CN106297914A - A kind of passive high-temperature heat pipe fast reactor reactor core heat transfer system and method thereof - Google Patents
A kind of passive high-temperature heat pipe fast reactor reactor core heat transfer system and method thereof Download PDFInfo
- Publication number
- CN106297914A CN106297914A CN201610824344.3A CN201610824344A CN106297914A CN 106297914 A CN106297914 A CN 106297914A CN 201610824344 A CN201610824344 A CN 201610824344A CN 106297914 A CN106297914 A CN 106297914A
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- China
- Prior art keywords
- heat pipe
- heat
- fast reactor
- reactor
- liquid
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
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Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
- G21C15/04—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from fissile or breeder material
- G21C15/06—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from fissile or breeder material in fuel elements
-
- 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
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
- G21C15/14—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from headers; from joints in ducts
-
- 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 discloses a kind of passive high-temperature heat pipe fast reactor reactor core heat transfer system and method thereof；Fast reactor coolant reservoir, heat pipe and the steam generator of liquid is received including being loaded with；What the lower end of described heat pipe was placed in fast reactor coolant reservoir receives in liquid, and the upper end of heat pipe is placed in the water of steam generator；Placing response heap fuel assembly in fast reactor coolant reservoir, reactor fuel assemblies be submerged in receive liquid liquid level under.By sodium cooling agent and reactor fuel module enclosure, by heat pipe, steam generator is conducted heat, in heat pipe, inflatable is difficult to the hydrargyrum with water generation chemical reaction, lead, bismuth, stannum or its alloy as working medium, and sodium cooling agent is the most directly conducted heat with water, substantially increases security performance.According to hydrargyrum as heat-pipe working medium, owing to single heat pipe charging amount is little, even if heat pipe leakage does not results in direct security threat yet.
Description
Technical field
The present invention relates to heat transfer component and technique, particularly relate to a kind of passive high-temperature heat pipe fast reactor reactor core heat transfer system and
Its method.
Background technology
At present, in nuclear power station wide variety of presurized water reactor (such as Qinshan, Daya Bay nuclear power plant's heap-type of China) to natural
The utilization rate of uranium resource only about 1%, this utilization rate then can be brought up to 60%～70% by fast reactor.This is to making full use of uranium
Resource, promotes nuclear power sustainable development, solves alternative energy supply problem significant.Due to the raising of utilization rate, relatively
Leaner uranium ore there has also been extraction value.World wide is said, the resource that can adopt uranium so can be made to increase by thousand times.
For preventing moderation of neutrons, fast reactor can not use the material containing proton, therefore can not adopt and use water as coolant.
Proposing coolant at present has Liquid Sodium cooling and liquid lead bismuth alloy to cool down two schemes.Liquid metal coolant has preferably
Performance: have relatively low steam pressure in operating condition；High atomic number；Higher scattering section and less absorption cut
Face.But, both coolants there is also fatal defects.Wherein sodium cooling agent Lead coolant easily plays chemistry instead with air and water
Should, the safe operation to reactor causes grave danger；And lead bismuth coolant is at operating temperatures, rotten to the material of construction package
Lose the most serious.It addition, the pump power circulating heat conduction system used at present too increases the potential safety hazard of fast reactor nuclear power station.
Summary of the invention
It is an object of the invention to overcome the shortcoming and defect of above-mentioned prior art, it is provided that a kind of simple in construction, safety is high
The passive high-temperature heat pipe fast reactor reactor core heat transfer system of effect and method thereof.
The present invention is achieved through the following technical solutions:
A kind of passive high-temperature heat pipe fast reactor reactor core heat transfer system, receives the fast reactor coolant reservoir 7 of liquid, heat pipe including being loaded with
2 and steam generator 1；What the lower end of described heat pipe 2 was placed in fast reactor coolant reservoir 7 receives in liquid, and the upper end of heat pipe 2 is placed in steam
In the water of generator 1.
Placing response heap fuel assembly 3 in described fast reactor coolant reservoir 7, reactor fuel assemblies 3 is submerged in receives the liquid of liquid
Under face.
Described heat pipe 2 is many heat pipe arrays that are vertical and that be parallel to each other, be intervally arranged；Described steam generator 1 is positioned at
The top of fast reactor coolant reservoir 7.
The bottom sidewall of described steam generator is provided with water under high pressure import 6, and top is provided with steam (vapor) outlet 4；Reactor fuel
Heat released by assembly 3, and liquid is received in heating, and the working medium in the lower end of heat pipe 2 gasifies after being heated, the gas after gasification in heat pipe 2 to
Upper flowing, is discharged by steam (vapor) outlet 4 after adding the water in hot steam generator 1 and being vaporized, and the working medium in heat pipe 2 condenses again
And flow downward, complete a circulation.
