CN206210405U - Nuclear reactor safety system - Google Patents
Nuclear reactor safety system Download PDFInfo
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- CN206210405U CN206210405U CN201621089894.7U CN201621089894U CN206210405U CN 206210405 U CN206210405 U CN 206210405U CN 201621089894 U CN201621089894 U CN 201621089894U CN 206210405 U CN206210405 U CN 206210405U
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- reactor
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
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- 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
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- 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
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The utility model 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 the liquid level lower section in pond, reactor core is located in reactor vessel, First Heat Exchanger is connected together to the first loop of closing with the vessel inlet and container outlet of reactor vessel, 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 the liquid level lower section in pond, passive residual heat heat exchanger is connected with the first loop, for when there is accident in 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 in normal reactor operation and opened when reactor occurs accident.According to nuclear reactor safety system of the present utility model, simple structure is safe.
Description
Technical field
The utility model is related 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 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 processed using different equipment, poor safety performance when there is accident.
Utility model content
The utility model is intended at least solve one of above-mentioned technical problem to a certain extent.
Therefore, the utility model proposes a kind of nuclear reactor safety system, the nuclear reactor safety system architecture is simple, into
This is low and safe.
According to nuclear reactor safety system of the present utility model, 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 vessel inlet and a container outlet, and the reactor core is located in the reactor vessel,
The First Heat Exchanger is located at reactor vessel outside, the vessel inlet of the First Heat Exchanger and the reactor vessel
With the first loop that container outlet is connected together to closing, 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 First Heat Exchanger with the water in 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 there is accident in 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
Closed during normal reactor operation and opened when the reactor occurs accident.
According to nuclear reactor safety system of the present utility model, reactor vessel is arranged in pond, is connected using pipeline
Logical First Heat Exchanger, the heat that the reactor core reaction of reactor vessel inner chamber is produced is heating network heat supply, and is set in pond
The passive residual heat heat exchanger connected with reactor vessel, passive residual heat heat exchanger and first time are controlled using the first isolating valve
The conducting of pipeline between road, can not only ensure that pool heat reactor normally runs heat supply, moreover it is possible to improve pool heat supply anti-
The security performance of heap is answered, when pool heat reactor occurs accident using passive residual heat heat exchanger by reactor vessel
In heat transmission to pond, the heat that pool heat reactor is distributed is absorbed using the water in pond, prevent pool heat supply from reacting
Heap accident induces bigger security incident to be occurred, and the simple low cost of nuclear reactor safety system architecture, and reactor core control is existed
In pond, additionally it is possible to prevent nuclear leakage, the extent of injury security performance for reducing accident is high.
In addition, according to nuclear reactor safety system of the present utility model, can also have following additional technical characteristic：
According to one embodiment of the present utility model, the nuclear reactor safety system also includes：Built-in heat exchanger and outer
Heat exchanger is put, the built-in heat exchanger is located in the pond and below the liquid level in the pond, the external heat exchange
Device is located at outside the pond, for deriving the heat in the pond.
According to one embodiment of the present utility model, the nuclear reactor safety system also includes primary Ioops voltage-stablizer, institute
State primary Ioops voltage-stablizer to be located at outside the pond, the primary Ioops voltage-stablizer is connected to adjust described first with first loop
Pressure in loop, the primary Ioops voltage-stablizer occurs in non-cut accident and the primary Ioops voltage-stablizer in the reactor
Pressure sends the signal that control first isolating valve is opened when being higher than predetermined value.
According to one embodiment of the present utility model, the nuclear reactor safety system also includes containment, the pond
It is located in the containment, the external heat exchanger is located at outside the containment.
According to one embodiment of the present utility model, the nuclear reactor safety system also includes cistern, the retaining
Pond connects with the pond, for moisturizing in the pond.
According to one embodiment of the present utility model, the pressure in loop between the First Heat Exchanger and the heating network
Power is more than the pressure in first loop.
According to one embodiment of the present utility model, the pressure in first loop is 1.5-20 standard atmospheric pressure
Minute-pressure.
According to one embodiment of the present utility model, the pressure in first loop is 5-12 standard atmospheric pressure.
According to one embodiment of the present utility model, the pressure in first loop is 6-9 standard atmospheric pressure.
According to one embodiment of the present utility model, the nuclear reactor safety system also includes safe filling pipe and safety
Water compensating valve, the safe filling pipe is located in the pond, and the safe water compensating valve is arranged on the safe filling pipe, described
Safe filling pipe is connected with the reactor vessel at one end and the other end is connected with the pond, and the safe water compensating valve is in institute
Opened so as to the water when stating pressure that reactor occurs in accident and the reactor vessel less than pressure in the pond
Water in pond is injected into the reactor vessel.
