropping valve of the first order 20, the automatic dropping valve in the second level 21, the entering of the automatic dropping valve of the third level 22
Mouth end is connected on manostat 11 with parallel way and by automatic for first order dropping valve 20, the automatic dropping valve in the second level the 21, the 3rd
The port of export of level dropping valve 22 automatically is connected to be positioned on the bubbler 60 in main water supply tank 17 with parallel way, main fall automatically
Pressure valve 23 connects with primary heat transport system hot arc 4, and passive residual heat removal heat exchanger 14 is not shown with cold section of 3(of primary heat transport system)
Connect with primary heat transport system hot arc 4, rely on coolant density difference in passive residual heat removal heat exchanger 14 and primary heat transport system
Natural Circulation is established between cold section 3 and primary heat transport system hot arc 4.Reactor pressure vessel 2 is arranged in melt pit 105, melt pit
Cooling water in 105 by melt pit reflux pipe 106, melt pit filter screen 24 and the explosive valve 55 being arranged in melt pit reflux pipe and
Connected with reactor pressure vessel 2 by direct safety injection pipe 18.
Fig. 3 is the signal that the melt pit of passive nuclear power station reactor core emergency cooling system cools down cyclic process for a long time
Figure.Melt pit filter screen 24, melt pit reflux pipeline is passed through under the effect of the driving force that the cooling water collected in melt pit is formed at density contrast
106 and the explosive valve 55 piii reactor pressure vessel 2 that is arranged on melt pit reflux pipeline in, thermogenetic more than reactor core
Steam is emitted in containment through main automatic dropping valve 23, and the steam established in Natural Circulation, and containment passes through safety
Shell cooling system cools down, and condensed water, at containment internal reflux to melt pit, supplements cooling water to melt pit.By such circulation
Reactor core waste heat is passed to the ambient atmosphere outside the containment of ultimate heat sink by mode, keeps reactor core to continue
Cooling, prevents reactor core overtemperature from melting and developing even more serious accident.
Above by reference to Fig. 1-3, passive nuclear power station is briefly described.It should be noted that active nuclear power station is similar to
Ground also includes primary heat transport system and the reactor core emergency cooling system communicated therewith, and this is to those skilled in the art
It is known, is not described in detail herein.
In the case of nuclear power station generation minor break accident, the cooling water in primary heat transport system (as shown in Figure 1) is from little broken
Mouth spurts in containment, and the pressure in reactor pressure vessel 2 declines, and the cooling water in primary heat transport system reduces, and causes steady
Water level in depressor 11 reduces, and will trigger reactor shutdown safety signal, reactor core 1 stopped reaction, and main pump 9 is shut down, and steams
Main steam isolation valve 13 on the main steam pipe 12 of vapour generator 6 outlet is closed.Owing to main steam isolation valve 13 is closed, steam
The steam that saturation water evaporation in the secondary side (space in steam generator 6 and outside U-tube 5) of generator produces cannot carry
To steam turbine (not shown in figure 1), the secondary side of steam generator cannot utilize normal operation mode to take away reactor core
The reactor core waste heat that remaining fission produces.
Therefore this utility model provides a kind of novel secondary buck system.Passive nuclear power station needs compensate or
When strengthening blood pressure lowering ability, make full use of the spy that vapours under the conditions of passive nuclear power plant accident is assembled in system or equipment eminence
Property, utilize secondary buck system, discharge or condensation heat steam, reach the most effectively to reduce the purpose of system pressure, in order to gravity
The safety injection system (IRWST gravity safety injection) driven can start smoothly, it is ensured that system obtains moisturizing and sufficiently cool in time, eliminates
Core uncovering risk.
Of the present utility model passive nuclear power station secondary buck system is described in detail below.
As secondary buck system, only start when needs enhancing system blood pressure lowering ability, do not come into operation under the conditions of other.