The heat-transferring method of described passive high-temperature heat pipe fast reactor reactor core heat transfer system, comprises the steps:
Heat pipe 2 is in erectility, and receiving its lower end insertion fast reactor coolant reservoir 7 in liquid；Reactor fuel group
Part 3 releases heat, and liquid is received in heating；Now heat is transmitted by sodium liquid at fast reactor coolant reservoir 7 inside vortex convection current, the liquid of receiving after heating
To the lower end of heat pipe 2, gasify after now the working medium in heat pipe 2 is heated, the gas after gasification heat pipe 2 (in figure, heat transmission side
To 5) in flow to the upper end of heat pipe from bottom to top, and its heat is passed to the water in steam generator 1, makes steam generator
Discharged by steam (vapor) outlet 4 after water vapor in 1, it is achieved the working medium after heat exchange again condenses and flows to heat pipe from top to bottom 2 times
End, completes a circulation.
Described vortex convection current is, the middle part that sodium liquid is first gone to the bottom by fast reactor coolant reservoir 7 flows up, the most again by middle and upper part
To the peripheral Rolling flow of fast reactor coolant reservoir 7, after being cooled down by heat pipe 2, again flow to the middle part that fast reactor coolant reservoir 7 is gone to the bottom, with
This iterative cycles, it is achieved whole diabatic process does not use power set.
Described heat pipe 2 is divided into two rows, often arranges and is made up of a heat pipe row several heat pipes；Middle part in fast reactor coolant reservoir 7
Inserting control rod 8 from top to bottom, control rod 8 is positioned at the middle part of this two heat exhausting pipe, and two heat exhausting pipes are arranged in fast reactor coolant
The inward flange in pond 7.
The present invention, relative to prior art, has such advantages as and effect:
The deficiency existed based on prior art, the present invention passive high-temperature heat pipe fast reactor reactor core heat transfer system, do not use and appoint
What power-equipment, by sodium cooling agent and reactor fuel module enclosure, is conducted heat to steam generator by heat pipe, can in heat pipe
Fill hydrargyrum, lead, bismuth, stannum or its alloy being difficult to water generation chemical reaction the most directly to carry out as working medium, sodium cooling agent and water
Heat transfer, substantially increases security performance.According to hydrargyrum as heat-pipe working medium, owing to single heat pipe charging amount is little, even if heat pipe is let out
Leakage does not results in direct security threat yet.
Accompanying drawing explanation
Fig. 1 is the present invention passive high-temperature heat pipe fast reactor reactor core heat transfer system structural representation.
Fig. 2 is the present invention passive high-temperature heat pipe fast reactor reactor core heat transfer system application example schematic diagram.
Detailed description of the invention
Below in conjunction with specific embodiment, the present invention is more specifically described in detail.
Embodiment
As shown in Figure 1, 2.The invention discloses a kind of passive high-temperature heat pipe fast reactor reactor core heat transfer system, including being loaded with
Receive the fast reactor coolant reservoir 7 of liquid, heat pipe 2 and steam generator 1；The lower end of described heat pipe 2 is placed in the liquid of receiving of fast reactor coolant reservoir 7
In, the upper end of heat pipe 2 is placed in the water of steam generator 1.
Placing response heap fuel assembly 3 in described fast reactor coolant reservoir 7, reactor fuel assemblies 3 is submerged in receives the liquid of liquid
Under face.
Described heat pipe 2 is many heat pipe arrays that are vertical and that be parallel to each other, be intervally arranged；Described steam generator 1 is positioned at
The top of fast reactor coolant reservoir 7.
The bottom sidewall of described steam generator is provided with water under high pressure import 6, and top is provided with steam (vapor) outlet 4；Reactor fuel
Heat released by assembly 3, and liquid is received in heating, and the working medium in the lower end (cold end) of heat pipe 2 gasifies after being heated, and the gas after gasification is at heat pipe
Flow up in 2, discharged by steam (vapor) outlet 4, in heat pipe 2 after adding the water in hot steam generator 1 (water under high pressure) and being vaporized
Working medium again condense and flow downward, complete a circulation.
