CN205656860U - Active discharge system of reactor core waste heat non - is piled in heat supply of low temperature nuclear - Google Patents
Active discharge system of reactor core waste heat non - is piled in heat supply of low temperature nuclear Download PDFInfo
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- CN205656860U CN205656860U CN201620055139.0U CN201620055139U CN205656860U CN 205656860 U CN205656860 U CN 205656860U CN 201620055139 U CN201620055139 U CN 201620055139U CN 205656860 U CN205656860 U CN 205656860U
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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
- Y02E30/30—Nuclear fission reactors
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Abstract
The utility model discloses an active discharge system of reactor core waste heat non - is piled in heat supply of low temperature nuclear, including reactor core after -heat removal system and heat transfer discharge system, reactor core after -heat removal system is including setting up the heat exchanger in heat exchange water tank, and heat exchanger import and export communicate steam generator's export and import respectively, still be equipped with in the heat exchange water tank the heat exchanger of heat transfer discharge system, the export and the import import and the export of the air cooler of intercommunication setting in the heat preservation air cooling tower respectively of heat exchanger, steam generator's import intercommunication moisturizing device. The utility model discloses possess the advantage of the active equipment of non -, improved the safety coefficient reliability effectively, strengthened the adaptibility to response of safety coefficient under nuclear power station accident operating mode, can effectively prevent and alleviate severe accident, reduce the risk probability that the reactor core melts probability and extensive radioactivity release, improve the nuclear power station security performance greatly, guarantee the rear screen barrier of nuclear safety.
Description
Technical field
This utility model belongs to low-temperature nuclear heat supplying pile safety system technical field, is specially a kind of low temperature
Nuclear heat supplying pile residual heat of nuclear core passive discharge system.
Background technology
Nuclear energy as the industrialization alternative energy source of safe and clean, efficient and unique practicable, the past
In many decades in terms of the ambient pressure that the electricity needs and alleviation greenhouse gases that meet the mankind are brought, play
Important effect, supplementing as nuclear power, nuclear heat supplying pile export sensible heat, can be used for residence, cities and towns
The people are for warm comprehensive utilization, and its popularization and application contribute to improving energy resource structure, GHG emissions mitigation and changing
Kind town environment.
At present, the subject matter that nuclear heating exists: after nuclear reactor shutdown, due to the residue of heap in-core
Fission and the decay of fission product, the residual heating of generation is the most considerable in the quite a long time,
Need to be set out to ultimate heat sink by the special safe level residual heat removal system arranged.Otherwise, in heap
Thermal accumlation and temperature raise and fuel element failure may be caused even to melt, thus cause serious radiation
The nuclear safety accident released outside property.This be nuclear reactor designs needs pay close attention to most important safety problem it
One.
In nuclear power station, containment is the important safety facility of reactor, is to prevent radioactive product to be discharged into
Last one barrier in atmospheric environment.In the pressurized-water reactor nuclear power plant of active service, for ensureing that reactor is being sent out
When raw design basis accident and beyond design basis accident, the decay heat of reactor core can persistently be discharged, logical
Often designing residual heat removal system at primary side, cooling water tank is arranged in containment, takies by this mode
The free space of containment, but also need the newly-increased heat exchanger being positioned in material-changing water tank, so that
The design of system and expenditure of construction increase, and once occur heat-transfer pipe damaged, primary Ioops coolant also can be made to let out
Leakage.Additionally, this residual heat removal system is under accident conditions, needs the power supply outside Chang Nei factory, emergent set
Standby (such as expensive Emergency diesel) and the intervention of operator, on the one hand this increase operator people because losing
Risk by mistake, on the other hand considerably increases number of devices, thus increases equipment purchase, installs, runs
With the expense of maintenance etc., the corresponding construction cost increasing nuclear power plant and operation and maintenance expenses are used.
