CN104916334A - Separated heat pipe type passive residual heat removal system for pressurized water reactor nuclear power plant - Google Patents
Separated heat pipe type passive residual heat removal system for pressurized water reactor nuclear power plant Download PDFInfo
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- CN104916334A CN104916334A CN201510319596.6A CN201510319596A CN104916334A CN 104916334 A CN104916334 A CN 104916334A CN 201510319596 A CN201510319596 A CN 201510319596A CN 104916334 A CN104916334 A CN 104916334A
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- heat pipe
- heat
- pipe
- isolation valve
- air cooling
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Abstract
The invention aims at providing a separated heat pipe type passive residual heat removal system for a pressurized water reactor nuclear power plant. The system comprises a steam generator, a heat exchanger and an air cooling tower, wherein a main steam pipeline, a water supply pipeline and a pollution discharge hole are respectively arranged on the steam generator; a separated heat pipe evaporation section is arranged in the heat exchanger; the upper part of the separated heat pipe evaporation section is connected with the main steam pipeline by virtue of a steam pipe; the lower part of the separated heat pipe evaporation section is connected with the pollution discharge hole by virtue of a condenser pipe; a heat pipe condensation section is arranged in the air cooling tower; the inlet of the heat exchanger is connected with the outlet of the heat pipe condensation section by virtue of a down pipe; the outlet of the heat exchanger is connected with the inlet of the heat pipe condensation section by virtue of an ascension pipe; a cold air inlet is formed in the lower end of the air cooling tower; a hot air outlet is formed in the upper end of the air cooling tower; and a first isolating valve is arranged on the water supply pipeline. According to the system provided by the invention, the rapid cooling requirement at the initial accident stage and the long-term cooling requirement at the later accident stage are met, and relatively high heat exchange efficiency can be obtained.
Description
Technical field
What the present invention relates to is a kind of nuclear power station safety full device, specifically residual heat removal system.
Background technology
Due to the generation of a large amount of waste heats such as decay heat, after reactor shutdown, need to arrange special residual heat removal system to ensure the discharge of residual heat of nuclear core, otherwise the lasting rising of reservoir pressure and temperature will be caused, the integrality of pressure vessel is threatened.The residual heat removal system overwhelming majority that existing nuclear power station is arranged is active equipment, operationally needs external unit to provide power, and this just makes remaining row's equipment there is the risk of the loss of function when external power supply is lost, and threatens to reactor safety.
Along with the development of Nuclear Power Industry, substantially all have employed passive technology in the design of advanced nuclear power plant of new generation to improve the inherent safety of system.Passive safety system structure simply and not easily lost efficacy, relying on when putting into operation the inherent characteristic of system and the natural law to ensure the safety of reactor, not needing the supply of the judgement and extra power too relying on operations staff just can complete corresponding security function.Existing Heat Discharging System of Chinese design is mostly by realizing the function of Residual heat removal to the direct cooling of primary Ioops cooling medium, this Residual heat removal mode has obvious heat transfer effect, but the requirement of heat exchanger design is higher, adds the probability of primary Ioops radioactivity refrigerant leaks.In addition current is that the Heat Discharging System of Chinese circuit cycle working medium of ultimate heat sink great majority in operational process keep single-phase with air, heat exchange efficiency is lower, and need larger difference in height to obtain stable natural circulation flow, this problem such as heat transmission equipment all will be caused oversize.
Summary of the invention
The object of the present invention is to provide meeting while the accident initial stage cools fast and cool requirement for a long time with post incident, obtaining larger heat exchange efficiency and the pressurized-water reactor nuclear power plant separate heat pipe formula Heat Discharging System of Chinese compared with skinny device size.