For the built-in material-changing water tank of IRWST(containment) pacify the spy being identified as passive nuclear plant safety the most dangerous period before note starts
Property, logic judgement mode can be used to recognize the need for start secondary buck system.A kind of simple control mode, be
After Automatic Depressurization System (such as fourth stage Automatic Depressurization System, ADS4) opens confirmation signal generation, open this secondary buck system,
Aid system carries out blood pressure lowering.Primary heat transport system pressure is made quickly to be down to the pressure that gravity safety injection can put into so that gravity safety
Note puts into smoothly, it is ensured that reactor core persistently cools down, and reduces the risk of Core uncovering, improves the safety allowance of nuclear power station.Naturally drive
The introducing of power, while being greatly improved emergence core stacking cool system reliability, owing to its driving force is relatively small, therefore, to assure that
Under the conditions of little driving force, cooling water equally can piii reactor reactor core smoothly.Mainly setting of passive core cooling system
Meter feature is to be equipped with outside a set of peace started under high, normal, basic pressure rating respectively note subsystem, the most supporting a set of
By the first order to third level Automatic Depressurization System ADS1-3 and ADS4 form totally 4 grades Automatic Depressurization System with realize system by
Walk controlled blood pressure lowering, so that safety injection system can start cooling water function of injecting.Wherein ADS1-3 is from manostat Base top contact, tool
Having two row parallel pipelines, every string parallel pipeline is made up of three grades of pressure relief pipes arranged side by side again, every string becomes depressurizing system
One-level.These three grades of depressurizing systems of ADS1-3 are the Automatic Depressurization System under high pressure, generally by higher from more than 10MPa of system
Pressure, controlled is down to below 1MPa.And ADS4 directly draws from the two of major loop heat pipes, totally two row, each column ADS4 has again
The pressure relief pipe composition that two row are in parallel.ADS4 is the Automatic Depressurization System under low pressure, generally by system by 1MPa pressure below
Release to close to ambient pressure in containment, so that relying on the IRWST safety injection system of weight-driven to start.
By the integrality test (ACME test) of theory analysis, numerical simulation and large-scale passive nuclear power station, find
After minor break accident occurs, owing to vapour density is far smaller than liquid, have considerable amount of superheated steam and be gathered in major loop
Regional area higher relative to position in system or equipment, the most topmost for inverted U pipe with reactor pressure vessel (RPV)
Upper cover.Fig. 5 is that in ACME test-bed 2inch minor break accident transient process, the mixing liquid level in RPV becomes in time
Changing curve, wherein transverse axis is time (unit: second)；The longitudinal axis is mixing liquid level (unit: millimeter), and the dotted line in Fig. 5 represents
The height of upper cover, curve represents mixed liquor position height.Mixing liquid level in RPV is significantly lower than upper cover as can be seen from the results
Region, mixing liquid level is the physical interface that phase separates, and the region more than mixing liquid level is steam dome, therefore upper cover district
Territory is the region that steam occupies.Fig. 6 is in ACME test-bed 2inch minor break accident transient process, in the upper cover in RPV
Portion's temperature changes over curve, and wherein transverse axis is time (unit: second)；The longitudinal axis is upper cover internal temperature (unit: Celsius
Degree), test understand the temperature in upper cover region higher than the saturation temperature under system corresponding pressure.Result in conjunction with Fig. 5 and 6
It can be seen that the upper cover region at RPV top is always region occupied by superheated steam substantially, show upper cover under emergency conditions
There is considerable amount of superheated steam.This point characteristic is low with vapour phase density and the system that is therefore gathered in is relative to high point locations/regions
It is consistent with.If it is possible to make full use of superheated steam to be gathered in this characteristic of system or equipment high point, to such
Discharge of steam or the method condensed are taked in specific region, can be effectively accomplished reduction system pressure, be easy to IRWST weight
Power injects the purpose started.