Therefore, it is necessary to provide a kind of to realize the derivation of reactor core decay heat, fall under accident the most passively
The secondary side passive residual heat guiding system of low construction and O&M cost, to solve above-mentioned prior art not
Foot.
In view of this, special proposition this utility model.
Utility model content
The technical problems to be solved in the utility model is to overcome the deficiencies in the prior art, it is provided that a kind of low temperature
Nuclear heat supplying pile residual heat of nuclear core passive discharge system, improves shutdown safety.
For solving above-mentioned technical problem, the basic conception of this utility model employing technical scheme is:
A kind of low-temperature nuclear heat supplying pile residual heat of nuclear core passive discharge system, including residual heat of nuclear core guiding system and
System is discharged in heat exchange, and described residual heat of nuclear core guiding system includes the heat exchanger being arranged in heat-exchanging water tank,
Heat exchanger inlets is respectively communicated with outlet and the import of steam generator with outlet；It is additionally provided with in heat-exchanging water tank
The heat exchanger of system is discharged in described heat exchange, and the outlet of heat exchanger and import are respectively communicated with and are arranged on insulation air cooling
The import of the air cooler in tower and outlet；The inlet communication water replanishing device of described steam generator.
Preferably, the import of described heat exchanger connects the major steam line of steam generator by steam pipe,
The outlet of heat exchanger connects the main feed line of steam generator by condensing tube, and described heat exchanger sets
The heat-exchanging water tank low inside put outside containment is put.
Preferably, described heat exchanger is water water-to-water heat exchanger, and water water-to-water heat exchanger is arranged on the middle part of heat-exchanging water tank
Or top；The import of water water-to-water heat exchanger connects the outlet of air cooler, going out of water water-to-water heat exchanger by down-comer
Mouth connects the import of air cooler by tedge.
Preferably, the top of described insulation air cooling tower is provided with hot air outlet, and the bottom of insulation air cooling tower sets
There is inlet of cold air.
Preferably, condensing tube is provided with two normally closed isolating valves in parallel, and wherein the first isolating valve is active
Isolating valve, the second isolating valve is passive isolating valve, and isolating valve downstream is provided with a check-valves.
Further, also include that constant pressure tank, the expansion tube of constant pressure tank lower center position are communicated to
Tedge, constant pressure tank bottom side is provided with circulation pipe, and circulation pipe is communicated to tedge；Constant pressure tank position
The peak of system is discharged in heat exchange.
Preferably, described water replanishing device includes the first water supply tank, and the first water supply tank is extremely steamed by pipeline communication
On the main feed line of vapour generator, on pipeline, parallel connection is provided with steam feed pump and electrically driven feed pump.
Preferably, steam feed pump in parallel on pipeline and electrically driven feed pump all at least 2.
Preferably, described water replanishing device includes the second water supply tank, by ball-cock assembly pipe in described constant pressure tank
Road connects described second water supply tank.
Preferably, in heat-exchanging water tank, on the connecting line of residual heat of nuclear core guiding system and system is discharged in heat exchange
It is equipped with temperature monitor, in steam generator, heat-exchanging water tank and constant pressure tank on the connecting line of system
It is equipped with water level detection gauge, temperature monitor and water level detection gauge and is the most wirelessly or non-wirelessly connected to teletransmission control
Device.
After using technique scheme, this utility model compared with prior art has the advantages that
The advantage that this utility model possesses passive equipment, it is possible to realize the secondary side cooling merit to primary Ioops
Can, make the smooth decrease temperature and pressure of primary Ioops, process heat reactor residual heat of nuclear core is derived, thus finally makes nuclear power station enter
Enter the safe condition of cold shutdown, be effectively improved security system reliability, enhance security system at core
Adaptibility to response under the accident conditions of power station, it is possible to effectively prevention is gentle solves major accident, reduces reactor core and melts
Probability and the risk probability of extensive radioactivity release, be greatly improved nuclear plant safety performance, it is ensured that core is pacified
Complete last barrier.
