CN106816186A - A kind of Integrated PWR Heat Discharging System of Chinese based on separate heat pipe - Google Patents
A kind of Integrated PWR Heat Discharging System of Chinese based on separate heat pipe Download PDFInfo
- Publication number
- CN106816186A CN106816186A CN201710053771.0A CN201710053771A CN106816186A CN 106816186 A CN106816186 A CN 106816186A CN 201710053771 A CN201710053771 A CN 201710053771A CN 106816186 A CN106816186 A CN 106816186A
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- China
- Prior art keywords
- heat
- heat pipe
- heat exchanger
- cooling agent
- shell
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Classifications
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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 present invention provides a kind of Integrated PWR Heat Discharging System of Chinese based on separate heat pipe, including main coolant system, heat exchanger, heat pipe condenser section, passage is filled on main coolant system to be connected with the shell-side outlet of heat exchanger by cooling agent down-comer, passage is let out under main coolant system to be connected with the shell-side inlet of heat exchanger by cooling agent tedge, the evaporator section tube bank influent header of heat exchanger is connected by down-comer with the outlet header of heat pipe condenser section, the evaporator section tube bank outlet header of heat exchanger is connected by tedge with the influent header of heat pipe condenser section, heat pipe condenser section upper end is provided with relief valve, normally opened isolating valve is provided with cooling agent tedge, passive isolating valve is provided with cooling agent down-comer.The present invention is while system inherent safety is improved, it is ensured that isolation to reactor coolant, meet relatively long distance heat transfer demand and simplification system design.
Description
Technical field
The present invention relates to a kind of Integrated PWR Heat Discharging System of Chinese based on separate heat pipe, belong to nuclear power
Stand security technology area.
Background technology
Due to the generation of a large amount of waste heats such as decay heat, it is necessary to set special residual heat removal system after reactor shutdown
To ensure the discharge of residual heat of nuclear core, will otherwise cause the lasting rising of reservoir pressure and temperature, to the complete of pressure vessel
Whole property threatens.The residual heat removal system overwhelming majority that existing nuclear power station is set is active equipment, operationally needs outside
Equipment provides power, and this allows for the risk that remaining row's equipment has the loss of function when external power supply is lost, and reactor is pacified
Threaten entirely.
As the development of Nuclear Power Industry, integral reactor are safe because of its small volume, every country is all to it in spy
The application that such as ship power, ocean platform, island generate electricity under different environment is explored and verified.Integral reactor should
With environment often away from land, the space that device can be arranged is restricted, and this requires that the design of engineered safety system is ensureing
Inherent safety, less equipment size and the simplified structure design of system are improved while nuclear reactor safety.It is existing non-
Mainly for land commercial nuclear power plant, auxiliary equipment is more, and physical dimension is big, and system design is more for active residual heat removal system design
Complexity, is not suitable for the particular surroundings of integral reactor.In addition the cycle fluid of existing Heat Discharging System of Chinese exists
Keep single-phase in heat transfer process mostly, heat exchange efficiency is relatively low, it is necessary to the natural circulation flow of larger difference in height acquisition stabilization, makes
Obtain equipment size excessive.
Chinese patent:Heat-pipe radiator during for reactor emergency shut-down, reactor is arranged for land distributing, is adopted
With separate heat pipe as after reactor emergency shut-down to gas cooling in containment, using air as ultimate heat sink.And this
Patent is directed to integral reactor, reactor coolant is cooled down, using seawater as ultimate heat sink.
Chinese patent:Floating nuclear power plant Heat Discharging System of Chinese, floating nuclear power plant reactor is arranged for distributing,
Primary Ioops coolant system is joined directly together with seawater water tank, using seawater as ultimate heat sink.And this patent is anti-for integration
Heap is answered, the intermediate loop between coolant system and seawater is set up using separate heat pipe loop, it is ensured that cooling agent and seawater
Isolation.