According to preferred embodiment of the present utility model, vapours method for releasing can be used to carry out secondary buck.Wherein, increase certainly
Dynamic depressurizing system progression, or increase and release pipeline with the parallel connection of level system, it is the most directly to improve depressurizing system ability
Approach.But the problem of the method most critical be pressure relief system itself operate in by system mass-energy release reduction system
While system pressure, intrasystem coolant also there will be certain forfeiture, and solving this to the method for contradiction is by pressure relief system
Promote absolute altitude, while pressure of releasing, reduce the loss of liquid coolant.But if able to it is specifically designed for what steam was assembled
Region carries out steam pressure release, can reach to discharge the effect of pressure, can significantly eliminate again the loss of liquid.Therefore, auxiliary
One of method of blood pressure lowering can be in the way of employing sets up secondary buck branch road for RPV upper cover.
According to preferred embodiment of the present utility model, it would however also be possible to employ internal direct condensation carrys out secondary buck.Do not examining
Consider under conditions of superheated steam is removed beyond system, these intrasystem superheated steams are condensed, due to its volume
Huge contraction, system pressure will be decreased obviously, original coolant in simultaneously not losing system, also be a kind of effective blood pressure lowering
Mode.Use the mode of directly spray in the region that RPV upper cover superheated steam is assembled, can obtain very with the least spray flux
Big condensation number, this direct condensation by contact is the most quick condensation method, and pressure drop reduces rapidly, but easily causes water hammer
Problem, it is therefore desirable to control condensing rate, it is impossible to too fast, therefore spray needs to consider special trickle structure, the such as spray of falling J-type
Device, as shown in Figure 7.
According to preferred embodiment of the present utility model, it would however also be possible to employ external heat-exchanging condensation method carrys out secondary buck.Except directly
It is connected on inside and carries out outside spray condensation, it is possible to use the mode of upper cover metal wall heat conduction, indirectly internal vapours is carried out
Heat exchange condenses.By RPV upper cover outer surface is cooled down, by increasing capacitance it is possible to increase internal vapours passes to pressure vessel cover head
The total amount of heat in metal inner surface face, indirect condensing over-heat inside steam by the way of upper cover outside derivation heat.Outside end socket
Heat is derived mode and can be taked style head plate equipment directly carries out spray condensation, maintains upper cover metal temperature less than system pressure pair
The saturation temperature answered.
According to preferred embodiment of the present utility model, secondary buck system can use enabling fashion, it is possible to uses non-energy
Dynamic working method.On selection technique route, such as passive nuclear power station, for keeping the non-energy of passive nuclear power station design
The core design theory of dynamic safety, design will consider according to passive type of drive.The same driving force used is attached most importance to
The natural agent such as power, compression pressure.
Fig. 8 shows the embodiment according to passive nuclear power station secondary buck system of the present utility model.As shown in Figure 8,
Individually set up a discharge of steam pipeline at RPV cover head, pipeline is in series with isolating valve and pressure relief valve.Isolating valve is used for
Keep properly functioning under zero leakage and emergency conditions under fully open, preferably by explosion valve.Pressure relief valve
Release pressure is adjusted to IRWST water level pressure head value.
When system generation cut, after passive system order puts into, ADS4 starts and receives ADS4 valve confirmation unlatching letter
Number, and (such as through time delay 40 seconds, this numerical value can evaporate according to the reactor core liquid that heap power level is corresponding after certain time-delay
Amount calculates), start secondary buck system.Explosion valve opening on discharge pipe line, now, if system pressure does not also reduce
To IRWST hydraulic pressure head pressure, then pressure relief valve opens, and is discharged by vapours, and aid system blood pressure lowering, at system pressure drop
Low below IRWST water level pressure head value, after IRWST peace note starts, pressure relief valve closes, and secondary buck quits work.