Accompanying drawing explanation
Fig. 1 is the structural representation of this utility model a kind of low-temperature nuclear heat supplying pile residual heat of nuclear core passive discharge system
Figure；
In figure:
1, steam generator；11, major steam line；12, main feed line；2, heat exchanger；21、
Steam pipe；22, condensing tube；23, first isolating valve；24, the second isolating valve；25, check-valves；3、
Containment；31, reactor core；4, heat-exchanging water tank；5, water water-to-water heat exchanger；51, down-comer；52, tedge；
6, air cooling tower；61, hot air outlet；62, inlet of cold air；7, air cooler；8, constant pressure tank；
81, expansion tube；82, circulation pipe；91, the first water supply tank；92, the second water supply tank；93, steam-operating feedwater
Pump；94, electrically driven feed pump.
Detailed description of the invention
Below in conjunction with the accompanying drawings and specific embodiment, the utility model is described in further detail, to help understanding
Content of the present utility model.
As it is shown in figure 1, a kind of low-temperature nuclear heat supplying pile residual heat of nuclear core passive discharge system, more than reactor core
System is discharged in hot guiding system and heat exchange, and described residual heat of nuclear core guiding system includes that heat exchanger 2, heat are handed over
The import of parallel operation 2 connects the major steam line 11 of steam generator 1, heat exchanger 2 by steam pipe 21
Outlet connected the main feed line 12 of steam generator 1, described heat exchanger 2 by condensing tube 22
Heat-exchanging water tank 4 low inside being arranged on outside containment 3 is put.
Described heat exchange is discharged system and is included being arranged on middle part or the water water-to-water heat exchanger 5 on top in heat-exchanging water tank 4,
Water liquid level in heat-exchanging water tank 4 is higher than the top of water water-to-water heat exchanger 5；Also include being incubated air cooling tower 6, protect
It is provided with air cooler 7 in temperature air cooling tower 6；The import of water water-to-water heat exchanger 5 connects air cooler by down-comer 51
The outlet of 7, the outlet of water water-to-water heat exchanger 5 connects the import of air cooler 7 by tedge 52；Insulation sky
The top of cold tower 6 is provided with hot air outlet 61, and its underpart is provided with inlet of cold air 62, water water-to-water heat exchanger 5
Heat in heat-exchanging water tank 4 takes to the most warm air cooling tower 6 in air cooler 7 discharge into the atmosphere.
When unexpected shutdown occurring, needing steam generator to discharge reactor core 31 waste heat, primary Ioops hot water passes through
Steam generator 1 heat-transfer pipe, is transmitted to secondary side by heat, makes the feedwater boiling of secondary side become steam,
Owing under accident conditions, major steam line 11 isolating valve cuts out, steam is by higher pressure in steam generator 1
The effect of power, enters along steam pipe 21 in the heat exchange of residual heat of nuclear core guiding system, is immersed in heat-exchanging water tank
Being vapour in the heat exchanger tube of the heat exchanger 2 of bottom in 4, pipe is outer is water, and steam heat is delivered in water,
Making steam condensation in heat exchanger 2, the outer water temperature of heat exchanger 2 raises；Condensed water is under gravity
The heat exchanger tube of outflow heat exchanger 2, flows back to the main feed line 12 of steam generator 1 along condensing tube 22,
Reenter steam generator 1, maintain the water level in steam generator 1.Thus Pattern completion circulation,
Realize the secondary side refrigerating function to primary Ioops, make the smooth decrease temperature and pressure of primary Ioops, by process heat reactor reactor core 31
Waste heat is derived, thus finally makes nuclear power station enter the safe condition of cold shutdown.
