CN107293338A - Nuclear reactor safety system - Google Patents
Nuclear reactor safety system Download PDFInfo
- Publication number
- CN107293338A CN107293338A CN201610862926.0A CN201610862926A CN107293338A CN 107293338 A CN107293338 A CN 107293338A CN 201610862926 A CN201610862926 A CN 201610862926A CN 107293338 A CN107293338 A CN 107293338A
- Authority
- CN
- China
- Prior art keywords
- reactor
- pond
- heat exchanger
- heat
- loop
- 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.)
- Granted
Links
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
- G21D9/00—Arrangements to provide heat for purposes other than conversion into power, e.g. for heating buildings
-
- 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)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention discloses a kind of nuclear reactor safety system, including：Pond, reactor vessel, reactor core, First Heat Exchanger, passive residual heat heat exchanger and the first isolating valve, reactor vessel is arranged on below the liquid level in pond, reactor core is located in reactor vessel, the vessel inlet and container outlet of First Heat Exchanger and reactor vessel are connected together to the first loop of closing, First Heat Exchanger is connected with heating network, water in reactor vessel carries out heat exchange by the water in First Heat Exchanger and heating network, passive residual heat heat exchanger is located at below the liquid level in pond, passive residual heat heat exchanger is connected with the first loop, for when accident occurs for reactor by the heat derives in the first loop to pond, pipeline between passive residual heat heat exchanger and the first loop is provided with the first isolating valve closed and opened when accident occurs for reactor in normal reactor operation.Nuclear reactor safety system according to embodiments of the present invention, it is simple in construction, it is safe.
Description
Technical field
The present invention relates to nuclear reactor technology field, more particularly, to a kind of nuclear reactor safety system.
Background technology
The heat-supplying mode of current China is main based on coal, and coal resources are non-renewable energy resources, scarcity of resources and combustion
Burning process can cause serious environmental pollution, with the development of heat supplying nuclear reactor technology, can not only be subtracted using nuclear heating
The consumption of few traditional fossil energy, more preferable environmental protection, moreover it is possible to widen the civil area of nuclear energy, in original power generation applications base
Increase heat supply purposes on plinth.Heat supplying nuclear reactor in correlation technique is usually shell-type reactor, it is necessary to set emergency safety to note
The system such as water and spray facility, process system and security system are complex, and cost of investment is higher, and pool heat reactor
, it is necessary to be handled using different equipment, poor safety performance when occurring accident.
The content of the invention
It is contemplated that at least solving one of above-mentioned technical problem to a certain extent.
Therefore, the present invention proposes a kind of nuclear reactor safety system, the nuclear reactor safety system architecture is simple, and cost is low
And it is safe.
Nuclear reactor safety system according to embodiments of the present invention, including：Pond, reactor vessel, reactor core, the first heat exchange
Device, passive residual heat heat exchanger and the first isolating valve, the reactor vessel are located in the pond and in the pond
Liquid level below, the reactor vessel has a vessel inlet and container outlet, and the reactor core is located in the reactor vessel,
The First Heat Exchanger is located at outside the reactor vessel, the vessel inlet of the First Heat Exchanger and the reactor vessel
The first loop of closing is connected together to container outlet, the First Heat Exchanger is suitable to be connected with heating network, the reactor
Water in container carries out heat exchange, the passive residual heat heat exchanger by the water in the First Heat Exchanger and the heating network
It is located in the pond and below the liquid level in the pond, the passive residual heat heat exchanger and first loop phase
Even, for when accident occurs for the reactor by the heat derives in first loop to the pond, described first
Isolating valve is located on the pipeline between the passive residual heat heat exchanger and first loop, and first isolating valve is described
Close and opened when accident occurs for the reactor during normal reactor operation.
Nuclear reactor safety system according to embodiments of the present invention, reactor vessel is arranged in pond, pipeline is utilized
First Heat Exchanger is connected, it is heating network heat supply that the reactor core of reactor vessel inner chamber is reacted to the heat produced, and is set in pond
The passive residual heat heat exchanger connected with reactor vessel is put, passive residual heat heat exchanger and first is controlled using the first isolating valve
The conducting of pipeline between loop, can not only ensure that pool heat reactor normally runs heat supply, moreover it is possible to improve pool heat supply
The security performance of reactor, when accident occurs for pool heat reactor using passive residual heat heat exchanger by reactor vessel
Heat transmission into pond, absorb the heat that distributes of pool heat reactor using the water in pond, prevent that pool heat supply is anti-
Answer heap accident to induce bigger security incident to occur, and the simple cost of nuclear reactor safety system architecture is low, by reactor core control
In pond, additionally it is possible to prevent nuclear leakage, the extent of injury security performance for reducing accident is high.
In addition, nuclear reactor safety system according to embodiments of the present invention, can also have technical characteristic additional as follows：
According to one embodiment of present invention, the nuclear reactor safety system also includes：Built-in heat exchanger and outer displacement
Hot device, the built-in heat exchanger is located in the pond and below the liquid level in the pond, and the external heat exchanger is set
Outside the pond, for exporting the heat in the pond.
According to one embodiment of present invention, the nuclear reactor safety system also includes primary Ioops voltage-stablizer, described one
Loop voltage-stablizer is located at outside the pond, and the primary Ioops voltage-stablizer is connected to adjust first loop with first loop
In the reactor pressure in non-cut accident and the primary Ioops voltage-stablizer occurs for interior pressure, the primary Ioops voltage-stablizer
The signal for controlling first isolating valve to open is sent during higher than predetermined value.
According to one embodiment of present invention, the nuclear reactor safety system also includes containment, and the pond is located at
In the containment, the external heat exchanger is located at outside the containment.
According to one embodiment of present invention, the nuclear reactor safety system also include cistern, the cistern with
The pond connection, for the moisturizing into the pond.
According to one embodiment of present invention, the pressure in the loop between the First Heat Exchanger and the heating network is big
Pressure in first loop.
According to one embodiment of present invention, the pressure in first loop is the micro- of 1.5-20 standard atmospheric pressure
Pressure.
According to one embodiment of present invention, the pressure in first loop is 5-12 standard atmospheric pressure.
According to one embodiment of present invention, the pressure in first loop is 6-9 standard atmospheric pressure.