Chinese patent:A kind of spentnuclear fuel pond passive residual heat guiding system and Chinese patent based on heat pipe:Based on water-cooled
The spentnuclear fuel passive residual heat guiding system of heat pipe, carries out passive residual heat removal, with air using heat pipe to spentnuclear fuel pond
As ultimate heat sink.And this patent is the residual heat removal system for integrated reacting shut-down system, with seawater as ultimate heat sink, pin
Object without directly contact, have very big difference in structure.
Chinese patent:Pressurized-water reactor nuclear power plant separate heat pipe formula Heat Discharging System of Chinese, for distributing arrangement
Land nuclear power station, steam generator is connected with the shell-side of heat pipe evaporator section, is passed heat by the phase-change heat-exchange in two loops
To ultimate heat sink air.And this patent is directed to integral reactor, coolant system is connected with separate heat pipe loop, by sea
Water as ultimate heat sink, reduce intermediate heat transfer loop and avoid because steam generator failure cause that waste heat cannot discharge can
Can property.
The content of the invention
The invention aims to provide a kind of Integrated PWR passive residual heat removal based on separate heat pipe
System, is a kind of with separate heat pipe as intermediate loop, for the Heat Discharging System of Chinese of Integrated PWR.
The object of the present invention is achieved like this:Including main coolant system, heat exchanger, heat pipe condenser section, main cooling
Passage is filled in agent system to be connected with the shell-side outlet of heat exchanger by cooling agent down-comer, lets out logical under main coolant system
Road is connected by cooling agent tedge with the shell-side inlet of heat exchanger, under the evaporator section tube bank influent header of heat exchanger passes through
Drop pipe is connected with the outlet header of heat pipe condenser section, and the evaporator section tube bank outlet header of heat exchanger passes through tedge and heat pipe cold
The influent header connection of solidifying section, heat pipe condenser section upper end is provided with relief valve, normally opened isolating valve is provided with cooling agent tedge,
Passive isolating valve is provided with cooling agent down-comer.
Present invention additionally comprises such some architectural features:
1. after the shell-side outlet outflow of cooling agent automatic heat-exchanger, flow through successively main coolant system on fill passage, cold
But agent down-comer, the pressure vessel descending branch of main coolant system, the reactor core passage of main coolant system, Main Coolant
The shell-side for entering heat exchanger after passage, cooling agent tedge is let out under pressure vessel ascent stage, the main coolant system of system
Entrance, forming closure waste heat derives loop one.
2. work medium for heat pipe flows through heat exchanger tube side, tedge, heat pipe condenser section tube side, down-comer, heat and hands over successively
Parallel operation tube side forms closure waste heat and derives loop two, and the work medium for heat pipe is a kind of heat-carrying working medium, including water or nanometer stream
Body.
3. heat exchanger described in is shell-and-tube heat exchanger, and shell fluid is cooling agent, and tube side fluid is that heat pipe work is situated between
Matter.
Compared with prior art, the beneficial effects of the invention are as follows:Of the present invention a kind of based on separate heat pipe one
Body presurized water reactor Heat Discharging System of Chinese, which employs separate heat pipe as in main coolant system and ultimate heat sink
Between heat transfer loop, by two phase flow Natural Circulation drive system, improve the inherent safety of system.Such design simultaneously is avoided
Cooling agent and seawater directly contact, are effectively ensured the shielding to cooling agent, on the other hand real in the case where small thermal resistance is introduced
Show the heat transfer of relatively long distance, simplified system design, reduce equipment size, it is special so as to meet Integrated PWR
The demand of applied environment.Namely the present invention is while system inherent safety is improved, it is ensured that isolation to reactor coolant,
Meet relatively long distance heat transfer demand and simplify system design.
Brief description of the drawings
Fig. 1 is structural representation of the invention.
Specific embodiment
The present invention is described in further detail with specific embodiment below in conjunction with the accompanying drawings.
A kind of Integrated PWR passive residual heat based on separate heat pipe of technical scheme as shown in Figure 1
Discharge system, including passive residual heat guiding system and separate heat pipe circuit system.