After water around heat-exchanging water tank 4 inside heat exchanger 2 absorbs steam heat, temperature raises, and density reduces,
Warm water can flow up, and the water temperature of heat-exchanging water tank 4 middle and upper part raises, and is arranged on heat-exchanging water tank 4 middle and upper part
Water water-to-water heat exchanger 5 absorb the heat of warm water and be taken to be incubated in the air cooler 7 in air cooling tower 6,
Water temperature near the water water-to-water heat exchanger 5 of heat-exchanging water tank 4 middle and upper part reduces, and density reduces, and cold water sinks,
Return to again carry out near the heat exchanger 2 of heat-exchanging water tank 4 bottom above-mentioned steam-water heat transfer process, so
Water in heat-exchanging water tank 4 forms Natural Circulation, is delivered to by the heat in heat-exchanging water tank 4 continuously
In the air cooler 7 of insulation air cooling tower 6.
The warm water of water water-to-water heat exchanger 5 is in tedge 52 enters air cooler 7, by the sky outside air cooler 7 pipe
Gas heats, and air cooler 7 is managed interior water temperature and reduced cooling, and cooling water is back to water water-to-water heat exchanger from down-comer 51
Continue to participate in heat exchange in 5 and discharge the work of system；The atmospheric density of air cooler 7 pipe external heat reduces, on
Rising, the hot air outlet 61 at warm air cooling tower 6 top enters air, and in insulation air cooling tower 6, pressure subtracts
Little, cold air enters from thermal-insulation cooling tower bottom inlet of cold air 62, participates in air cooler 7 heat exchange.
Condensing tube 22 is provided with two normally closed isolating valves in parallel, wherein the first isolating valve 23 be active every
From valve, manual unlocking when normal Residual heat removal, the second isolating valve 24 is passive isolating valve, is used for
Automatically opening up under emergency conditions, isolating valve downstream is provided with a check-valves 25；Time properly functioning, two every
From valve all in closed mode, under accident conditions or when normal shutdown needs to carry out Residual heat removal, often
Close passive valve or normally closed energy movable valve automatically opens up, possess active and passive advantage, security performance
More preferably.
Also include that constant pressure tank 8, tedge 52 are provided with described constant pressure tank 8；Constant pressure tank 8 is positioned at
The peak of system, the change in volume that variations in temperature causes in balanced loop are discharged in heat exchange, and provide
One stable operating pressure；Concrete, the expansion tube 81 of constant pressure tank 8 lower center position is communicated to
Tedge 52, proceeds to constant pressure tank 8 by the volume that water in heat exchange discharge system is increased because adding thermal expansion；
Constant pressure tank 8 bottom side is provided with circulation pipe 82, and circulation pipe 82 is communicated to tedge 52, at head water
When case 8 and expansion tube 81 are it may happen that freeze, it is used for making water circulate, the stability of raising constant pressure tank 8,
Reliability.
Further, also including water replanishing device, water replanishing device includes the first water supply tank 91 and the second water supply tank
92；Wherein, the first water supply tank 91 by pipeline communication to the main feed line 12 of steam generator 1,
On pipeline, parallel connection is provided with steam feed pump 93 and electrically driven feed pump 94, and this utility model is preferably with 2 50%
Electrically driven feed pump and the allocation plan of 2 50% steam feed pumps, 4 pumps are that parallel relationship is arranged, from
And improve the reliability of moisturizing, and disclosure satisfy that single failure criteria, even if there being a steam-operating feedwater
Pump and an electrically driven feed pump fault, nor affect on water charging system and normally work.
By the second water supply tank 92 described in ball-cock assembly pipeline connection in constant pressure tank 8, when in constant pressure tank 8
Water level less than designated water level time ball-cock assembly automatically open up water.
In heat-exchanging water tank 4, residual heat of nuclear core guiding system connecting line (as steam pipe 21, condensing tube 22,
Major steam line 11 etc.) and heat exchange discharge system connecting line (such as tedge 52, down-comer 51 etc.)