According to one embodiment of present invention, the nuclear reactor safety system also includes safe filling pipe and safe moisturizing
Valve, the safe filling pipe is located in the pond, and the safe water compensating valve is arranged on the safe filling pipe, the safety
Filling pipe is connected at one end with the reactor vessel and the other end is connected with the pond, and the safe water compensating valve is described anti-
Opened when answering heap to occur the pressure in accident and the reactor vessel less than pressure in the pond so as in the pond
Water be injected into the reactor vessel.
The additional aspect and advantage of the present invention will be set forth in part in the description, and will partly become from the following description
Obtain substantially, or recognized by the practice of the present invention.
Brief description of the drawings
The above-mentioned and/or additional aspect and advantage of the present invention will become from description of the accompanying drawings below to embodiment is combined
Substantially and be readily appreciated that, wherein：
Fig. 1 is the structural representation of nuclear reactor safety system according to embodiments of the present invention.
Reference：
100：Nuclear reactor safety system
10：Pond；11：Containment；
20：Reactor vessel；21：Vessel inlet；22：Container outlet；23：Safe filling pipe；24：Safety is mended
Water valve；
30：First Heat Exchanger；31：First import；32：First outlet；33：Voltage-stablizer；34：Release case；35：
Pressure-relief valve；36：Safety valve；37：Compartment；
40：Passive residual heat heat exchanger；41：Second import；42：Second outlet；
50：First isolating valve；51：Second isolating valve；
60：Built-in heat exchanger；61：External heat exchanger；70：Cold pipe；80：Heat pipe；90：Non-return valve.
Embodiment
Embodiments of the invention are described below in detail, the example of the embodiment is shown in the drawings, wherein from beginning to end
Same or similar label represents same or similar element or the element with same or like function.Below with reference to attached
The embodiment of figure description is exemplary, it is intended to for explaining the present invention, and be not considered as limiting the invention.
1 specifically describe nuclear reactor safety system 100 according to embodiments of the present invention below in conjunction with the accompanying drawings.
As shown in figure 1, nuclear reactor safety system 100 according to embodiments of the present invention, including：Pond 10, reactor hold
Device 20, reactor core (not shown), First Heat Exchanger 30, the isolating valve 50 of passive residual heat heat exchanger 40 and first.
Specifically, reactor vessel 20 is located in pond 10 and below the liquid level in pond 10, reactor vessel
20 have vessel inlet 21 and container outlet 22, and reactor core is located in reactor vessel 20, and First Heat Exchanger 30 holds positioned at reactor
The vessel inlet 21 and container outlet 22 of the outside of device 20, First Heat Exchanger 30 and reactor vessel 20 are connected together to the of closing
Primary Ioops, First Heat Exchanger 30 is connected with heating network (not shown), the water in reactor vessel 20 by First Heat Exchanger 30 with
Water in heating network carries out heat exchange, passive residual heat heat exchanger 40 be located at the liquid level in pond 10 and in pond 10 with
Under, passive residual heat heat exchanger 40 is connected with the first loop, for when accident occurs for reactor by the heat in the first loop
Export in pond 10, the first isolating valve 50 is located on the pipeline between the loop of passive residual heat heat exchanger 40 and first, first
Isolating valve 50 is closed and opened when accident occurs for reactor in normal reactor operation.
In other words, nuclear reactor safety system 100 is main by pond 10, reactor vessel 20, reactor core, First Heat Exchanger
30th, the isolating valve 50 of passive residual heat heat exchanger 40 and first is constituted, and the water surface in pond 10 has a reactor vessel 20, reaction
The side of heap container 20 is provided with vessel inlet 21 and container outlet 22, and vessel inlet 21 and container outlet 22 hold with reactor
Reactor core, the vessel inlet 21 and container outlet 22 of reactor vessel 20 are provided with the inner chamber connection of device 20, reactor vessel 20
Connect the first import 31 and the first outlet 32 of First Heat Exchanger 30 with cold pipe 70 by heat pipe 80 respectively, First Heat Exchanger 30 leads to
Cross vessel inlet 21 and container outlet 22 and the first loop (not shown) of formation is connected with reactor vessel 20, cold pipe 70 is provided with the
Two isolating valves 51, heat pipe 80 is provided with non-return valve 90, and cold pipe 70, with being provided with coolant in heat pipe 80, coolant is in the first heat exchange
Flowing carries out heat exchange between device 30 and reactor vessel 20.
Wherein, passive residual heat heat exchanger 40 is additionally provided with pond 10, passive residual heat heat exchanger 40 is located in pond 10
The water surface under, one end of passive residual heat heat exchanger 40 is provided with the second import 41, and the other end is provided with second outlet 42, and second enters
Mouth 41 and second outlet 42 are connected with the cold pipe 70 and heat pipe 80 in the first loop respectively, and passive residual heat heat exchanger 40 utilizes cold
But liquid and the first loop carry out pipeline between heat exchange, the loop of passive residual heat heat exchanger 40 and first provided with first every
From valve 50, the first isolating valve 50 can control the opening and closing of pipeline between the loop of passive residual heat heat exchanger 40 and first,
By controlling the flowing of coolant between the loop of passive residual heat heat exchanger 40 and first, so control the opening of heat exchange with
Close.
When accident occurs for pool heat reactor, the first isolating valve 50 is opened, conducting passive residual heat heat exchanger 40 with
Pipeline between first loop, using the connection function in the first loop, the two-port of passive residual heat heat exchanger 40 is respectively communicated with
The vessel inlet 21 of reactor vessel 20 and the two-port of container outlet 22 and First Heat Exchanger 30, by cold in connecting pipe
But the heat exchange between passive residual heat heat exchanger 40, First Heat Exchanger 30 and reactor vessel 20 is realized in the circulation of liquid.
Thus, nuclear reactor safety system 100 according to embodiments of the present invention, pond 10 is arranged on by reactor vessel 20
In, using pipeline communication First Heat Exchanger 30, the reactor core of the inner chamber of reactor vessel 20 is reacted to the heat produced and supplied for heating network
Heat, and the passive residual heat heat exchanger 40 connected with reactor vessel 20 is set in pond 10, controlled using the first isolating valve 50
The conducting of pipeline, can not only ensure that pool heat reactor is normal between the loop of passive residual heat heat exchanger 40 and first processed
Run heat supply, moreover it is possible to improve the security performance of pool heat reactor, non-energy is utilized when accident occurs for pool heat reactor
Heat transmission in reactor vessel 20 into pond 10, is absorbed pool using the water in pond 10 and supplied by dynamic afterheat heat exchanger 40
The heat that thermal reactor is distributed, prevents pool heat reactor accident from inducing bigger security incident and occurring, and nuclear reactor
The cost simple in construction of security system 100 is low, by reactor core control in pond 10, additionally it is possible to prevent nuclear leakage, reduces the danger of accident
Evil degree security performance is high.