The heat-transferring method of described passive high-temperature heat pipe fast reactor reactor core heat transfer system, comprises the steps:
Heat pipe 2 is in erectility, and receiving its lower end insertion fast reactor coolant reservoir 7 in liquid；Reactor fuel group
Part 3 releases heat, and liquid is received in heating；Now heat is transmitted by sodium liquid at fast reactor coolant reservoir 7 inside vortex convection current, the liquid of receiving after heating
To the lower end (cold end) of heat pipe 2, after now the working medium in heat pipe 2 is heated gasify, the gas after gasification in heat pipe 2 from bottom to top
Flow to the upper end (hot junction) of heat pipe, and its heat is passed to the water in steam generator 1, make the water in steam generator 1
Discharged by steam (vapor) outlet 4 after vaporization, it is achieved the working medium after heat exchange again condenses and flows to the lower end of heat pipe 2 from top to bottom, completes
One circulation.
Described vortex convection current is, the middle part that sodium liquid is first gone to the bottom by fast reactor coolant reservoir 7 flows up, the most again by middle and upper part
To the peripheral Rolling flow of fast reactor coolant reservoir 7, after being cooled down by heat pipe 2, again flow to the middle part that fast reactor coolant reservoir 7 is gone to the bottom, with
This iterative cycles, it is achieved whole diabatic process does not use power set.
Described heat pipe 2 is divided into two rows, often arranges and is made up of a heat pipe row several heat pipes；Middle part in fast reactor coolant reservoir 7
Inserting control rod 8 from top to bottom, control rod 8 is positioned at the middle part of this two heat exhausting pipe, and two heat exhausting pipes are arranged in fast reactor coolant
The inward flange in pond 7.Control rod is a part for reactor fuel assemblies.
Steam generator, by sodium cooling agent and reactor fuel module enclosure, is conducted heat by the present invention by heat pipe, heat pipe
Interior inflatable is difficult to the hydrargyrum with water generation chemical reaction, lead, bismuth, stannum or its alloy as working medium, and sodium cooling agent is the most direct with water
Conduct heat, substantially increase security performance.Simultaneously as the charging amount of hot intraductal working medium is the least, therefore, working medium opposite heat tube
The melting corrosivity of wall is substantially reduced.According to hydrargyrum as heat-pipe working medium, owing to charging amount is little, even if heat pipe leakage also will not
Cause direct security threat.
As it has been described above, just can preferably realize the present invention.
Embodiments of the present invention are also not restricted to the described embodiments, other any spirit without departing from the present invention
With the change made under principle, modify, substitute, combine, simplify, all should be the substitute mode of equivalence, be included in the present invention's
Within protection domain.
Claims (8)
1. a passive high-temperature heat pipe fast reactor reactor core heat transfer system, it is characterised in that: include being loaded with and receive the fast reactor cooling of liquid
Agent pond (7), heat pipe (2) and steam generator (1)；What the lower end of described heat pipe (2) was placed in fast reactor coolant reservoir (7) receives in liquid,
The upper end of heat pipe (2) is placed in the water of steam generator (1).
The most passive high-temperature heat pipe fast reactor reactor core heat transfer system, it is characterised in that: described fast reactor cools down
Agent pond (7) interior placing response heap fuel assembly (3), reactor fuel assemblies (3) be submerged in receive liquid liquid level under.
Passive high-temperature heat pipe fast reactor reactor core heat transfer system the most according to claim 1 or claim 2, it is characterised in that: described heat pipe
(2) it is many heat pipe arrays that are vertical and that be parallel to each other, be intervally arranged；Described steam generator (1) is positioned at fast reactor coolant reservoir
(7) top.
The most passive high-temperature heat pipe fast reactor reactor core heat transfer system, it is characterised in that: described steam generation
The bottom sidewall of device is provided with water under high pressure import (6), and top is provided with steam (vapor) outlet (4)；Reactor fuel assemblies (3) releases heat,
Liquid is received in heating, and the working medium in the lower end of heat pipe (2) gasifies after being heated, and the gas after gasification flows up in heat pipe (2), heating
Water in steam generator (1) is also discharged by steam (vapor) outlet (4) after being vaporized, the working medium in heat pipe (2) again condense and to
Lower flowing, completes a circulation.
5. the heat-transferring method of passive high-temperature heat pipe fast reactor reactor core heat transfer system, its feature according to any one of Claims 1-4
It is to comprise the steps:
Heat pipe (2) is in erectility, and receiving its lower end insertion fast reactor coolant reservoir (7) in liquid；Reactor fuel group
Part (3) releases heat, and liquid is received in heating；Now sodium liquid is in fast reactor coolant reservoir (7) inside vortex convection current, receives liquid by heat after heating
Passing to the lower end of heat pipe (2), gasify after now the working medium in heat pipe (2) is heated, the gas after gasification is heat pipe (2) under oneself
Flow to the upper end of heat pipe on and, and its heat is passed to the water in steam generator (1), in making steam generator (1)
Discharged by steam (vapor) outlet (4) after water vapor, it is achieved the working medium after heat exchange again condenses and flows to from top to bottom under heat pipe (2)
End, completes a circulation.