The coolant flow passage of the targeted integral reactor main coolant system of the present invention is main by reactor
Core passage 1, the cooling agent ascent stage 2, steam generator 5, cooling agent descending branch 6 are constituted, and mark 3 is empty steady pressure of system in accompanying drawing
Between.Passive residual heat guiding system also includes cooling agent tedge 12, passive residual heat removal heat exchange except main coolant system
Device (heat pipe evaporator section) 13 and cooling agent down-comer 11;Passive residual heat removal heat exchanger 13 is waste heat guiding system and heat pipe
Circuit system shared device;Separate heat pipe circuit system is by passive residual heat removal heat exchanger 13, tedge 15, separate type
Heat pipe condenser section 14 and down-comer 16 are constituted;The separate heat pipe condensation segment 14 is placed in seawater out of my cabin.
Passive residual heat removal heat exchanger 13 is shell-and-tube heat exchanger, and shell fluid is cooling agent, and tube side fluid is heat
Pipe working media;It is passive residual heat guiding system and heat pipe circuit system shared device, is placed in reactor cabin.Heat
The shell fluid of exchanger 13 is reactor coolant, and shell-side inlet under cooling agent tedge 12 and main coolant system 4 by letting out
Passage is connected;Shell-side outlet is connected by filling passage on cooling agent down-comer 11 and main coolant system 4.Heat exchanger 13 is managed
Side is separate heat pipe evaporator section, and evaporator section tube bank influent header 19 passes through down-comer 16 and the phase of 14 outlet header of condensation segment 20
Connection, evaporator section tube bank outlet header 18 is connected by tedge with the influent header 21 of condensation segment 14.Set on cooling agent tedge 12
Normally opened isolating valve 9, described cooling agent down-comer 11 is provided with passive isolating valve 10.
Described passive residual heat removal heat exchanger 13 is placed in reactor cabin, and height above sea level is high at shell-side outlet
In filling channel interface on down-comer 11 and Main Coolant;Described separate heat pipe condensation segment 14 is placed in seawater cabin out of my cabin
In, height above sea level is less than sea level, and the upper end of condensation segment 14 is equipped with relief valve 17.
Heat exchanger tube side is separate heat pipe evaporator section, and evaporator section is made up of multitubular bundles, under port air inlet-outlet-housing passes through
Drop pipe, tedge and condensation segment air inlet-outlet-housing are connected.
After Main Coolant flows out from the shell-side outlet of passive residual heat removal heat exchanger 13 in passive residual heat guiding system,
Flow through successively and passage, cooling agent down-comer 11, pressure vessel descending branch 6, reactor core passage 1 filled on main coolant system,
Passage, cooling agent tedge 12 is let out under the pressure vessel ascent stage 2, main coolant system to be formed into the shell-side inlet of heat exchanger 13
Closure waste heat derives loop one.Working media flows through the tube side of heat exchanger 13, tedge 15, heat successively in separate heat pipe loop
Pipework condensation section 14 and down-comer 16, return again to the tube side of heat exchanger 13, and forming closure waste heat derives loop two, work in heat pipe circuit
It is other heat-carrying working medium such as water or nano-fluid to make medium.
A kind of work of Integrated PWR Heat Discharging System of Chinese based on separate heat pipe of the present invention
Principle is:After integrated reacting shut-down system shutdown, main pump enters running down process to entirely off, and isolating valve 10 is automatically turned on, remaining
Hot discharge system comes into operation.Cooling agent flows into reactor core passage 1 and absorbs heat by lower head of pressure vessel, and temperature is raised, upwards
Motion being flowed through under pass through after the pressure vessel ascent stage 2 and lets out passage into cooling agent tedge 12, is then entered passive residual heat and is arranged
Go out the shell-side of heat exchanger 13.And the tube side of heat exchanger 13 is the evaporator section in separate heat pipe loop, into the shell of heat exchanger 13
The cooling agent of side is cooled, and flows downward, and is held into pressure by filling passage on main coolant system by cooling agent down-comer 11
Device descending branch 6, returns to lower head of pressure vessel, so forms Natural Circulation, is by residual heat of nuclear core transmission heat pipe circuit evaporator section
The tube side of heat exchanger 13.The tube side working media of heat exchanger 13 is moved upwards after absorbing heat of vaporization, into header 18, by upper
Riser 15 enters heat pipe circuit condensation segment 14.Working media is managed outer seawater condensing in condensation segment 14, is entered under gravity
Enter header 20, heat exchanger 13 is then returned to by down-comer 16, the waste heat for constituting closure derives loop.In the pipe of condensation segment 14
Outward, due to Absorption by Sea Water heat, motion forms convection current upwards, and residual heat of nuclear core is finally transmitted to seawater.