Additional aspect of the present utility model and advantage will be set forth in part in the description, partly by from following description
In become obvious, or by it is of the present utility model practice recognize.
Brief description of the drawings
Of the present utility model above-mentioned and/or additional aspect and advantage will from description of the accompanying drawings below to embodiment is combined
Become substantially and be readily appreciated that, wherein：
Fig. 1 is the structural representation of the nuclear reactor safety system according to the utility model embodiment.
Reference：
100：Nuclear reactor safety system
10：Pond；11：Containment；
20：Reactor vessel；21：Vessel inlet；22：Container outlet；23：Safe filling pipe；24：Safe water compensating 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.
Specific embodiment
Embodiment of the present utility model is described below in detail, the example of the embodiment is shown in the drawings, wherein ad initio
Same or similar element or element with same or like function are represented to same or similar label eventually.Below by ginseng
The embodiment for examining Description of Drawings is exemplary, it is intended to for explaining the utility model, and it is not intended that to the utility model
Limitation.
1 specifically describe the nuclear reactor safety system 100 according to the utility model embodiment below in conjunction with the accompanying drawings.
As shown in figure 1, the nuclear reactor safety system 100 according to the utility model embodiment, including：Pond 10, reaction
Heap container 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 outside of device 20, First Heat Exchanger 30 and the vessel inlet 21 and container outlet 22 of 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 in pond 10 and the liquid level in pond 10 with
Under, passive residual heat heat exchanger 40 is connected with the first loop, for when there is accident in 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 in normal reactor operation and opened when reactor occurs accident.
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 space 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 and coolant is provided with non-return valve 90, and cold pipe 70 and heat pipe 80, and 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 cold pipe 70 and heat pipe 80 in the first loop respectively, and passive residual heat heat exchanger 40 is using cold
But liquid and the first loop carry out heat exchange, the pipeline between the loop of passive residual heat heat exchanger 40 and first be 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 pool heat reactor occurs accident, 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, the nuclear reactor safety system 100 according to the utility model embodiment, water is arranged on by reactor vessel 20
In pond 10, using pipeline communication First Heat Exchanger 30, the heat that the reactor core reaction of the inner chamber of reactor vessel 20 is produced is heat supply
Net heat supply, and the passive residual heat heat exchanger 40 that setting is connected with reactor vessel 20 in pond 10, using 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, utilizes when pool heat reactor occurs accident
Passive residual heat heat exchanger 40 by the heat transmission in reactor vessel 20 to pond 10, using the water absorption cell in pond 10
The heat that formula heat reactor is distributed, prevents pool heat reactor accident from inducing bigger security incident and occurs, and core is anti-
The simple structure low cost of heap security system 100 is answered, by reactor core control in pond 10, additionally it is possible to prevent nuclear leakage, accident is reduced
Extent of injury security performance it 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, water is provided with accommodating chamber and forms pond 10, are provided with pond 10
Reactor vessel 20 and passive residual heat heat exchanger 40, it is ensured that the security of reactor system.
Containment 11 is set by the periphery of pond 10, accommodating chamber can not only be limited for accommodating 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, is on the other hand prevented from leakage when pool heat reactor occurs accident or hurts
Surrounding employee, and, the simple structure of containment 11 is easily realized, 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 deriving 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 does not have
Below the water surface, it is ensured that built-in heat exchanger 60 can be contacted sufficiently with water, built-in heat exchanger 60 is replaced by outside pipeline communication
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 inside and outside setting built-in heat exchanger 60 and the external heat exchanger 61 in pond 10, and by pipeline communication, energy
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 with 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 heat reactor occurs accident, 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 is steady with primary Ioops
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, to be 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 reactor occur non-cut accident when, 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 to water, by 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 in First Heat Exchanger 30
The heat of transmission, on the other hand reduces the temperature and pressure in reactor vessel 20, prevents reactor core from a greater degree of destruction occurring,
Prevent the first loop from cut occurring under HTHP effect, the security performance of nuclear energy uses is improved, using primary Ioops voltage-stablizer
33 opening and closings for automatically controlling the first isolating valve 50, operate 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
The moisturizing in 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 on pipeline with pond 10
Valve, be that pond 10 carries 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 being 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, and connecting pipe forms second between the heat exchanger (not shown) of First Heat Exchanger 30 and second
Loop, the pressure of the coolant in 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, and so as to prevent, coolant in reactor vessel 20 is lost in or evaporation causes Core uncovering to be damaged, low temperature minute-pressure
Characteristic makes it possess the condition for reducing equipment safety rank.