It is provided with temperature monitor (not indicating in figure), steam generator 1, heat-exchanging water tank 4 and constant pressure tank 8
Inside being provided with water level detection gauge (not indicating in figure), temperature monitor and water level detection gauge are the most wirelessly or non-wirelessly
It is connected to teletransmission controller (not indicating in figure), whole system is monitored.
In this utility model, water water-to-water heat exchanger and air cooler are preferably welded plate type heat exchanger, improve heat exchange effect
Rate.
This utility model possesses the advantage of passive equipment, is effectively improved security system reliability, by force
Change security system adaptibility to response under nuclear power plant accident operating mode, it is possible to effectively prevention is gentle solves serious thing
Therefore, reduce reactor core and melt probability and the risk probability of extensive radioactivity release, be greatly improved nuclear power station safety
Full performance.
This utility model reactor shutdown initial stage decay heat power is relatively big, and in heat-exchanging water tank the temperature of water is relatively
Low, a large amount of saturated vapors that steam generator produces can be condensed into saturation water；The reactor shutdown later stage
Steam production reduces, and in heat-exchanging water tank, the rising of coolant-temperature gage makes the heat exchange guiding system that heat-exchanging water tank connects
Heat exchange efficiency increase, natural-circulation capacity strengthens, it is ensured that the long-term cooling of heat exchanging water tank.
The above is only preferred implementation of the present utility model, it is noted that for the art
Those of ordinary skill for, on the premise of without departing from this utility model principle, it is also possible to make some
Improvements and modifications, these improvements and modifications also should be regarded as protection domain of the present utility model.
Claims (5)
1. a low-temperature nuclear heat supplying pile residual heat of nuclear core passive discharge system, it is characterized in that: include that system is discharged in residual heat of nuclear core guiding system and heat exchange, described residual heat of nuclear core guiding system includes that the heat exchanger being arranged in heat-exchanging water tank, heat exchanger inlets are respectively communicated with outlet and the import of steam generator with outlet；Being additionally provided with described heat exchange in heat-exchanging water tank and discharge the heat exchanger of system, the outlet of heat exchanger and import are respectively communicated to be arranged on import and the outlet of the air cooler in insulation air cooling tower；The inlet communication water replanishing device of described steam generator；
The import of described heat exchanger connects the major steam line of steam generator by steam pipe, and the outlet of heat exchanger connects the main feed line of steam generator by condensing tube, and the heat-exchanging water tank low inside that described heat exchanger is arranged on outside containment is put；
Described heat exchanger is water water-to-water heat exchanger, and water water-to-water heat exchanger is arranged on middle part or the top of heat-exchanging water tank；The import of water water-to-water heat exchanger connects the outlet of air cooler by down-comer, and the outlet of water water-to-water heat exchanger connects the import of air cooler by tedge；
Also including constant pressure tank, the expansion tube that constant pressure tank bottom center is arranged is communicated to tedge, and constant pressure tank bottom side is provided with circulation pipe, and circulation pipe is communicated to tedge；Constant pressure tank is positioned at heat exchange and discharges the peak of system；
Described water replanishing device includes the first water supply tank, and the first water supply tank is by pipeline communication to the main feed line of steam generator, and on this pipeline, parallel connection is provided with steam feed pump and electrically driven feed pump；
Steam feed pump in parallel on pipeline and electrically driven feed pump all at least 2.
Low-temperature nuclear heat supplying pile residual heat of nuclear core the most according to claim 1 passive discharge system, it is characterised in that: the top of described insulation air cooling tower is provided with hot air outlet, and the bottom of insulation air cooling tower is provided with inlet of cold air.
Low-temperature nuclear heat supplying pile residual heat of nuclear core the most according to claim 1 passive discharge system, it is characterized in that: condensing tube is provided with two normally closed isolating valves in parallel, wherein the first isolating valve is active isolating valve, and the second isolating valve is passive isolating valve, and isolating valve downstream is provided with a check-valves.