Present invention employs separate heat pipe as main coolant system and the intermediate heat transfer loop of ultimate heat sink, by close
Degree difference Natural Circulation drive system, improves the inherent safety of system.It is straight with seawater that such design simultaneously avoids cooling agent
Contact, is effectively ensured the shielding to cooling agent, and the heat of relatively long distance is on the other hand realized in the case where small thermal resistance is introduced
Amount transmission, simplifies system design, equipment size is reduced, so as to meet the demand of Integrated PWR application circumstances.
Claims (5)
1. a kind of Integrated PWR Heat Discharging System of Chinese based on separate heat pipe, it is characterised in that:It is cold including master
But agent system, heat exchanger, heat pipe condenser section, fill passage by cooling agent down-comer and heat exchanger on main coolant system
Shell-side outlet connection, passage is let out under main coolant system and is connected by the shell-side inlet of cooling agent tedge and heat exchanger
Connect, the evaporator section tube bank influent header of heat exchanger is connected by down-comer with the outlet header of heat pipe condenser section, heat exchanger
Evaporator section tube bank outlet header be connected with the influent header of heat pipe condenser section by tedge, heat pipe condenser section upper end is provided with
Relief valve, is provided with normally opened isolating valve on cooling agent tedge, passive isolating valve is provided with cooling agent down-comer.
2. a kind of Integrated PWR Heat Discharging System of Chinese based on separate heat pipe according to claim 1,
It is characterized in that:After the shell-side outlet outflow of cooling agent automatic heat-exchanger, flow through successively main coolant system on fill passage, cold
But agent down-comer, the pressure vessel descending branch of main coolant system, the reactor core passage of main coolant system, Main Coolant
The shell-side for entering heat exchanger after passage, cooling agent tedge is let out under pressure vessel ascent stage, the main coolant system of system
Entrance, forming closure waste heat derives loop one.
3. a kind of Integrated PWR passive residual heat removal system based on separate heat pipe according to claim 1 and 2
System, it is characterised in that:Work medium for heat pipe flow through successively heat exchanger tube side, tedge, heat pipe condenser section tube side, down-comer,
Heat exchanger tube side forms closure waste heat and derives loop two, and the work medium for heat pipe is a kind of heat-carrying working medium, including water or receives
Meter Liu Ti.
4. a kind of Integrated PWR passive residual heat removal system based on separate heat pipe according to claim 1 and 2
System, it is characterised in that:The heat exchanger is shell-and-tube heat exchanger, and shell fluid is cooling agent, and tube side fluid is heat pipe work
Make medium.
5. a kind of Integrated PWR Heat Discharging System of Chinese based on separate heat pipe according to claim 3,
It is characterized in that:The heat exchanger is shell-and-tube heat exchanger, and shell fluid is cooling agent, and tube side fluid is that heat pipe work is situated between
Matter.