Alternatively, the pressure in the first loop is the 1.5-20 minute-pressure of standard atmospheric pressure.Advantageously, in the first loop
Pressure is the 5-12 minute-pressure of 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 the technical requirements balance of design and user terminal (heating network)
What change was obtained.Too low operating pressure (being less than 1.5 atmospheric pressure) can cause that reactor export problem is too low (to can only achieve 100
DEG C or so), the temperature is difficult to adapt to the demand (large-scale 110 DEG C of heat supply network return water temperature requirement) of 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 cost can be brought to be significantly increased, system complex and anti-
The problems such as answering heap security to be 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.As minute-pressure process heat reactor design uses 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 to can produce the pressure of a certain amount of pressure loss, container outlet 22 to be slightly less than at reactor core between container outlet 22
Pressure.
The design parameter of the coolant pressure in the first loop can be according to coolant pressure in second servo loop, in 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 there is accident, it is ensured that reactor core is unlikely to largely to be lost in due to cooling water and causes naked
Dew so that pool heat reactor has the condition for reducing 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 and is less than in reactor
Opened so that the water in pond 10 is injected into reactor vessel 20 during pressure in pond 10.
Referring to the drawings 1, the bottom of reactor vessel 20 is provided with safe filling pipe 23, one end and the reaction of safe filling pipe 23
The bottom wall of heap container 20 is connected, and with the inner space of reactor vessel 20, the other end of safe filling pipe 23 is in water, can
Water is poured into the inside of reactor vessel 20, safe water compensating valve 24, safe water compensating valve are provided between 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 reactor occurs accident, safe water compensating valve 24 is opened, if the pressure in reactor vessel 20 is less than pond 10
The pressure of the interior free end of safe filling pipe 23, the current in 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 work of the nuclear reactor safety system 100 according to the utility model embodiment is described with reference to specific embodiment
Process.
Nuclear reactor safety system 100 according to the utility model embodiment, including：Pond 10, reactor vessel 20, heap
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 position
Below the liquid level in pond 10, reactor vessel 20 has vessel inlet 21 and container outlet 22, and reactor core holds positioned at reactor
In device 20, First Heat Exchanger 30 is located at the vessel inlet of the outside of reactor vessel 20, First Heat Exchanger 30 and reactor vessel 20
21 and container outlet 22 be connected together to the first loop of closing, First Heat Exchanger 30 is connected with heating network, reactor vessel 20
Interior water carries out heat exchange by the water in First Heat Exchanger 30 and heating network, and passive residual heat heat exchanger 40 is 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 there is thing in reactor
Therefore 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
On pipeline between loop, the first isolating valve 50 is closed in normal reactor operation and opened when reactor occurs accident.
Wherein, when pool heat reactor occurs non-cut accident, the first isolating valve 50 is opened, and turns on passive residual heat
Pipeline between the loop of heat exchanger 40 and first, using 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
Heat discharge in pond 10 is prevented temperature and pressure in reactor vessel from persistently rising and caused more by the mutual cooperation between 61
Serious accident occurs.
If pool heat reactor occurs cut accident, because the temperature in the first loop, pressure are relatively low, even if reactor
Major loop produces breakage, also will not be largely lost in and be evaporated due to cooling agent and cause Core uncovering, the peace on safe filling pipe 23
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 the utility model embodiment, pond 10 is arranged on by reactor vessel 20
In, using pipeline communication First Heat Exchanger 30, by the heat transmission that the reactor core reaction of the inner chamber of reactor vessel 20 is produced go out for
Other equipment heat supply, and the passive residual heat heat exchanger 40 that setting is connected with reactor vessel 20 in pond 10, using first
Isolating valve 50 controls the conducting of pipeline between passive residual heat heat exchanger 40 and the first loop, can not only ensure that pool heat supply is anti-
Answer heap normally to run heat supply, moreover it is possible to improve the security performance of pool heat reactor, accident occurs in pool heat reactor
Shi Liyong passive residual heats heat exchanger 40 by the heat transmission in reactor vessel 20 to pond 10, using the water in pond 10
The heat that pool heat reactor is distributed is absorbed, is prevented pool heat reactor accident from inducing bigger security incident and is occurred, and
And the simple structure low cost of pool heat reactor security system 100, by reactor core control in pond 10, additionally it is possible to prevent core from letting out
Leakage, the extent of injury security performance for reducing accident is high.