Further, nuclear reactor safety system 100 also includes containment 11, and pond 10 is located in containment 11, safety
Shell 11 is externally provided with external heat exchanger 61, and containment 11 is arranged on bottom, sidepiece and the top in pond 10 to accommodate and covered pool
10.Specifically, as shown in figure 1, the periphery in pond 10 is provided with containment 11, containment 11 can be closed and coat pond 10
Top, sidepiece and bottom, the inner chamber in pond 10 are provided with accommodating chamber, accommodating chamber to be formed provided with water and are provided with pond 10, pond 10
Reactor vessel 20 and passive residual heat heat exchanger 40, it is ensured that the security of reactor system.
By setting containment 11 in the periphery of pond 10, can not only limit accommodating chamber is used to accommodate pond 10 and pool
Heat reactor, moreover it is possible to form containment vessel and wrap up pool heat reactor, on the one hand can reduce external environment to pond
The interference effect of formula heat reactor, on the other hand can prevent that leakage occurs when pool heat reactor from occurring accident or hurt
Surrounding employee, moreover, containment 11 is simple in construction, easily realizes, practical, improves the safety of pool heat reactor system
Property.
Preferably, nuclear reactor safety system 100 also includes built-in heat exchanger 60 and external heat exchanger 61, built-in heat exchanger
60 are located in pond 10 and below the liquid level in pond 10, and external heat exchanger 61 is located at outside pond 10, for exporting pond
Heat in 10, as shown in figure 1, being provided with built-in heat exchanger 60 in pond 10, built-in heat exchanger 60 is arranged in pond 10 and not had
Below the water surface, it is ensured that built-in heat exchanger 60 can be contacted sufficiently with water, built-in heat exchanger 60 outside pipeline communication by replacing
Coolant is provided with hot device 61, built-in heat exchanger 60 and external heat exchanger 61 and pipeline between the two, coolant is built-in
Heat exchange is realized in flowing between heat exchanger 60 and external heat exchanger 61.
Wherein, respectively in the inside and outside setting built-in heat exchanger 60 in pond 10 and external heat exchanger 61, and pipeline communication, energy are passed through
It is enough timely by outside the heat transfer in pond 10 to pond 10, it is ensured that the water in pond 10 is in a relatively low temperature shape
State, by increasing capacitance it is possible to increase the operating efficiency of passive residual heat heat exchanger 40, improves passive residual heat heat exchanger 40 and current in pond 10
Heat exchanger effectiveness, and then increase the internal heat of reactor vessel 20 diffuser efficiency and speed, thus, built-in heat exchanger 60,
External heat exchanger 61 and the co-ordination of passive residual heat heat exchanger 40, form the heat-exchange system of series of stable, reduce pool
Heat accumulation when accident occurs for heat reactor, reduces accident harm, improve pool heat reactor safety in utilization and
Controlling.
Advantageously, nuclear reactor safety system 100 also includes primary Ioops voltage-stablizer 33, and primary Ioops voltage-stablizer 33 is located at pond
Outside 10, one end of primary Ioops voltage-stablizer 33 is connected on heat pipe 80, other end connection release case 34, and release case 34 and primary Ioops are steady
Pressure-relief valve 35 is provided between depressor 33, by pipeline communication water between pressure-relief valve 35 and primary Ioops voltage-stablizer 33, and in connection
Pipeline is provided with safety valve 36, and primary Ioops voltage-stablizer 33 and First Heat Exchanger 30 isolate setting with reactor by interval 37.
Primary Ioops voltage-stablizer 33 is connected with the first loop to adjust the pressure in the first loop, and primary Ioops voltage-stablizer 33 is anti-
Heap is answered to occur to send control the first isolating valve 50 dozens when the pressure in non-cut accident and primary Ioops voltage-stablizer 33 is higher than predetermined value
The signal opened.
Specifically, connected in the first loop and connect primary Ioops on the pipeline between reactor vessel 20 and First Heat Exchanger 30
Voltage-stablizer 33, primary Ioops voltage-stablizer 33 can adjust the pressure in the first loop by the loop of pipeline communication first, for example, working as
When the pressure that pool heat reactor occurs in non-cut accident and primary Ioops voltage-stablizer 33 is higher than predetermined value, primary Ioops voltage-stablizer
33 send signal, control unlatching and the closure of the first isolating valve 50.
Nuclear reactor safety system 100 is when non-cut accident occurs for reactor, the accident starting stage, in the first loop
Coolant pressure and temperature rise, and primary Ioops voltage-stablizer 33 sends the opening signal of the first isolating valve 50, the first isolating valve 50 dozens
The pipeline between the loop of passive residual heat heat exchanger 40 and first is opened, passive residual heat heat exchanger 40 and reactor vessel 20 is realized
Heat exchange between interior, by the heat transfer in reactor vessel 20 into water, passes through built-in heat exchanger 60 and external heat exchange
Device 61 is further transferred heat to outside containment 11, on the one hand can reduce pool heat reactor into First Heat Exchanger 30
The heat of transmission, on the other hand the temperature and pressure in reduction reactor vessel 20, prevent reactor core from occurring a greater degree of destruction,
Prevent the first loop from occurring cut under HTHP effect, improve the security performance of nuclear energy uses, utilize primary Ioops voltage-stablizer
33 automatically control the opening and closing of the first isolating valve 50, are operated in person without operating personnel, reduce pool heat reactor to operation
The damage of personnel.
Alternatively, nuclear reactor safety system 100 also includes cistern (not shown), and cistern is connected with pond 10, uses
In the moisturizing into pond 10, that is to say, that nuclear reactor safety system 100 is by setting cistern to further enhance system
Safety guarantee, when the water water level in pond 10 is reduced to certain altitude, opens cistern and is connected with pond 10 on pipeline
Valve, be pond 10 carry out moisturizing.
It is the moisturizing of pond 10 using cistern, it is ensured that the water in pond 10 is not less than a certain height, for example, when in pond 10
Water when being less than the height, cistern is the moisturizing of pond 10, when the water level in pond 10 reaches certain height, cistern
Stop as the moisturizing of pond 10, prevent the security of the very few influence pool heat reactor of water in pond 10, it is ensured that pool heat supply
When reactor breaks down, the enough pool heat reactor radiatings of water in pond 10.