Fig. 9 shows another embodiment according to passive nuclear power station secondary buck system of the present utility model.Such as Fig. 9
Shown in, individually set up a discharge of steam pipeline at RPV cover head, pipeline be in series with spray thrower, isolating valve and elevated tank,
Use the mode that the vapours assembled in RPV upper cover is carried out direct condensation by contact.Isolating valve be used for keeping properly functioning under
Zero leakage and emergency conditions under fully open, preferably by explosion valve.In order to can thermotropism after ensureing valve opening
Steam dome trickle, the other end of water tank and CMT(Core makeup tank) PBL(pressure-equalizing line) connect, keep tank pressure
Equal with system pressure, merely with the relative high potential difference of water tank as driving force.Further, since directly the condensing rate of contact is non-
The fastest, easily induce water hammer, therefore to prevent the structure of water hammer in discharge outlet increase, such as the spray thrower of falling J-type (Fig. 7), control to connect
Touch the speed of condensation.
When system generation cut, after passive system order puts into, ADS4 starts and receives ADS4 valve confirmation unlatching letter
Number, and (such as through time delay 40 seconds, this numerical value can evaporate according to the reactor core liquid that heap power level is corresponding after certain time-delay
Amount calculates), start secondary buck system.Thus, when system needs secondary buck, open the isolating valve on pipeline, logical
Crossing high-order water tank connecting pipe line to carry out upper cover cooling down water injection, cause the vapours condensation assembled, the system that reaches drops rapidly
The purpose of pressure.
Owing to direct condensation by contact amount is very big, therefore the required cooling water inflow injected is little.Water tank volume is corresponding the least.
According to steam latent heat value, steam and cooling water density, carry out cooling down the estimation of water injection rate according to the following formula:
Wherein, m is required cooling water inflow, and V is upper cover volume,For vapour density,For latent heat enthalpy,For
Inject the supercool enthalpy of cooling water.
Figure 10 shows another embodiment according to passive nuclear power station secondary buck system of the present utility model.Such as figure
Shown in 10, in the integrated cover head device of RPV, set up the outside spraying cooling of RPV end socket, reached by heat transfer mode
The effect of RPV over-heat inside steam condensation.
As shown in Figure 10, sprinkler is arranged in the integrated cover head of RPV, arranges one or more groups and sprays allotter.
Sprinkler is connected to isolating valve, this isolating valve for keep properly functioning under zero leakage and emergency conditions under fully open,
Preferably by explosion valve.Can be connected to provide it water source with elevated tank afterwards.Wherein, the water of secondary buck system
Source can come from elevated tank, can be separately provided, it would however also be possible to employ existing IRWST.When receiving secondary buck system start-up
During signal, open the isolating valve on pipeline, upper cover is carried out cooling and sprays.Meanwhile, utilize integration cover head chiller,
This integration cover head chiller includes air inlet and the air outlet at top of bottom, and it utilizes air inlet and air outlet to spray
The steam spilling evaporation generation is taken out of.The internal vapours heat of RPV progressively removes, and system pressure gradually reduces, and reaches secondary buck
Purpose.
When system generation cut, after passive system order puts into, ADS4 starts and receives ADS4 valve confirmation unlatching letter
Number, and (such as through time delay 40 seconds, this numerical value can evaporate according to the reactor core liquid that heap power level is corresponding after certain time-delay
Amount calculates), start secondary buck system.Start when IRWST injects, ascending pipe linear flow rate this numerical value of 500t/h(can basis
Power station specific design and safety analysis result are adjusted) flow time, secondary buck system close, close spray pipeline isolation
Valve.Now, system only relies on the lasting peace note of original ADS depressurizing system and IRWST and just can keep reactor core moisturizing and cooling.
This utility model is had been described in detail with reference to particular embodiments, it is clear that without departing from claims
Defined in this utility model scope in the case of, can be modified and change.Although it is more specifically, of the present utility model
Some aspects are identified herein as preferred or favourable, but this utility model should not necessarily be limited by of the present utility model
These preferred embodiments.
Claims (10)
1. a passive nuclear power station secondary buck system, it is characterised in that it top including being arranged on reactor pressure vessel
Independent discharge of steam pipeline on end socket, is in series with isolating valve and pressure relief valve on discharge pipe line, and described isolating valve is used for
Keeping zero leakage under normal operation and fully open under emergency conditions, the release pressure of described pressure relief valve is adjusted to
The water level pressure head value of the built-in material-changing water tank of containment.