The heat-transferring method of the most passive high-temperature heat pipe fast reactor reactor core heat transfer system, it is characterised in that institute
Stating vortex convection current is, the middle part that sodium liquid is first gone to the bottom by fast reactor coolant reservoir (7) flows up, cold to fast reactor by middle and upper part the most again
But the peripheral Rolling flow of agent pond (7), flows to the middle part that fast reactor coolant reservoir (7) is gone to the bottom, again with this after being cooled down by heat pipe (2)
Iterative cycles, it is achieved whole diabatic process does not use power set.
The heat-transferring method of the most passive high-temperature heat pipe fast reactor reactor core heat transfer system, it is characterised in that institute
State heat pipe (2) and be divided into two rows, often arrange and be made up of a heat pipe row several heat pipes；At the middle part of fast reactor coolant reservoir (7) from upper and
Lower insertion control rod (8), control rod (8) is positioned at the middle part of this two heat exhausting pipe, and two heat exhausting pipes are arranged in fast reactor coolant reservoir
(7) inward flange.
The heat-transferring method of the most passive high-temperature heat pipe fast reactor reactor core heat transfer system, it is characterised in that heat
Working medium in pipe (2) is hydrargyrum.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201610824344.3A CN106297914A (en) | 2016-09-14 | 2016-09-14 | A kind of passive high-temperature heat pipe fast reactor reactor core heat transfer system and method thereof |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201610824344.3A CN106297914A (en) | 2016-09-14 | 2016-09-14 | A kind of passive high-temperature heat pipe fast reactor reactor core heat transfer system and method thereof |
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| CN106297914A true CN106297914A (en) | 2017-01-04 |
Family
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| CN201610824344.3A Pending CN106297914A (en) | 2016-09-14 | 2016-09-14 | A kind of passive high-temperature heat pipe fast reactor reactor core heat transfer system and method thereof |
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Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106683720A (en) * | 2017-01-13 | 2017-05-17 | 中国核动力研究设计院 | Shell-and-tube lead base alloy cooling reactor |
| CN109817355A (en) * | 2018-12-29 | 2019-05-28 | 中核霞浦核电有限公司 | A kind of cylindrical body sodium-sodium-gas integrated heat exchanger |
| CN111341470A (en) * | 2020-03-14 | 2020-06-26 | 哈尔滨工程大学 | Nuclear steam supply system based on heat pipe heat transmission |
| CN111344806A (en) * | 2017-11-20 | 2020-06-26 | 泰拉能源公司 | Sodium-tin coolant and sodium-tin-lead coolant |
| CN111540489A (en) * | 2020-05-21 | 2020-08-14 | 哈尔滨工程大学 | Modular supercritical water cooling and heating pipe reactor system |
| CN113607820A (en) * | 2021-08-10 | 2021-11-05 | 温州大学 | Turbine rotor crack propagation on-site detection system under extreme working condition |
| CN117153435A (en) * | 2023-09-01 | 2023-12-01 | 华能核能技术研究院有限公司 | Heat pipe integrated high-temperature reactor |
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| CN206075830U (en) * | 2016-09-14 | 2017-04-05 | 华南理工大学 | A kind of passive high-temperature heat pipe fast reactor reactor core heat transfer system |
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Cited By (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106683720A (en) * | 2017-01-13 | 2017-05-17 | 中国核动力研究设计院 | Shell-and-tube lead base alloy cooling reactor |
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| CN111344806A (en) * | 2017-11-20 | 2020-06-26 | 泰拉能源公司 | Sodium-tin coolant and sodium-tin-lead coolant |
| CN109817355A (en) * | 2018-12-29 | 2019-05-28 | 中核霞浦核电有限公司 | A kind of cylindrical body sodium-sodium-gas integrated heat exchanger |
| CN111341470A (en) * | 2020-03-14 | 2020-06-26 | 哈尔滨工程大学 | Nuclear steam supply system based on heat pipe heat transmission |
| CN111540489A (en) * | 2020-05-21 | 2020-08-14 | 哈尔滨工程大学 | Modular supercritical water cooling and heating pipe reactor system |
| CN113607820A (en) * | 2021-08-10 | 2021-11-05 | 温州大学 | Turbine rotor crack propagation on-site detection system under extreme working condition |
| CN113607820B (en) * | 2021-08-10 | 2024-03-19 | 温州大学 | Turbine rotor crack propagation in-situ detection system under extreme working condition |
| CN117153435A (en) * | 2023-09-01 | 2023-12-01 | 华能核能技术研究院有限公司 | Heat pipe integrated high-temperature reactor |
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