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Cited By (16)
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CN107146925A (en) * | 2017-06-16 | 2017-09-08 | 苏州热工研究院有限公司 | The passive exhaust apparatus of battery compartment |
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 |
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 |
CN107833642A (en) * | 2017-10-10 | 2018-03-23 | 中国船舶重工集团公司第七〇九研究所 | Heat exchanger is located at the outer marine PWR Passive residual heat removal system of water tank |
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 |
CN108860552A (en) * | 2018-06-15 | 2018-11-23 | 中国船舶科学研究中心(中国船舶重工集团公司第七0二研究所) | A kind of passive salt water cooling system of outboard of underwater manned platform |
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 |
CN109273112A (en) * | 2018-09-13 | 2019-01-25 | 中国核动力研究设计院 | A kind of direct cooling passive residual heat removal system of anti-gravity direction flowing |
CN109841288A (en) * | 2019-04-09 | 2019-06-04 | 中国核动力研究设计院 | One kind being used for carbon dioxide cooled reactor residual heat removal system |
CN110211711A (en) * | 2019-05-31 | 2019-09-06 | 中国舰船研究设计中心 | A kind of Marine heat pipe type lead bismuth heap residual heat removal system |
CN110491533A (en) * | 2019-08-22 | 2019-11-22 | 哈尔滨工程大学 | A kind of double-deck cooling reactor core electricity generation system |
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 |
CN113689964A (en) * | 2021-08-30 | 2021-11-23 | 西安交通大学 | Main heat-waste heat integrated heat exchanger of small nuclear reactor |
CN113838587A (en) * | 2021-08-30 | 2021-12-24 | 西安交通大学 | Small-size villiaumite pile passive surplus row system based on integral type heat exchanger |
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CN104916334A (en) * | 2015-06-11 | 2015-09-16 | 哈尔滨工程大学 | Separated heat pipe type passive residual heat removal system for pressurized water reactor nuclear power plant |
CN104969301A (en) * | 2013-02-27 | 2015-10-07 | 西屋电气有限责任公司 | Pressurized water reactor depressurization system |
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US20130343504A1 (en) * | 2012-06-20 | 2013-12-26 | Korea Atomic Energy Research Institute | Heat exchanger for passive residual heat removal system |
CN104969301A (en) * | 2013-02-27 | 2015-10-07 | 西屋电气有限责任公司 | Pressurized water reactor depressurization system |
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CN107146925A (en) * | 2017-06-16 | 2017-09-08 | 苏州热工研究院有限公司 | The passive exhaust apparatus of battery compartment |
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 |
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 |
CN107833642A (en) * | 2017-10-10 | 2018-03-23 | 中国船舶重工集团公司第七〇九研究所 | Heat exchanger is located at the outer marine PWR Passive residual heat removal system of water tank |
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 |
CN108860552A (en) * | 2018-06-15 | 2018-11-23 | 中国船舶科学研究中心(中国船舶重工集团公司第七0二研究所) | A kind of passive salt water cooling system of outboard of underwater manned platform |
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 |
CN109273112A (en) * | 2018-09-13 | 2019-01-25 | 中国核动力研究设计院 | A kind of direct cooling passive residual heat removal system of anti-gravity direction flowing |
CN109273112B (en) * | 2018-09-13 | 2022-03-18 | 中国核动力研究设计院 | Direct cooling passive residual heat removal system capable of flowing in anti-gravity direction |
CN109841288B (en) * | 2019-04-09 | 2020-10-23 | 中国核动力研究设计院 | Be used for carbon dioxide cooling reactor waste heat discharge system |
CN109841288A (en) * | 2019-04-09 | 2019-06-04 | 中国核动力研究设计院 | One kind being used for carbon dioxide cooled reactor residual heat removal system |
CN110211711A (en) * | 2019-05-31 | 2019-09-06 | 中国舰船研究设计中心 | A kind of Marine heat pipe type lead bismuth heap residual heat removal system |
CN110491533A (en) * | 2019-08-22 | 2019-11-22 | 哈尔滨工程大学 | A kind of double-deck cooling reactor core electricity generation system |
CN110491533B (en) * | 2019-08-22 | 2022-02-22 | 哈尔滨工程大学 | Double-layer cooling reactor core power generation system |
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 |
CN113689964A (en) * | 2021-08-30 | 2021-11-23 | 西安交通大学 | Main heat-waste heat integrated heat exchanger of small nuclear reactor |
CN113838587A (en) * | 2021-08-30 | 2021-12-24 | 西安交通大学 | Small-size villiaumite pile passive surplus row system based on integral type heat exchanger |
CN113689964B (en) * | 2021-08-30 | 2022-12-09 | 西安交通大学 | Main heat-waste heat integrated heat exchanger of small nuclear reactor |
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Application publication date: 20170609 |