The object of the present invention is achieved like this:
Pressurized-water reactor nuclear power plant separate heat pipe formula Heat Discharging System of Chinese of the present invention, it is characterized in that: comprise steam generator, heat interchanger, air cooling compressor, steam generator arranges main steam line respectively, feedwater piping, mudhole, separate heat pipe evaporator section is installed in heat interchanger, the top of separate heat pipe evaporator section is connected with main steam line by steam pipe, the below of separate heat pipe evaporator section is connected with mudhole by solidifying water pipe, in air cooling compressor, heat pipe condenser section is installed, the import of heat interchanger is connected with the outlet of heat pipe condenser section by downtake, the outlet of heat interchanger is connected with the import of heat pipe condenser section by tedge, the bottom of air cooling compressor is inlet of cold air, the upper end of air cooling compressor is hot air outlet, feedwater piping is arranged the first isolation valve.
The present invention can also comprise:
1, main steam line is arranged the second isolation valve often opened, solidifying water pipe arranges parallel connection and the 3rd normally closed isolation valve and the 4th isolation valve, 3rd isolation valve and the 4th in parallel solidifying water pipe between isolation valve and mudhole arranges non-return valve, heat pipe condenser section arranges relief valve.
2, the height above sea level of separate heat pipe condensation segment is higher than the height above sea level of heat pipe evaporator section.
Advantage of the present invention is:
1, Heat Discharging System of Chinese is connected to steam generator secondary side, ensure that the integrality on primary Ioops main cooling system border, the diffusion of radiomaterial under effective control emergency conditions;
2, passive residual heat removal Tube Sheet of Heat Exchanger side is separate heat pipe evaporator section, produces steam and directly cools, and form the larger temperature difference between ultimate heat sink obtaining stable circulation, taken out of in time by heat steam generator.
3, adopt separate heat pipe as intermediate loop, in heat pipe, the phase-change heat-exchange of working medium makes it have very high heat exchange efficiency, significantly reduces equipment size;
4, atmospheric environment is as ultimate heat sink, is finally entered in atmospheric environment by heat, meets the requirement of reactor needs cooling for a long time.
Accompanying drawing explanation
Fig. 1 is structural representation of the present invention.
Embodiment
Below in conjunction with accompanying drawing citing, the present invention is described in more detail:
Composition graphs 1, pressurized-water reactor nuclear power plant separate heat pipe formula Heat Discharging System of Chinese, comprise passive residual heat guiding system and separate heat pipe circuit system, described passive residual heat guiding system comprises steam pipe 5, passive residual heat removal heat interchanger 6 and solidifying water pipe 7; Described passive residual heat removal heat interchanger 6 is waste heat guiding system and heat pipe circuit system shared device; Described separate heat pipe circuit system by passive residual heat removal heat interchanger 6, tedge 13, separate heat pipe condensation segment 15 and downtake 16 form; Described separate heat pipe condensation segment 15 is positioned at chimney 17 bottom.
Described passive residual heat removal heat interchanger 6 is shell-and-tube heat exchanger, and be two system shared devices, heat interchanger shell-side is connected with jet chimney 5, and Tube Sheet of Heat Exchanger side is separate heat pipe evaporator section 12, and the height above sea level of shell-side outlet is a little less than the water level of steam generator 1.
Described steam pipe 5 is connected with bottom main steam line 2, is connected to passive residual heat removal heat interchanger 6 downwards along certain angle of inclination.
Described solidifying water pipe 7 is connected with steam generator blowdown hole 11, and solidifying water pipe 7 is provided with two normally closed isolation valves in parallel, and isolation valve 9 is active isolation valve, and isolation valve 8 is non-active isolation valve, and a non-return valve 10 is established in isolation valve downstream.
The import of described heat pipe evaporator section 12 is exported with heat pipe condenser section 15 by downtake 16 and is connected, and the outlet of heat pipe evaporator section 12 is connected with heat pipe condenser section 15 import by tedge 13.
Described separate heat pipe condensation segment 15 is arranged in air cooling compressor 17, and the height above sea level of separate heat pipe condensation segment 15 is higher than the height above sea level of heat pipe evaporator section 12.Relief valve 14 is equipped with in separate heat pipe condensation segment 15 upper end.