Preferably, the pressure in the loop between First Heat Exchanger 30 and heating network is more than the pressure in the first loop,
That is, the pressure in the first loop is smaller, that is, the container for connecting reactor vessel 20 enters between 21 mouthfuls and container outlet 22
The pressure of inner cavity of pipe coolant is relatively low, connecting pipe formation second between the heat exchanger (not shown) of First Heat Exchanger 30 and second
The pressure of coolant in loop, second servo loop is higher, and tertiary circuit is formed between the second heat exchanger and heating network (not shown).
Wherein, the pressure in the first loop is relatively low, damaged in the heap major loop that reacts, particularly when in First Heat Exchanger 30
When being damaged, the pressure of coolant is higher between First Heat Exchanger 30 and heating network, does not result in the cooling in the first loop
Liquid is revealed, so that prevent that coolant is lost in reactor vessel 20 or evaporation causes Core uncovering to be damaged, low temperature minute-pressure
Characteristic makes the condition that it possesses reduction equipment safety rank.
Alternatively, the pressure in the first loop is the minute-pressure of 1.5-20 standard atmospheric pressure.Advantageously, in the first loop
Pressure is the minute-pressure of 5-12 standard atmospheric pressure.Preferably, the pressure in the first loop is 6-9 standard atmospheric pressure.
The determination of the operational factor of process heat reactor is solid according to design and the technical requirements of user terminal (heating network) balance
Change what is obtained.Too low operating pressure (being less than 1.5 atmospheric pressure) can cause reactor export problem is too low (to can only achieve 100
DEG C or so), the temperature is difficult the demand (large-scale 110 DEG C of heat supply network return water temperature requirement) for adapting to municipal heating systems.Too high pressure (example
Such as more than 20 atmospheric pressure) although the outlet temperature of reactor core can be greatly improved, (such as presurized water reactor can reach 150
Atm higher, outlet temperature can reach more than 310 DEG C), but high pressure can bring cost to be significantly increased, system complex and anti-
Answer the problems such as heap security is greatly reduced.According to optimization design, the optimum pressure section of minute-pressure process heat reactor is 5-12 normal atmosphere
Between pressure, the operating pressure scope is on the premise of ensureing that reactor is inherently safe, it is possible to achieve large-scale heat supply network (heat supply temperature
More than 120 DEG C) and part industrial heating demand.If minute-pressure process heat reactor design is using 6 atmospheric pressure (6-9 standards
In barometric pressure range), the system outlet temperature fully meets large-scale heat supply network technical requirements up to 120 DEG C, while taking into account well
Economy and security, are a prioritization schemes dedicated for resident's heat supply.
Wherein it should be noted that minute-pressure is the pressure of the pressure of coolant or container outlet 22 in the first loop
Power, because reactor core is slightly less than at reactor core to that can produce a certain amount of pressure loss, the pressure of container outlet 22 between container outlet 22
Pressure.
The design parameter of coolant pressure in first loop can be according in coolant pressure in second servo loop, pond 10
The actual design demands such as water pressure make accommodation, so as to can not only improve pool heat supply under accidental conditions
The heating parameter of reactor, and when occurring accident, it is ensured that reactor core is unlikely to cause naked because cooling water is largely lost in
Dew so that pool heat reactor has the condition of reduction level of security, advantageously reduces equipment manufacturing cost.
Nuclear reactor safety system 100 also includes safe filling pipe 23 and safe water compensating valve 24, and safe filling pipe 23 is located at
In pond 10, safe water compensating valve 24 is arranged on safe filling pipe 23, and one end and the reactor vessel 20 of safe filling pipe 23 connect
The logical and other end is connected with pond 10, and safe water compensating valve 24 occurs the pressure in accident and reactor vessel 20 in reactor and is less than
Opened during pressure in pond 10 so that the water in pond 10 is injected into reactor vessel 20.
Referring to the drawings 1, the bottom of reactor vessel 20 is provided with safe filling pipe 23, one end of safe filling pipe 23 and reaction
The bottom wall of heap container 20 is connected, and is connected with the inner chamber of reactor vessel 20, and the other end of safe filling pipe 23 is in water, can
Water is poured into safe water compensating valve 24, safe water compensating valve are provided between the inside of reactor vessel 20, the two ends of safe filling pipe 23
The conducting of the 24 safe filling pipes 23 of control, so as to control the supplement of water in reactor vessel 20.
When accident occurs for reactor, safe water compensating valve 24 is opened, if the pressure in reactor vessel 20 is less than pond 10
Current in the pressure of the interior free end of safe filling pipe 23, pond 10 enter reactor vessel 20 in the presence of hydrostatic pressure,
The temperature of reactor core in reactor vessel 20, the destroying infection that reduction accident is caused can be reduced.
The worked of nuclear reactor safety system 100 according to embodiments of the present invention is described with reference to specific embodiment
Journey.
Nuclear reactor safety system 100 according to embodiments of the present invention, including：Pond 10, reactor vessel 20, reactor core,
First Heat Exchanger 30, the isolating valve 50 of passive residual heat heat exchanger 40 and first, reactor vessel 20 are located in pond 10 and are located at
Below liquid level in pond 10, reactor vessel 20 has vessel inlet 21 and container outlet 22, and reactor core is located at reactor vessel
In 20, First Heat Exchanger 30 is located at the outside of reactor vessel 20, the vessel inlet 21 of First Heat Exchanger 30 and reactor vessel 20
The first loop of closing is connected together to container outlet 22, First Heat Exchanger 30 is connected with heating network, in reactor vessel 20
Water heat exchange is carried out by the water in First Heat Exchanger 30 and heating network, passive residual heat heat exchanger 40 be located in pond 10 and
Below the liquid level in pond 10, passive residual heat heat exchanger 40 is connected with the first loop, for occurring accident in reactor
When by the heat derives in the first loop to pond 10, the first isolating valve 50 is located at passive residual heat heat exchanger 40 and first time
On pipeline between road, the first isolating valve 50 is closed and opened when accident occurs for reactor in normal reactor operation.