Passive nuclear power station secondary buck system the most according to claim 1, it is characterised in that described isolating valve is explosion
Valve.
Passive nuclear power station secondary buck system the most according to claim 1 and 2, it is characterised in that when system occurs broken
Mouth passive system order puts into, and receives fourth stage Automatic Depressurization System valve and confirms to open signal, after time delay in 40 seconds, opens
Dynamic auxiliary depressurizing system, wherein opens the isolating valve on discharge pipe line, if system pressure is not also reduced to displacement in containment
The water level pressure head value of material water tank, then pressure relief valve opens, and is discharged by vapours, and aid system blood pressure lowering, at system pressure drop
Low below the water level pressure head value of the built-in material-changing water tank of containment, containment built-in material-changing water tank peace note starts, pressure relief valve
Closing, secondary buck quits work.
4. a passive nuclear power station secondary buck system, it is characterised in that it top including being arranged on reactor pressure vessel
Independent discharge of steam pipeline on end socket, is in series with spray thrower, isolating valve and elevated tank, described high-order water on discharge pipe line
Case connects with the pressure-equalizing line of Core makeup tank, and described isolating valve is for keeping zero leakage under normal operation and in thing
Fully open under the conditions of therefore.
Passive nuclear power station secondary buck system the most according to claim 4, it is characterised in that described spray thrower is down J
Type spray thrower.
6. according to the passive nuclear power station secondary buck system described in claim 4 or 5, it is characterised in that when system occurs broken
Mouth passive system order puts into, and receives fourth stage Automatic Depressurization System valve and confirms to open signal, after time delay in 40 seconds, opens
Dynamic auxiliary depressurizing system, wherein opens the isolating valve on discharge pipe line, connects pipeline by elevated tank and carries out upper cover
Cooling water injects.
Passive nuclear power station secondary buck system the most according to claim 6, it is characterised in that according to steam latent heat value,
Steam and cooling water density, according to the following formula carry out cool down water injection rate estimation:
Wherein, m is required cooling water inflow, and V is upper cover volume,For vapour density,For latent heat enthalpy,For injecting
The supercool enthalpy of cooling water.
8. a passive nuclear power station secondary buck system, it is characterised in that it include being arranged on reactor pressure vessel one
Sprinkler in body cover head device, described sprinkler includes that one or more groups sprays allotter, and sprinkler is connected to isolation
Valve, described isolating valve is for keeping zero leakage under normal operation and fully opening under emergency conditions, and isolating valve is connected to
Water source, described integration cover head device includes air inlet and the air outlet at top of bottom, and it utilizes air inlet and air outlet
The steam spraying evaporation generation is taken out of.
Passive nuclear power station secondary buck system the most according to claim 8, it is characterised in that described water source is high-order water
Case, the water source being separately provided, or the built-in material-changing water tank of existing containment.
Passive nuclear power station secondary buck system the most according to claim 8 or claim 9, it is characterised in that when system occurs broken
Mouth passive system order puts into, and receives fourth stage Automatic Depressurization System valve and confirms to open signal, after time delay in 40 seconds, opens
Dynamic auxiliary depressurizing system, wherein opens the isolating valve on discharge pipe line, starts when the built-in material-changing water tank of containment injects, injects
Pipeline flow > 500t/h time, close isolating valve.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201620259332.6U CN205789133U (en) | 2016-03-31 | 2016-03-31 | A kind of passive nuclear power station secondary buck system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201620259332.6U CN205789133U (en) | 2016-03-31 | 2016-03-31 | A kind of passive nuclear power station secondary buck system |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN205789133U true CN205789133U (en) | 2016-12-07 |
Family
ID=57414430
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201620259332.6U Expired - Fee Related CN205789133U (en) | 2016-03-31 | 2016-03-31 | A kind of passive nuclear power station secondary buck system |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN205789133U (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109887624A (en) * | 2019-03-06 | 2019-06-14 | 中国核动力研究设计院 | Analyses of LOCA Long-term cooling system when modular rickle containment isolated failure |
| CN111627577A (en) * | 2020-06-05 | 2020-09-04 | 中国核动力研究设计院 | Test system and test method for performance evaluation of active equipment in accident environment |
| CN114121309A (en) * | 2021-11-26 | 2022-03-01 | 中国核动力研究设计院 | Reactor based on all-ceramic dispersion micro-packaging fuel and silicon carbide cladding |
-
2016
- 2016-03-31 CN CN201620259332.6U patent/CN205789133U/en not_active Expired - Fee Related
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109887624A (en) * | 2019-03-06 | 2019-06-14 | 中国核动力研究设计院 | Analyses of LOCA Long-term cooling system when modular rickle containment isolated failure |
| CN111627577A (en) * | 2020-06-05 | 2020-09-04 | 中国核动力研究设计院 | Test system and test method for performance evaluation of active equipment in accident environment |
| CN111627577B (en) * | 2020-06-05 | 2022-02-22 | 中国核动力研究设计院 | Test system and test method for performance evaluation of active equipment in accident environment |
| CN114121309A (en) * | 2021-11-26 | 2022-03-01 | 中国核动力研究设计院 | Reactor based on all-ceramic dispersion micro-packaging fuel and silicon carbide cladding |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN105810257B (en) | A kind of passive nuclear power station pressure release condensation heat exchange system | |
| JP5791836B1 (en) | Boiling water type geothermal exchanger and boiling water type geothermal power generator | |
| CN105810256B (en) | A kind of nuclear power station passive residual heat removal system | |
| CN104979023B (en) | Passive containment thermal conduction system and its control method and pressurized water reactor | |
| CN102163469B (en) | Nuclear power station non-active engineering safety system | |
| JP5731051B1 (en) | Boiling water type geothermal exchanger and boiling water type geothermal power generator | |
| CN204480678U (en) | A kind of nuclear power station Heat Discharging System of Chinese | |
| CN204614459U (en) | A kind of non-active nuclear power station pressure release condensation heat exchange system | |
| CN102867550A (en) | Passive heat removal device for dealing with station blackout accident | |
| CN205789133U (en) | A kind of passive nuclear power station secondary buck system | |
| CN105957567B (en) | A kind of steam generator secondary side Heat Discharging System of Chinese | |
| CN104103325B (en) | Heat derivation system for long-term passive containment | |
| JP6067173B1 (en) | Geothermal exchanger and geothermal power generator | |
| CN104916334A (en) | Separated heat pipe type passive residual heat removal system for pressurized water reactor nuclear power plant | |
| KR101250479B1 (en) | Apparatus for safety improvement of passive type emergency core cooling system with a safeguard vessel and Method for heat transfer-function improvement using thereof | |
| CN104205239A (en) | System for discharging residual power of pressurized water nuclear reactor | |
| JP2017106430A (en) | Geothermal heat exchanger and geothermal power generation device | |
| CN204680390U (en) | Pressurized-water reactor nuclear power plant separate heat pipe formula Heat Discharging System of Chinese | |
| CN104078086A (en) | Active and passive combined containment sump water cooling system | |
| CN107799188A (en) | A kind of containment pressure supression system | |
| CN205230605U (en) | Active containment cooling system of nuclear power station non - | |
| CN206907495U (en) | Nuclear reactor | |
| CN103295657A (en) | Residual heat removal system of nuclear reactor | |
| CN204010703U (en) | A kind of containment sump water cooling system of active, non-active combination | |
| CN202549318U (en) | Residual heat removable system of nuclear reactor |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| CF01 | Termination of patent right due to non-payment of annual fee |
Granted publication date: 20161207 Termination date: 20190331 |
|
| CF01 | Termination of patent right due to non-payment of annual fee |