Described air cooling compressor 17 is positioned at containment outside, and air cooling compressor 17 bottom is inlet of cold air, and top is hot air outlet.
Described main steam line 2 is provided with the motor-operated isolation valve 3 often opened; Steam generator 1 feedwater piping is provided with the motor-operated isolation valve 4 often opened, and described isolation valve 3 and isolation valve 4 automatically should be able to be closed under emergency conditions.
In described non-active separate-type heat pipe system, the working medium of flowing is for meeting water or other heat-carrying working medium of boiling point needed for system works.
Pressurized-water reactor nuclear power plant Heat Discharging System of Chinese as shown in Figure 1, comprise passive residual heat guiding system and separate heat pipe circuit system, passive residual heat guiding system is by steam pipe 5, passive residual heat removal heat interchanger 6 and solidifying water pipe 7 form, passive residual heat removal heat interchanger 6 shell-side is connected with evaporator 1 secondary side, and import is connected with steam pipe 5; The height above sea level of shell-side outlet, a little less than the water level of steam generator 1, is connected with steam generator blowdown hole 11 by solidifying water pipe 7; Steam pipe 5 is connected with bottom main steam line 2, and is downward-slopingly connected to heat interchanger 6 shell-side inlet, prevents steam from condensing in pipe and blocking steam pipe; Solidifying water pipe 7 is provided with two normally closed isolation valves in parallel, and isolation valve 9 is active isolation valve, and for manual unlocking during normal Residual heat removal, isolation valve 8 is non-active isolation valve, and for automatically opening under emergency conditions, isolation valve downstream is provided with a non-return valve 10; Main steam line 2 is provided with the motor-operated isolation valve 3 often opened, and steam generator 1 feedwater piping is provided with the motor-operated isolation valve 4 often opened, and isolation valve 3 and isolation valve 4 automatically should be able to be closed under emergency conditions.
Separate heat pipe circuit system by separate heat pipe evaporator section 12, tedge 13, heat pipe condenser section 15 and downtake 16 form; The import of heat pipe evaporator section 12 is exported with heat pipe condenser section 15 by downtake 16 and is connected, and the outlet of heat pipe evaporator section 12 is connected with heat pipe condenser section 15 import by tedge 13, forms separate heat pipe loop and enters in atmospheric environment by the heat in water tank; Air cooling compressor 17 is positioned at containment outside, and bottom is inlet of cold air, and top is hot air outlet; In separate heat pipe circuit system, the working medium of flowing is water or other heat-carrying working medium.
During normal operation, two the solidifying water segregation valves 8,9 connecting residual heat removal system outlet are all in closed condition, passive residual heat removal is full of water in loop, has certain water level in jet chimney 5, and steam can only be flowed to secondary coolant circuit system by main steam pipe 3; Flow is not had in heat pipe circuit; Air mass flow in air cooling compressor 17 is almost nil.
Under accident conditions or when normal shutdown needs to carry out Residual heat removal, often open main feed valve door 4 and main steam valve 3 is closed automatically, connecting the normally closed non-of passive residual heat removal heat interchanger 6 can movable valve 8 or normally closedly to open by movable valve 9.Cold water in residual heat removal system flows into steam generator secondary side by steam generator blowdown hole 11 under gravity, and steam enters condensation in passive residual heat removal heat interchanger 6 by steam pipe 5.Because the height above sea level of solidifying water chamber is lower than steam generator water level, so a stable water level can be formed during stable operation in passive residual heat removal heat interchanger 6 shell-side.Along with increasing of condensate water, when the water level of condensate water in heat interchanger 6 shell-side is higher than steam generator water level, condensate water flows into steam generator secondary side through solidifying water pipe under the effect of height of water level difference, enter passive residual heat removal heat interchanger 6 under the suction function that steam in steam generator produces at passive residual heat removal heat interchanger 6 shell-side steam-condensation, so form the circulation in carbonated drink loop.Due to the cooling effect of steam generator 1, primary side of steam generator outlet coolant temperature reduces, and primary Ioops cooling medium moves at the flows by action of Natural Circulation density difference, is derived by reactor waste.