Sum it up, the pool heat reactor according to the utility model embodiment, mainly by three circulation loops and peace
Total system is constituted, and the first loop is coolant circuit, with cooling agent as carrier, reactor core disintegration energy is effectively derived；The
Secondary circuit is radioactivity isolated loop, while playing a part of additional hot trap；Tertiary circuit is heat supplying loop, is managed with thermal source user
Net is connected.Reactor core implosion is become three circulation loops the Energy Efficient for producing derives, and 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 during reactor core directly is immersed in into pond, the pressure in reactor vessel is more
Height, makes its heating parameter increase.And, compared with shell-type reactor, the water in the system in well can be for during accident
Derive 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 at reactor core top.
Reactor coolant loop is made up of several loops, and each loop is led by the primary side of one-level plate type heat exchanger
The composition such as pipeline, valve of pump and correlation.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.With city heat supply pipeline be isolated in reactor coolant loop by second servo loop, 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 order to avoid the working medium of second servo loop is caused
Radioactive pollution；Second servo loop plays additional hot trap effect simultaneously, under some accident conditionses, can partly derive 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 spray thrower spray come
Regulation 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
Pressure it is high to setting valve when, pressure-relief valve is opened, and voltage-stablizer is connected with release case so that the pressure in voltage-stablizer is reduced；When steady
Depressor pressure it is high to a setting valve higher when, safety valve is opened, and voltage-stablizer is connected with water so that the pressure in voltage-stablizer
Reduce.
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 is made up of the outer air cooler of shielding factory building, pond inside heat exchanger and associated conduit, valve, shields
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 with air
Hot trap, realizes the heat exchange of water and air, and 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, in the heat-exchange tube that density contrast effect flows down in back pool,
So go round and begin again to form circulation, during decay heat endlessly to export to 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 there is 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 there is non-cut accident, the second isolating valve is closed,
Isolate first and changed and held device, while the first isolating valve is opened, passive residual heat heat exchanger and reactor core have been connected, on reactor core
The water or steam of side will carry out heat exchange cooling into passive residual heat heat exchanger and water.
The temperature of cooling agent in micro- pressurization well-type reactor of the pool heat reactor according to the utility model embodiment,
Pressure is relatively low, when the heap major loop that reacts is damaged, will not be largely lost in and be evaporated due to cooling agent and cause Core uncovering.It is low
The characteristic of warm minute-pressure makes it possess the condition for reducing 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 compositions of pool heat reactor according to the utility model embodiment and operation are common for this area
All it is known for technical staff, is not detailed herein.
In description of the present utility model, it is to be understood that term " " center ", " longitudinal direction ", " transverse direction ", " length ", " width
Degree ", " thickness ", " on ", D score, "front", "rear", "left", "right", " vertical ", " level ", " top ", " bottom " " interior ", " outward ", " suitable
The orientation or position relationship of the instruction such as hour hands ", " counterclockwise " are based on orientation shown in the drawings or position relationship, merely to just
Described with simplified in description the utility model, must be with specific side rather than the device or element for indicating or imply meaning
Position, with specific azimuth configuration and operation, therefore it is not intended that to limitation of the present utility model.
Additionally, 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 description of the present utility model, " multiple " is meant that two or two
More than, unless otherwise expressly limited specifically.
In the utility model, unless otherwise clearly defined and limited, term " installation ", " connected ", " connection ", " Gu
It is fixed " etc. term should be interpreted broadly, for example, it may be being fixedly connected, or being detachably connected, or be integrally connected；Can
Being to mechanically connect, or electrically connect；Can be joined directly together, it is also possible to be indirectly connected to by intermediary, Ke Yishi
Two connections of element internal.For the ordinary skill in the art, above-mentioned term can as the case may be understood
Concrete meaning in the utility model.
In the utility model, unless otherwise clearly defined and limited, fisrt feature second feature it " on " or it
D score can include the first and second feature directly contacts, it is also possible to including the first and second features not be directly contact but logical
The other characterisation contact crossed between them.And, fisrt feature second feature " on ", " top " and " above " include the
One feature is directly over second feature and oblique upper, or is merely representative of fisrt feature level height higher than second feature.First is special
Levy second feature " under ", " lower section " and " below " include fisrt feature directly over second feature and oblique upper, or only
Represent that 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 spy that the embodiment or example are described
Point is contained at least one embodiment of the present utility model or example.In this manual, to the schematic table of above-mentioned term
State and be not necessarily referring to identical embodiment or example.And, the specific features of description, structure, material or feature can be
Combined in an appropriate manner in one or more any embodiments or example.