Low-temperature nuclear heat supplying pile residual heat of nuclear core the most according to claim 1 passive discharge system, it is characterised in that: described water replanishing device includes the second water supply tank, by the second water supply tank described in ball-cock assembly pipeline connection in described constant pressure tank.
5. according to the low-temperature nuclear heat supplying pile residual heat of nuclear core passive discharge system described in any one of claim 1-4, it is characterized in that: in heat-exchanging water tank, on the connecting line of residual heat of nuclear core guiding system and heat exchange is discharged and is equipped with temperature monitor on the connecting line of system, it is equipped with water level detection gauge, temperature monitor and water level detection gauge in steam generator, heat-exchanging water tank and constant pressure tank and is the most wirelessly or non-wirelessly connected to teletransmission controller.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201620055139.0U CN205656860U (en) | 2016-01-20 | 2016-01-20 | Active discharge system of reactor core waste heat non - is piled in heat supply of low temperature nuclear |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201620055139.0U CN205656860U (en) | 2016-01-20 | 2016-01-20 | Active discharge system of reactor core waste heat non - is piled in heat supply of low temperature nuclear |
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| CN205656860U true CN205656860U (en) | 2016-10-19 |
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Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106373622A (en) * | 2016-09-30 | 2017-02-01 | 中国核动力研究设计院 | Active-and-passive-fusion reactor-core waste-heat leading-out system |
| CN107393605A (en) * | 2017-07-07 | 2017-11-24 | 西安交通大学 | The passive air-cooling apparatus and method of a kind of modular small nuclear reactor |
| CN107403650A (en) * | 2017-08-25 | 2017-11-28 | 中国船舶重工集团公司第七〇九研究所 | The Passive residual heat removal system of floating nuclear power plant |
| CN107833641A (en) * | 2017-10-10 | 2018-03-23 | 中国船舶重工集团公司第七〇九研究所 | A kind of marine PWR seawater cools down Passive residual heat removal system |
| CN115240880A (en) * | 2022-08-01 | 2022-10-25 | 哈尔滨工程大学 | Passive residual heat removal system and method capable of achieving continuous heat removal |
-
2016
- 2016-01-20 CN CN201620055139.0U patent/CN205656860U/en active Active
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106373622A (en) * | 2016-09-30 | 2017-02-01 | 中国核动力研究设计院 | Active-and-passive-fusion reactor-core waste-heat leading-out system |
| CN107393605A (en) * | 2017-07-07 | 2017-11-24 | 西安交通大学 | The passive air-cooling apparatus and method of a kind of modular small nuclear reactor |
| CN107403650A (en) * | 2017-08-25 | 2017-11-28 | 中国船舶重工集团公司第七〇九研究所 | The Passive residual heat removal system of floating nuclear power plant |
| CN107403650B (en) * | 2017-08-25 | 2023-11-03 | 中国船舶重工集团公司第七一九研究所 | Secondary side passive waste heat discharging system of offshore floating nuclear power station |
| CN107833641A (en) * | 2017-10-10 | 2018-03-23 | 中国船舶重工集团公司第七〇九研究所 | A kind of marine PWR seawater cools down Passive residual heat removal system |
| CN115240880A (en) * | 2022-08-01 | 2022-10-25 | 哈尔滨工程大学 | Passive residual heat removal system and method capable of achieving continuous heat removal |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| TR01 | Transfer of patent right |
Effective date of registration: 20171129 Address after: 100085 A, No. 9, Third Street, Shanghai Haidian District, Beijing, 9 layer A1003-105 Patentee after: Kai Xin Xin nuclear (Beijing) Energy Technology Co., Ltd. Address before: 100193, Beijing, Haidian District, Zhongguancun northeast Beijing Software Park Incubator Building 2, block 2140-099, room B Patentee before: X-NUCLEAR (BEIJING) ENERGY TECH. CO., LTD. |
|
| TR01 | Transfer of patent right |