Vacuum state is in before being taken into use in separate heat pipe, heat-transfer working medium in heat pipe circuit evaporator section 12 absorbs the heat of the steam-condensation release produced by evaporator, evaporation or boiling occur, and the steam of generation enters heat pipe condenser section 15 by tedge 13 due to buoyancy lift.Condensation segment 15 is by the cooling release heat of pipe outer air, and gaseous working medium generation condensation in heat pipe, condensation working medium is got back in evaporator section heat interchanger 15 by downtake 16, thus heat pipe circuit forms stable Natural Circulation.Air enters along cooling tower 17 bottom inlet, and heated outside air cooled heat exchanger pipe, density diminishes and buoyance lift, and hot-air is flowed out by cooling tower 17 upper outlet.Heat imports in atmospheric environment the most at last.
Because diabatic process in heat pipe is along with boiling and the phase transition process of condensation, therefore system has very large heat exchange efficiency.Reactor shutdown initial stage decay heat power is comparatively large, and separate heat pipe starts fast and working temperature is stable, and in it, working medium keeps state of saturation, can get rid of heat in time; Reactor shutdown later stage waste heat reduces, separate heat pipe still can stable operation under the less temperature difference, ensures the discharge of preheating, under this external discharge waste heat condition, significantly can reduce equipment size because separate heat pipe has higher heat exchange efficiency, optimize reactor and arrange.
Claims (3)
1. pressurized-water reactor nuclear power plant separate heat pipe formula Heat Discharging System of Chinese, it is characterized in that: comprise steam generator, heat interchanger, air cooling compressor, steam generator arranges main steam line respectively, feedwater piping, mudhole, separate heat pipe evaporator section is installed in heat interchanger, the top of separate heat pipe evaporator section is connected with main steam line by steam pipe, the below of separate heat pipe evaporator section is connected with mudhole by solidifying water pipe, in air cooling compressor, heat pipe condenser section is installed, the import of heat interchanger is connected with the outlet of heat pipe condenser section by downtake, the outlet of heat interchanger is connected with the import of heat pipe condenser section by tedge, the bottom of air cooling compressor is inlet of cold air, the upper end of air cooling compressor is hot air outlet, feedwater piping is arranged the first isolation valve.
2. pressurized-water reactor nuclear power plant separate heat pipe formula Heat Discharging System of Chinese according to claim 1, it is characterized in that: main steam line is arranged the second isolation valve often opened, solidifying water pipe arranges parallel connection and the 3rd normally closed isolation valve and the 4th isolation valve, 3rd isolation valve and the 4th in parallel solidifying water pipe between isolation valve and mudhole arranges non-return valve, heat pipe condenser section arranges relief valve.
3. pressurized-water reactor nuclear power plant separate heat pipe formula Heat Discharging System of Chinese according to claim 1 and 2, is characterized in that: the height above sea level of separate heat pipe condensation segment is higher than the height above sea level of heat pipe evaporator section.