Although embodiment of the present utility model has been shown and described above, it is to be understood that above-described embodiment is
Exemplary, it is impossible to it is interpreted as to limitation of the present utility model, one of ordinary skill in the art is not departing from the utility model
Principle and objective in the case of above-described embodiment can be changed in the range of the utility model, 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-
Answering heap container has vessel inlet and container outlet；
Reactor core in the reactor vessel；
First Heat Exchanger outside the reactor vessel, the First Heat Exchanger enters with the container of the reactor vessel
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 First Heat Exchanger with the water in 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 the reactor occurs accident
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 in the normal reactor operation and opened when the reactor occurs accident.
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 deriving the heat in the pond.
3. nuclear reactor safety system according to claim 2, it is characterised in that also include：Containment, the pond sets
In the containment, the external heat exchanger is located at outside the containment.
4. nuclear reactor safety system according to claim 3, 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, there is non-cut accident and described in the primary Ioops voltage-stablizer in the reactor
Pressure in primary Ioops voltage-stablizer sends the signal that control first isolating valve is opened when being higher than predetermined value.
5. nuclear reactor safety system according to claim 1, it is characterised in that also include：Cistern, the cistern
Connected with the pond, for moisturizing in 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 be 1.5-20 standard atmospheric 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, there is accident and the reactor in the safe water compensating valve in the reactor
Opened so that the water in the pond is injected into the reactor vessel during pressure that the pressure in container is less than in the pond
It is interior.
Applications Claiming Priority (10)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2016203028183 | 2016-04-12 | ||
| CN201620302818 | 2016-04-12 | ||
| CN2016203029928 | 2016-04-12 | ||
| CN2016102254196 | 2016-04-12 | ||
| CN201610225056 | 2016-04-12 | ||
| CN2016102250566 | 2016-04-12 | ||
| CN201620302992 | 2016-04-12 | ||
| CN201610225419 | 2016-04-12 | ||
| CN2016205897304 | 2016-06-16 | ||
| CN201620589730 | 2016-06-16 |
Publications (1)
| Publication Number | Publication Date |
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| CN206210405U true CN206210405U (en) | 2017-05-31 |
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 |
| CN201610862926.0A Active CN107293338B (en) | 2016-04-12 | 2016-09-28 | Nuclear reactor safety system |
| CN201621089913.6U Active CN206210415U (en) | 2016-04-12 | 2016-09-28 | Pool heat 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 |
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| Application Number | Title | Priority Date | Filing Date |
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| CN201610862925.6A Active CN107293341B (en) | 2016-04-12 | 2016-09-28 | Pool type reactor |
| CN201610862926.0A Active CN107293338B (en) | 2016-04-12 | 2016-09-28 | Nuclear reactor safety system |
| CN201621089913.6U Active CN206210415U (en) | 2016-04-12 | 2016-09-28 | Pool heat reactor |
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| Application Number | Title | Priority Date | Filing Date |
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| CN201621091308.2U Active CN206210418U (en) | 2016-04-12 | 2016-09-28 | Pool reactor |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107293338A (en) * | 2016-04-12 | 2017-10-24 | 国家电投集团科学技术研究院有限公司 | Nuclear reactor safety system |
| 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 |
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| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| CN112071454B (en) * | 2020-09-15 | 2023-01-03 | 哈尔滨工程大学 | Passive combined heat removal system with integrated heat release trap |
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| CN114999683B (en) * | 2022-06-16 | 2024-09-24 | 中广核研究院有限公司 | Integrated safety system for a reactor |
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- 2016-09-28 CN CN201621089913.6U patent/CN206210415U/en active Active
- 2016-09-28 CN CN201621089894.7U patent/CN206210405U/en active Active
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| CN107293338A (en) * | 2016-04-12 | 2017-10-24 | 国家电投集团科学技术研究院有限公司 | Nuclear reactor safety system |
| CN107293338B (en) * | 2016-04-12 | 2023-06-23 | 国家电投集团科学技术研究院有限公司 | Nuclear reactor safety system |
| 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 |
Also Published As
| Publication number | Publication date |
|---|---|
| CN107293341A (en) | 2017-10-24 |
| CN107293338A (en) | 2017-10-24 |
| CN107293338B (en) | 2023-06-23 |
| CN206210415U (en) | 2017-05-31 |
| CN107293341B (en) | 2023-11-03 |
| CN206210418U (en) | 2017-05-31 |
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