Wherein, when non-cut accident occurs for pool heat reactor, the first isolating valve 50 is opened, and turns on passive residual heat
Pipeline between the loop of heat exchanger 40 and first, utilizes the connection function in the first loop, the two ends of passive residual heat heat exchanger 40
Mouth is respectively communicated with the vessel inlet 21 and container outlet 22 of reactor vessel 20, is realized by the circulation of coolant in connecting pipe
Heat exchange between passive residual heat heat exchanger 40 and reactor vessel 20, and utilize built-in heat exchanger 60 and external heat exchanger
The heat in pond 10 is discharged in mutual cooperation between 61, is prevented in reactor vessel that temperature and pressure persistently rises and is caused more
Serious accident occurs.
If cut accident occurs for pool heat reactor, because the temperature in the first loop, pressure are relatively low, even if reactor
Major loop produces breakage, also largely will not be lost in and evaporated the peace caused on Core uncovering, safe filling pipe 23 due to cooling agent
Full water compensating valve 24 is opened, and the water in pond enters reactor vessel 20, and the characteristic of low temperature minute-pressure makes it possess reduction equipment safety
The condition of rank.
Nuclear reactor safety system 100 according to embodiments of the present invention, reactor vessel 20 is arranged in pond 10, profit
With pipeline communication First Heat Exchanger 30, the reactor core of the inner chamber of reactor vessel 20 is reacted to the heat transmission produced and goes out to set for other
Available heat, and the passive residual heat heat exchanger 40 connected with reactor vessel 20 is set in pond 10, utilize the first isolating valve
The conducting of pipeline, can not only ensure pool heat reactor just between 50 control passive residual heat heat exchangers 40 and the first loop
Normal operation heat supply, moreover it is possible to improve the security performance of pool heat reactor, is utilized when accident occurs for pool heat reactor
Heat transmission in reactor vessel 20 into pond 10, is utilized the water absorption cell in pond 10 by passive residual heat heat exchanger 40
The heat that formula heat reactor is distributed, prevents pool heat reactor accident from inducing bigger security incident and occurring, and pool
The cost simple in construction of heat reactor security system 100 is low, by reactor core control in pond 10, additionally it is possible to prevent nuclear leakage, drops
The extent of injury security performance of low accident is high.
Sum it up, pool heat reactor according to embodiments of the present invention, is mainly by three circulation loops and safety
System composition, the first loop is coolant circuit, and using cooling agent as carrier, reactor core disintegration energy is effectively exported；Second time
Road is radioactivity isolated loop, while playing a part of additional hot trap；Tertiary circuit is heat supplying loop, with thermal source user's pipe network phase
Even.Reactor core implosion is become the Energy Efficient produced and exported by three circulation loops, is used for district heating system.
First loop is mainly made up of reaction reator body and reactor coolant loop.Reactor body construction is by reactor
Container, reactor core, in-pile component and CRDM etc. are constituted.Reactor core is located in reactor vessel, reactor vessel submergence
In a deep well, compared with the pool reactor that directly reactor core is immersed in pond, the pressure in reactor vessel is more
Height, makes its heating parameter increase.Moreover, compared with shell-type reactor, during the water in the system in well can be accident
Export residual heat of nuclear core and huge middle hot trap is provided, be an important mitigation strategy of reactor accident.Reactor core upper and lower part
It is respectively equipped with chamber.CRDM is located above reactor core.
Reactor coolant loop is made up of several loops, and each loop is by the primary side of one-level plate type heat exchanger, master
The composition such as pump and related pipeline, valve.Reactor inlet pipeline is connected to the bottom of core pressure vessel, that is to say, that under
Chamber is connected with several cold pipes.Compared with existing presurized water reactor technology, the reactor vessel of the system is submerged in pond,
Pressure vessel can not set descending branch, and equipment is simplified, and reduce the resistance of cooling agent.Reactor export pipeline is connected to heap
The top of core pressure vessel, that is to say, that reactor upper chamber is connected with several heat pipes.
Pool heat reactor is provided with second servo loop, and coolant circuit is connected with municipal heating systems.Second servo loop is by some
Individual loop composition, each loop by the secondary side of first-class heat exchanger, the primary side of secondary heat exchanger, circulating pump, voltage-stablizer and
Corresponding pipeline, valve composition.Reactor coolant loop is isolated by second servo loop with city heat supply pipeline, it is ensured that any
Under accident conditions, radioactivity will not be carried out to the heating net belt in city.And the pressure of working medium is slightly above the first loop in second servo loop,
Under accident conditions, the cooling agent in the first loop will not be leaked to second servo loop, in case the working medium to second servo loop is caused
Radioactive pollution；Second servo loop plays additional hot trap effect simultaneously, under some accident conditionses, can partly export more than reactor core
Heat.
Pool heat reactor is additionally provided with three loops, is connected with the heating network in city.If tertiary circuit by one or
Dry loop composition, each loop is by the secondary side of secondary heat exchanger, constant pressure pump, circulating pump and corresponding pipeline, valve group
Into.
In addition, be additionally provided with voltage-stablizer on reactor coolant loop, heated by electric heater and the spray of spray thrower come
Adjust voltage-stablizer internal pressure.Voltage-stablizer is connected with release case, and connecting pipe is provided with pressure-relief valve and safety valve.Work as voltage-stablizer
When pressure height arrives setting valve, pressure-relief valve is opened, and voltage-stablizer is connected with release case so that the pressure reduction in voltage-stablizer；When steady
When depressor pressure height arrives a higher setting valve, safety valve is opened, and voltage-stablizer is connected with water so that the pressure in voltage-stablizer
Reduction.
The security system of the pool heat reactor mainly includes the pond heat extraction circulatory system and passive residual heat removal system
System, the pond heat extraction circulatory system air cooler, pond inside heat exchanger and associated conduit, valve outside shielding factory building are constituted, and are shielded
The outer air cooler of factory building is located at outside shielding factory building, and connecting pipe is through containment and keeps containment leak tightness, is final using air
Hot trap, realizes the heat exchange of water and air, water is cooled down without time limit.When pond water temperature rises the setting valve that reaches a high temperature
Afterwards, the heat extraction circulatory system in pond will start, and flowing, hot fluid are formed under buoyancy lift driving after fluid heating in the circulatory system
Rise in outdoor air cooling device, under air cooling, density rises, and the heat-exchange tube flowed down in back pool is acted in density contrast,
So go round and begin again to form circulation, decay heat is endlessly exported in environment.