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| CN201510319596.6A CN104916334A (en) | 2015-06-11 | 2015-06-11 | Separated heat pipe type passive residual heat removal system for pressurized water reactor nuclear power plant |
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| CN201510319596.6A CN104916334A (en) | 2015-06-11 | 2015-06-11 | Separated heat pipe type passive residual heat removal system for pressurized water reactor nuclear power plant |
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Cited By (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105608979A (en) * | 2016-02-23 | 2016-05-25 | 中广核研究院有限公司 | Test device for simulating steam generator secondary side waste heat exhaust system and method |
| CN106816186A (en) * | 2017-01-24 | 2017-06-09 | 哈尔滨工程大学 | A kind of Integrated PWR Heat Discharging System of Chinese based on separate heat pipe |
| CN107068215A (en) * | 2017-02-09 | 2017-08-18 | 中科瑞华原子能源技术有限公司 | A kind of Heat Discharging System of Chinese and nuclear power system based on heat pipe heat exchanging |
| CN108615566A (en) * | 2018-06-14 | 2018-10-02 | 华南理工大学 | A kind of small cores reactor heat transport system cooled down using circuit parallel heatpipe |
| CN109099736A (en) * | 2018-07-23 | 2018-12-28 | 华信咨询设计研究院有限公司 | A kind of gravity heat pipe heat exchanger used for cooling tower |
| CN109273113A (en) * | 2018-09-13 | 2019-01-25 | 中国核动力研究设计院 | A kind of heat pipe-type passive residual heat removal system cooling based on seawater |
| CN109273114A (en) * | 2018-09-13 | 2019-01-25 | 中国核动力研究设计院 | One kind being based on the air cooled heat pipe-type passive residual heat removal system in deck |
| CN110957055A (en) * | 2019-10-09 | 2020-04-03 | 中国核电工程有限公司 | Separated flexible heat pipe cooling system suitable for pressurized water reactor nuclear power station |
| CN111785399A (en) * | 2020-07-06 | 2020-10-16 | 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) | System for heat export of marine nuclear power platform |
| 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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Cited By (16)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105608979B (en) * | 2016-02-23 | 2019-11-15 | 中广核研究院有限公司 | The experimental rig and method of model steam generator secondary side residual heat removal system |
| CN105608979A (en) * | 2016-02-23 | 2016-05-25 | 中广核研究院有限公司 | Test device for simulating steam generator secondary side waste heat exhaust system and method |
| CN106816186A (en) * | 2017-01-24 | 2017-06-09 | 哈尔滨工程大学 | A kind of Integrated PWR Heat Discharging System of Chinese based on separate heat pipe |
| CN107068215A (en) * | 2017-02-09 | 2017-08-18 | 中科瑞华原子能源技术有限公司 | A kind of Heat Discharging System of Chinese and nuclear power system based on heat pipe heat exchanging |
| CN107068215B (en) * | 2017-02-09 | 2018-07-24 | 中科瑞华原子能源技术有限公司 | A kind of passive residual heat removal system and nuclear power system based on heat pipe heat exchanging |
| CN108615566A (en) * | 2018-06-14 | 2018-10-02 | 华南理工大学 | A kind of small cores reactor heat transport system cooled down using circuit parallel heatpipe |
| CN108615566B (en) * | 2018-06-14 | 2023-08-18 | 华南理工大学 | Small nuclear reactor heat transmission system cooled by loop parallel heat pipes |
| CN109099736A (en) * | 2018-07-23 | 2018-12-28 | 华信咨询设计研究院有限公司 | A kind of gravity heat pipe heat exchanger used for cooling tower |
| CN109273113A (en) * | 2018-09-13 | 2019-01-25 | 中国核动力研究设计院 | A kind of heat pipe-type passive residual heat removal system cooling based on seawater |
| CN109273114A (en) * | 2018-09-13 | 2019-01-25 | 中国核动力研究设计院 | One kind being based on the air cooled heat pipe-type passive residual heat removal system in deck |
| CN110957055A (en) * | 2019-10-09 | 2020-04-03 | 中国核电工程有限公司 | Separated flexible heat pipe cooling system suitable for pressurized water reactor nuclear power station |
| CN110957055B (en) * | 2019-10-09 | 2022-11-25 | 中国核电工程有限公司 | Separated flexible heat pipe cooling system suitable for pressurized water reactor nuclear power station |
| CN111785399A (en) * | 2020-07-06 | 2020-10-16 | 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) | System for heat export of marine nuclear power platform |
| CN111785399B (en) * | 2020-07-06 | 2023-06-20 | 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) | System for be used for ocean nuclear power platform heat to derive |
| 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 |
| CN115240880B (en) * | 2022-08-01 | 2023-04-07 | 哈尔滨工程大学 | Passive residual heat removal system and method capable of achieving continuous heat removal |
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