Heat Discharging System of Chinese is by passive residual heat heat exchanger, pond, non-return valve, the first isolating valve and connecting pipe
Composition.Non-return valve is connected with the cold pipe of coolant circuit, when occurring cut accident, when reaction reactor water level is to less than the pond water surface
Automatically opened up during certain altitude, water floods reactor core into reactor, when occurring non-cut accident, the second isolating valve is closed,
Isolate first and changed and held device, while the first isolating valve is opened, connected on passive residual heat heat exchanger and reactor core, reactor core
The water or steam of side will enter passive residual heat heat exchanger and carry out heat exchange cooling with water.
The temperature of cooling agent, pressure in micro- pressurization well-type reactor of pool heat reactor according to embodiments of the present invention
It is relatively low, when the heap major loop that reacts is damaged, Core uncovering will not be caused because cooling agent is largely lost in and evaporated.Low temperature is micro-
The characteristic of pressure makes the condition that it possesses reduction equipment safety rank, advantageously reduces equipment manufacturing cost.
Reactor vessel does not set descending branch, and equipment is simplified, and reduces the resistance of cooling agent.Using plate-type heat-exchange
Device, compact conformation, and maintenance cost is relatively low.Compared with traditional PWR nuclear power plant, reactor core is used without boron scheme, is simplified existing
There is the change applied in power plant to hold system, simplify operation technological process.Using the pond heat extraction circulatory system, under density contrast effect
Circulation is formed, decay heat is endlessly exported in environment, safety guarantee does not have time restriction.Reactor coolant loop
Low-pressure low-temperature operation characteristic, the passive feature of security system, the huge heat release capacity in deep water pond and air cooling follow
Air is excluded decay heat, above overall characteristic in pond by ring so that the design is able to ensure that reaction
Heap is inherently safe, actual elimination reaction heap reactor core failure risk.
Other of pool heat reactor according to embodiments of the present invention are constituted and operated for ordinary skill
All it is known for personnel, is not detailed herein.
In the description of the invention, it is to be understood that term " " center ", " longitudinal direction ", " transverse direction ", " length ", " width ",
" thickness ", " on ", " under ", "front", "rear", "left", "right", " vertical ", " level ", " top ", " bottom " " interior ", " outer ", " up time
The orientation or position relationship of the instruction such as pin ", " counterclockwise " are, based on orientation shown in the drawings or position relationship, to be for only for ease of
The description present invention and simplified description, rather than indicate or imply that the device or element of meaning must have specific orientation, Yi Te
Fixed azimuth configuration and operation, therefore be not considered as limiting the invention.
In addition, term " first ", " second " are only used for describing purpose, and it is not intended that indicating or implying relative importance
Or the implicit quantity for indicating indicated technical characteristic.Thus, define " first ", the feature of " second " can express or
Implicitly include one or more this feature.In the description of the invention, " multiple " are meant that two or more,
Unless otherwise specifically defined.
In the present invention, unless otherwise clearly defined and limited, term " installation ", " connected ", " connection ", " fixation " etc.
Term should be interpreted broadly, for example, it may be being fixedly connected or being detachably connected, or be integrally connected；It can be machine
Tool is connected or electrically connected；Can be joined directly together, can also be indirectly connected to by intermediary, can be two members
Connection inside part.For the ordinary skill in the art, above-mentioned term can be understood in this hair as the case may be
Concrete meaning in bright.
In the present invention, unless otherwise clearly defined and limited, fisrt feature second feature it " on " or it " under "
Can directly it be contacted including the first and second features, it is not direct contact but by it that can also include the first and second features
Between other characterisation contact.Moreover, fisrt feature second feature " on ", " top " and " above " to include first special
Levy directly over second feature and oblique upper, or be merely representative of fisrt feature level height higher than second feature.Fisrt feature exists
Second feature " under ", " lower section " and " following " fisrt feature that includes are directly over second feature and oblique upper, or be merely representative of
Fisrt feature level height is less than second feature.
In the description of this specification, reference term " one embodiment ", " some embodiments ", " example ", " specifically show
The description of example " or " some examples " etc. means to combine specific features, structure, material or the spy that the embodiment or example are described
Point is contained at least one embodiment of the present invention or example.In this manual, to the schematic representation of above-mentioned term not
Necessarily refer to identical embodiment or example.Moreover, specific features, structure, material or the feature of description can be any
One or more embodiments or example in combine in an appropriate manner.
Although embodiments of the invention have been shown and described above, it is to be understood that above-described embodiment is example
Property, it is impossible to limitation of the present invention is interpreted as, one of ordinary skill in the art is not departing from the principle and objective of the present invention
In the case of above-described embodiment can be changed within the scope of the invention, change, replace and modification.
Claims (10)
1. a kind of nuclear reactor safety system, it is characterised in that including：
Pond,
Reactor vessel, the reactor vessel is located in the pond and below the liquid level in the pond, described anti-
Answer heap container that there is vessel inlet and container outlet；
Reactor core in the reactor vessel；
First Heat Exchanger outside the reactor vessel, the container of the First Heat Exchanger and the reactor vessel enters
Mouth and container outlet are connected together to the first loop of closing, and the First Heat Exchanger is suitable to be connected with heating network, the reaction
Water in heap container carries out heat exchange by the water in the First Heat Exchanger and the heating network；
Passive residual heat heat exchanger, the passive residual heat heat exchanger is located at the liquid level in the pond and in the pond
Hereinafter, the passive residual heat heat exchanger is connected with first loop, for inciting somebody to action described when accident occurs for the reactor
Heat derives in first loop are in the pond；
First isolating valve, first isolating valve is located at the pipeline between the passive residual heat heat exchanger and first loop
On, first isolating valve is closed and opened when accident occurs for the reactor in the normal reactor operation.
2. nuclear reactor safety system according to claim 1, it is characterised in that also include：
Built-in heat exchanger, the built-in heat exchanger is located in the pond and below the liquid level in the pond；
External heat exchanger, the external heat exchanger is located at outside the pond, for exporting the heat in the pond.
3. nuclear reactor safety system according to claim 1, it is characterised in that also include：Primary Ioops voltage-stablizer, it is described
Primary Ioops voltage-stablizer is located in the containment and outside the pond, the primary Ioops voltage-stablizer and first loop phase
Even to adjust the pressure in first loop, in the reactor non-cut accident occurs for the primary Ioops voltage-stablizer and described
Pressure in primary Ioops voltage-stablizer sends the signal for controlling first isolating valve to open when being higher than predetermined value.
4. nuclear reactor safety system according to claim 1, it is characterised in that also include：Containment, the pond is set
In the containment, the external heat exchanger is located at outside the containment.
5. nuclear reactor safety system according to claim 1, it is characterised in that also include：Cistern, the cistern
Connected with the pond, for the moisturizing into the pond.
6. nuclear reactor safety system according to claim 5, it is characterised in that the First Heat Exchanger and the heat supply
The pressure in loop between net is more than the pressure in first loop.
7. the nuclear reactor safety system according to any one of claim 1-6, it is characterised in that in first loop
Pressure for 1.5-20 standard atmospheric pressure minute-pressure.
8. nuclear reactor safety system according to claim 7, it is characterised in that the pressure in first loop is 5-
12 standard atmospheric pressures.
9. nuclear reactor safety system according to claim 8, it is characterised in that the pressure in first loop is 6-
9 standard atmospheric pressures.
10. nuclear reactor safety system according to claim 1, it is characterised in that also include：It is located in the pond
Safe filling pipe and the safe water compensating valve being located on the safe filling pipe, the safe filling pipe at one end with the reactor
The reservoir and other end is connected with the pond, in the reactor accident and the reactor occur for the safe water compensating valve
Pressure in container is opened so that the water in the pond is injected into the reactor vessel when being less than the pressure in the pond
It is interior.
Applications Claiming Priority (10)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201620302992 | 2016-04-12 | ||
| CN2016102254196 | 2016-04-12 | ||
| CN201620302818 | 2016-04-12 | ||
| CN2016203029928 | 2016-04-12 | ||
| CN201610225419 | 2016-04-12 | ||
| CN2016102250566 | 2016-04-12 | ||
| CN2016203028183 | 2016-04-12 | ||
| CN201610225056 | 2016-04-12 | ||
| CN201620589730 | 2016-06-16 | ||
| CN2016205897304 | 2016-06-16 |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN107293338A true CN107293338A (en) | 2017-10-24 |
| CN107293338B CN107293338B (en) | 2023-06-23 |
Family
ID=58761733
Family Applications (5)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201610862925.6A Active CN107293341B (en) | 2016-04-12 | 2016-09-28 | Pool type reactor |
| CN201621089894.7U Active CN206210405U (en) | 2016-04-12 | 2016-09-28 | Nuclear reactor safety system |
| CN201621091308.2U Active CN206210418U (en) | 2016-04-12 | 2016-09-28 | Pool reactor |
| CN201621089913.6U Active CN206210415U (en) | 2016-04-12 | 2016-09-28 | Pool heat reactor |
| CN201610862926.0A Active CN107293338B (en) | 2016-04-12 | 2016-09-28 | Nuclear reactor safety system |
Family Applications Before (4)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201610862925.6A Active CN107293341B (en) | 2016-04-12 | 2016-09-28 | Pool type reactor |
| CN201621089894.7U Active CN206210405U (en) | 2016-04-12 | 2016-09-28 | Nuclear reactor safety system |
| CN201621091308.2U Active CN206210418U (en) | 2016-04-12 | 2016-09-28 | Pool reactor |
| CN201621089913.6U Active CN206210415U (en) | 2016-04-12 | 2016-09-28 | Pool heat reactor |
Country Status (1)
| Country | Link |
|---|---|
| CN (5) | CN107293341B (en) |
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108417282A (en) * | 2018-05-11 | 2018-08-17 | 上海核工程研究设计院有限公司 | A kind of loop structure of reactor circuit and a kind of low-temperature heat supply reactor with the reactor circuit |
| CN109545402A (en) * | 2018-10-30 | 2019-03-29 | 中广核研究院有限公司 | A kind of method that nuclear power station is adjusted based on the chemical environment of water of no soluble boron coolant |
| CN109559836A (en) * | 2018-10-30 | 2019-04-02 | 中广核研究院有限公司 | A kind of method that nuclear power station is improved based on the chemical environment of water of no soluble boron coolant |
| CN112071454A (en) * | 2020-09-15 | 2020-12-11 | 哈尔滨工程大学 | Passive combined heat removal system with integrated heat release trap |
| CN112216412A (en) * | 2020-09-04 | 2021-01-12 | 国家电投集团科学技术研究院有限公司 | Passive self-adjusting waste heat removal system and method and liquid metal reactor |
| WO2023241096A1 (en) * | 2022-06-16 | 2023-12-21 | 中广核研究院有限公司 | Integrated safety system for reactor |
Families Citing this family (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107293341B (en) * | 2016-04-12 | 2023-11-03 | 国家电投集团科学技术研究院有限公司 | Pool type reactor |
| CN108320817B (en) * | 2017-12-28 | 2019-12-20 | 中核北方核燃料元件有限公司 | Air pressure sealing method |
| CN108443850A (en) * | 2018-03-29 | 2018-08-24 | 何满潮 | Waste heat collection and utilization system for underground neutron energy power station |
| CN108550407A (en) * | 2018-03-30 | 2018-09-18 | 清华大学天津高端装备研究院 | A kind of lead bismuth heap primary Ioops system and nuclear reactor |
| CN108665981A (en) * | 2018-07-03 | 2018-10-16 | 启迪新核（北京）能源科技有限公司 | The natural circulation cooling system and well formula normal pressure process heat reactor of well formula normal pressure process heat reactor |
| CN108877962A (en) * | 2018-07-11 | 2018-11-23 | 上海核工程研究设计院有限公司 | A kind of pool integrated low-temperature reactor heating system |
| CN111383782B (en) * | 2018-12-28 | 2022-12-23 | 国家电投集团科学技术研究院有限公司 | Passive safety system and pressurized water reactor with same |
| CN111383786B (en) * | 2018-12-29 | 2022-08-30 | 国家电投集团科学技术研究院有限公司 | Method for changing material of pool reactor |
| CN111883270B (en) * | 2020-08-26 | 2023-05-23 | 中国原子能科学研究院 | Heat discharging system, pool type reactor and pool type reactor heat discharging method |
Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2000019285A (en) * | 1998-07-06 | 2000-01-21 | Hitachi Ltd | Reactor heat removal system |
| CN101149990A (en) * | 2007-11-09 | 2008-03-26 | 中国核动力研究设计院 | Non-kinetic inherently safe tube-pool type reactor |
| CN103295656A (en) * | 2012-02-29 | 2013-09-11 | 上海核工程研究设计院 | Diversified engineered safety system for nuclear reactor |
| CN103377732A (en) * | 2012-04-27 | 2013-10-30 | 上海核工程研究设计院 | Heat pipe-based passive after-heat removal system of spent fuel pool |
| CN206210405U (en) * | 2016-04-12 | 2017-05-31 | 国家电投集团科学技术研究院有限公司 | Nuclear reactor safety system |
Family Cites Families (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2750789B1 (en) * | 1996-07-08 | 1998-11-06 | Framatome Sa | PROCESS FOR PRODUCING STEAM FROM THE HEAT RELEASED FROM THE HEART OF A NUCLEAR REACTOR AND NUCLEAR REACTOR FOR IMPLEMENTING THE PROCESS |
| JP2002156485A (en) * | 2000-11-15 | 2002-05-31 | Hitachi Ltd | Reactor |
| CN101154472B (en) * | 2006-09-29 | 2011-11-09 | 中国核动力研究设计院 | Integrated low-temperature nuclear heat supplying pile |
| CN201914937U (en) * | 2010-12-30 | 2011-08-03 | 一重集团大连设计研究院有限公司 | Seawater desalination system with multilevel heat exchanges |
| CN105374408A (en) * | 2015-11-27 | 2016-03-02 | 田力 | Deep well type atmospheric pressure heat supply nuclear reactor |
-
2016
- 2016-09-28 CN CN201610862925.6A patent/CN107293341B/en active Active
- 2016-09-28 CN CN201621089894.7U patent/CN206210405U/en active Active
- 2016-09-28 CN CN201621091308.2U patent/CN206210418U/en active Active
- 2016-09-28 CN CN201621089913.6U patent/CN206210415U/en active Active
- 2016-09-28 CN CN201610862926.0A patent/CN107293338B/en active Active
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2000019285A (en) * | 1998-07-06 | 2000-01-21 | Hitachi Ltd | Reactor heat removal system |
| CN101149990A (en) * | 2007-11-09 | 2008-03-26 | 中国核动力研究设计院 | Non-kinetic inherently safe tube-pool type reactor |
| CN103295656A (en) * | 2012-02-29 | 2013-09-11 | 上海核工程研究设计院 | Diversified engineered safety system for nuclear reactor |
| CN103377732A (en) * | 2012-04-27 | 2013-10-30 | 上海核工程研究设计院 | Heat pipe-based passive after-heat removal system of spent fuel pool |
| CN206210405U (en) * | 2016-04-12 | 2017-05-31 | 国家电投集团科学技术研究院有限公司 | Nuclear reactor safety system |
Non-Patent Citations (1)
| Title |
|---|
| 庄毅;黄兴蓉;姜百华;张金山;石家娟;: "CARR应急堆芯冷却系统停堆冷却措施分析" * |
Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108417282A (en) * | 2018-05-11 | 2018-08-17 | 上海核工程研究设计院有限公司 | A kind of loop structure of reactor circuit and a kind of low-temperature heat supply reactor with the reactor circuit |
| CN109545402A (en) * | 2018-10-30 | 2019-03-29 | 中广核研究院有限公司 | A kind of method that nuclear power station is adjusted based on the chemical environment of water of no soluble boron coolant |
| CN109559836A (en) * | 2018-10-30 | 2019-04-02 | 中广核研究院有限公司 | A kind of method that nuclear power station is improved based on the chemical environment of water of no soluble boron coolant |
| CN112216412A (en) * | 2020-09-04 | 2021-01-12 | 国家电投集团科学技术研究院有限公司 | Passive self-adjusting waste heat removal system and method and liquid metal reactor |
| CN112216412B (en) * | 2020-09-04 | 2023-11-03 | 国家电投集团科学技术研究院有限公司 | Passive self-regulating waste heat lead-out system, method and liquid metal reactor |
| CN112071454A (en) * | 2020-09-15 | 2020-12-11 | 哈尔滨工程大学 | Passive combined heat removal system with integrated heat release trap |
| WO2023241096A1 (en) * | 2022-06-16 | 2023-12-21 | 中广核研究院有限公司 | Integrated safety system for reactor |
Also Published As
| Publication number | Publication date |
|---|---|
| CN206210405U (en) | 2017-05-31 |
| CN206210418U (en) | 2017-05-31 |
| CN107293341B (en) | 2023-11-03 |
| CN107293338B (en) | 2023-06-23 |
| CN107293341A (en) | 2017-10-24 |
| CN206210415U (en) | 2017-05-31 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN206210405U (en) | Nuclear reactor safety system | |
| CN202887748U (en) | Passive heat discharge device for dealing with plant switch-off accident | |
| CN202110832U (en) | Top-positioned type non-dynamic emergency waste heat discharging system for pressurized water reactor | |
| WO2016078421A1 (en) | Passive safe cooling system | |
| CN104979023B (en) | Passive containment thermal conduction system and its control method and pressurized water reactor | |
| CN201946323U (en) | Emergency water supply system for nuclear power station | |
| CN206210417U (en) | Dry type reactor heating system | |
| CN107644693B (en) | Naval reactor and once through steam generator Passive residual heat removal system | |
| CN106328223B (en) | A kind of novel passive containment energy management system | |
| CN113808764B (en) | Method and system for guiding out residual heat of reactor core in containment | |
| CN110517796A (en) | A kind of improved passive residual heat removal system | |
| CN104916334A (en) | Separated heat pipe type passive residual heat removal system for pressurized water reactor nuclear power plant | |
| CN107093473B (en) | A kind of used by nuclear reactor residual heat removal system | |
| CN209729520U (en) | A kind of passive dump of nuclear power station steam generator and cooling system | |
| CN106531243B (en) | Waste heat discharge system and factory building under small-size pressurized water reactor accident of modularization | |
| CN203366752U (en) | Passive pressurized water reactor depressurizing system | |
| CN204680390U (en) | Pressurized-water reactor nuclear power plant separate heat pipe formula Heat Discharging System of Chinese | |
| CN114121313A (en) | Passive safety system of compact reactor | |
| CN203397713U (en) | Secondary side afterheat removal system with non-condensable gas collecting device | |
| CN103295657A (en) | Residual heat removal system of nuclear reactor | |
| CN207489488U (en) | A kind of pressurized water reactor peculiar to vessel and its primary side non-kinetic residual heat removal system | |
| CN100510595C (en) | Full natural-circulating air cooling tower | |
| CN208111094U (en) | A kind of cooling system | |
| CN203070791U (en) | Built-in spent fuel pool of containment | |
| CN85100182A (en) | Adopt the nuclear power station light water reactor of double pressure shell |
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 | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |