CN105261401A - Passive residual heat removal system for liquid heavy metal cooled reactor in pool - Google Patents
Passive residual heat removal system for liquid heavy metal cooled reactor in pool Download PDFInfo
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- CN105261401A CN105261401A CN201510559216.6A CN201510559216A CN105261401A CN 105261401 A CN105261401 A CN 105261401A CN 201510559216 A CN201510559216 A CN 201510559216A CN 105261401 A CN105261401 A CN 105261401A
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- hot plate
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- 229910001385 heavy metal Inorganic materials 0.000 title claims abstract description 25
- 239000007788 liquid Substances 0.000 title claims abstract description 25
- 230000007423 decrease Effects 0.000 claims description 30
- 238000000926 separation method Methods 0.000 claims description 19
- 238000007599 discharging Methods 0.000 claims description 16
- 239000002826 coolant Substances 0.000 claims description 14
- 238000010438 heat treatment Methods 0.000 claims description 5
- 210000000481 breast Anatomy 0.000 claims description 3
- 239000000463 material Substances 0.000 claims description 3
- 239000012774 insulation material Substances 0.000 claims description 2
- 238000009413 insulation Methods 0.000 abstract 2
- 230000005484 gravity Effects 0.000 abstract 1
- 230000000630 rising effect Effects 0.000 abstract 1
- 238000001816 cooling Methods 0.000 description 16
- 230000008676 import Effects 0.000 description 2
- 230000001681 protective effect Effects 0.000 description 2
- 230000002159 abnormal effect Effects 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 229910052797 bismuth Inorganic materials 0.000 description 1
- JCXGWMGPZLAOME-UHFFFAOYSA-N bismuth atom Chemical compound [Bi] JCXGWMGPZLAOME-UHFFFAOYSA-N 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 230000000717 retained effect Effects 0.000 description 1
- 238000009423 ventilation Methods 0.000 description 1
- 239000002918 waste heat Substances 0.000 description 1
Classifications
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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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- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
Abstract
The invention discloses a passive residual heat removal system for a liquid heavy metal cooled reactor in a pool. The passive residual heat removal system for the liquid heavy metal cooled reactor in the pool is positioned in the pool of the liquid heavy metal cooled reactor; is installed in a gap among the insulation boards of cold pool inside, hot pool outside and reactor core outside of the liquid heavy metal cooled reactor; and mainly includes hot-air rising pipelines, cold-air down pipelines, cylindrical thermal insulation layers, chimneys and valves. The passive residual heat removal system can depend on natural air circulation to remove the residual heat of the reactor core without any external power supply, by using a passive mode of gravity-driven. The passive residual heat removal system for the liquid heavy metal cooled reactor in the pool can start instantaneously and has no need of human interference. Moreover, the system has simple equipment, large heat exchange area, high efficiency on removing heat of the reactor core, and can make the reactor maintain in a safe state.
Description
Technical field
The present invention relates to the technical field of discharging residual heat of nuclear core in pond under liquid heavy metal cooled reactor accident conditions, be specifically related to liquid heavy metal cooled reactor Heat Discharging System of Chinese in a kind of pond.
Background technology
Even if emergency shut-down under liquid heavy metal cooled reactor accident conditions, part of waste heat is still had to continue to produce.In order to ensure reactor operation safety, in pond liquid heavy metal cooled reactor be provided with a series of residual heat removal facility be used for discharge residual heat of nuclear core, as main heat exchanger cooling system, reactor vessel air cooling system etc.Such as main heat exchanger cooling system must could be opened thus cool reactor core under power drives, but when major accident and superposition thereof, when as station blackout, standby power supply all cannot use.This possibility needing the safety installations of Power supply often to there is inefficacy; therefore in the design of following reaction heap, often all adopt the passive safety system of similar reactor vessel air cooling system; namely do not rely on any external source, only rely on the safety that non-active mechanism protective reaction is piled.
Mostly adopt reactor vessel air cooling system as main Heat Discharging System of Chinese in existing liquid heavy metal cooled reactor design, reactor vessel air cooling system is positioned at outside safety container, the density difference relying on air self-temperature difference to cause completely drives hot-air upwards to flow, cooled reactor container, chilled reactor vessel reaches the object of cooling reactor core by cooling cold drop coolant temperature.Although reactor vessel air cooling system relies on air natural to circulate completely and takes away residual heat of nuclear core, do not need by external power source, but cooling medium charging capacity huge (about 600t) in liquid heavy metal cooled reactor in pond, reactor vessel air cooling system is used to rely on outside air cooled reactor primary tank, thus reach the object of cooling medium in cools stacks, which heat interchanging area is limited, and expend time in length, and efficiency is not high; In addition reactor vessel air cooling system is adopted to need, on the basis of original liquid heavy metal cooled reactor design, at the outside interpolation equipment of reactor vessel, to take up room large.
The invention provides and give another Heat Discharging System of Chinese of discharging residual heat of nuclear core; in the hot pond of liquid heavy metal cooled reactor, reactor core and cold drop dividing plate place increase air-cooling apparatus; equipment is simple to operation; residual heat of nuclear core can be taken away in time under accident conditions, thus the safety of protective reaction heap.Compared with mode in the past, possess equipment simple, take up room little and efficiency advantages of higher.
Summary of the invention
The technical problem to be solved in the present invention is the Heat Discharging System of Chinese of not discharging residual heat of nuclear core under a kind of accident conditions by any external power source system, the serious consequence that when avoiding reactor vessel to be damaged, residual heat of nuclear core can not be discharged in time simultaneously.
In order to solve the problem, technical scheme of the present invention is: liquid heavy metal cooled reactor Heat Discharging System of Chinese in a kind of pond, described system can not rely on any external power source efficiently to be discharged by residual heat of nuclear core, comprising: chimney, separation valve door, Re Chi, reactor vessel, cold drop, reactor core, hot-air increase in pipeline, cylindrical thermofin, hot pond lateral septal hot plate, cold air decline pipeline, cold drop medial septal hot plate and reactor core lateral septal hot plate; Wherein reactor core lateral septal hot plate is arranged in reactor core periphery, is connected with reactor core lateral septal hot plate, and leaves appropriate gap with cold drop medial septal hot plate; Form semi-enclosed hot diaphragm structure, hot pond lateral septal hot plate and reactor core lateral septal hot plate and cold drop medial septal hot plate bosom install cylindrical thermofin, keep certain distance between bottom cylindrical thermofin and bottom cold drop medial septal hot plate, and cylindrical thermofin is all identical with the distance of hot pond lateral septal hot plate, reactor core lateral septal hot plate and cold drop medial septal hot plate; Reactor core lateral septal hot plate adopts the good material of thermal conductivity, and hot pond lateral septal hot plate and cold drop medial septal hot plate all adopt thermal insulation material; Hot-air increase in pipeline and cold air decline pipeline lay respectively at the both sides of cylindrical thermofin, and what be positioned at cold drop medial septal hot plate side is cold air decline pipeline, and what be positioned at lateral septal hot plate side, hot pond is hot-air increase in pipeline; Hot-air increase in pipeline and cold air decline pipeline all extend to the outside of reactor vessel.Air after heating is directly flowed into chimney by hot-air increase in pipeline, enter air, and cold air decline pipeline is communicated with outside air.
Wherein, in hot-air increase in pipeline and cold air decline pipeline, respectively separation valve door is housed, separation valve door controls by main coolant system temperature in reactor vessel, during normal operation, separation valve door is in closed condition, due to Decay afterheat after shutdown, in reactor vessel, main coolant system temperature raises, and separation valve door is opened automatically.
Beneficial effect of the present invention: the present invention utilizes the design at hot dividing plate place, in conjunction with air cooling system, does not rely on any external power source, relies on air natural circulation to realize liquid heavy metal cooled reactor Heat Discharging System of Chinese in a kind of pond completely.Instant invention overcomes the shortcoming of existing program: 1) without the need to using any external power source and emergency service equipment; 2) without the need to additionally adding equipment in reactor vessel outside, minimizing takes up room; 3) passive residual heat removal device of the present invention is positioned at liquid heavy metal pond, substantially increases heat exchange efficiency; 4) once heap in-core coolant temperature occurs abnormal, automatically open by the temperature controlled valve of reactor vessel Main Coolant, outside air flows into device, can discharge residual heat of nuclear core timely and effectively, reduces accident harm.
Accompanying drawing explanation
Fig. 1 is liquid heavy metal cooled reactor Heat Discharging System of Chinese structural representation in a kind of pond of the present invention;
In figure, 1. chimney, 2. separation valve door, 3. cold drop, 4. reactor vessel, 5. cold drop, 6. reactor core, 7. hot-air increase in pipeline, 8. cylindrical thermofin, 9. hot pond lateral septal hot plate, 10. cold air decline pipeline, 11. cold drop medial septal hot plates, 12. reactor core lateral septal hot plates.
Embodiment
The present invention is further illustrated below in conjunction with accompanying drawing and specific embodiment.
A kind of liquid heavy metal cooled reactor Heat Discharging System of Chinese, this system comprises chimney 1, separation valve door 2, cold drop 3, reactor vessel 4, cold drop 5, reactor core 6, hot-air increase in pipeline 7, cylindrical thermofin 8, hot pond lateral septal hot plate 9, cold air decline pipeline 10, cold drop medial septal hot plate 11 and reactor core lateral septal hot plate 12.Hot pond lateral septal hot plate 9 is connected with reactor core lateral septal hot plate 12, and leaves appropriate gap with cold drop medial septal hot plate 11; Form semi-enclosed hot diaphragm structure, hot pond lateral septal hot plate 9 and reactor core lateral septal hot plate 12 install cylindrical thermofin 8 with cold drop medial septal hot plate 11 bosom, keep certain distance between bottom cylindrical thermofin 8 and bottom cold drop medial septal hot plate 11, and cylindrical thermofin 8 is all identical with the distance of hot pond lateral septal hot plate 9, reactor core lateral septal hot plate 12, cold drop medial septal hot plate 11.Hot-air increase in pipeline 7 and cold air decline pipeline 10 lay respectively at the both sides of cylindrical thermofin 8, and what be positioned at cold drop medial septal hot plate 11 side is cold air decline pipeline 10, and what be positioned at lateral septal hot plate 9 side, hot pond is hot-air increase in pipeline 7.Hot-air increase in pipeline 7 and cold air decline pipeline 10 all extend to the outside of reactor vessel 4.Air after heating is directly flowed into chimney 1 by hot-air increase in pipeline 7, enter air, and cold air decline pipeline 10 is communicated with outside air.
With hot-air increase in pipeline 7 and cold air decline pipeline 10, separation valve door 2 is housed respectively.Separation valve door 2 controls by main coolant system temperature in reactor vessel 4.During normal operation, separation valve door 2 is in closed condition, due to Decay afterheat after shutdown, in reactor vessel 4, main coolant system temperature raises, separation valve door 2 is opened automatically, outside air is entered by cold air decline pipeline 10, extraneous leaked-in air contacts with cold drop medial septal hot plate 11 with adiabatic cylindrical thermofin 8 at cold air decline pipeline 10, temperature remains unchanged substantially, hot-air increase in pipeline 7 is flowed into cold drop medial septal hot plate 11 bottom space through cylindrical thermofin 8, contact with reactor core lateral septal hot plate 12 bottom hot-air increase in pipeline 7 and heated, hot-air density after heating reduces, upwards flow into chimney 1.
With reference to liquid heavy metal cooled reactor in a typical pond, core power 100MW, its afterheat heat output is 1MW, and the total charging capacity of Main Coolant is 600 tons.Reactor core overall height is 6m, and chimney height is fixed as 15m; According to the design of reactor vessel air cooling system, when, number comparatively large at hot-air increase in pipeline and cold air decline pipe diameter is less, air velocity is little, imports and exports the temperature difference less, the natural convection air coefficient of heat transfer is comparatively large, makes the heat removal capacity of air less; At hot-air increase in pipeline and cold air decline pipe diameter is less, number is more time, air velocity is large, and import and export the temperature difference comparatively large, the natural convection air coefficient of heat transfer is less, makes the heat removal capacity of air less equally; Consider and choose optimum pipeline diameter and number and make the heat removal capacity of air reach best, choose 14cm based on hot-air increase in pipeline in this stillpot and cold air decline pipe diameter, number of conduits gets 72.
Under normal reactor operation operating mode, Main Coolant temperature is in normal range (300 ~ 385 DEG C), and the separation valve door of hot-air increase in pipeline and cold air decline pipeline is in closed condition, and pipeline has retained appropriate air.
When reactor is in accident conditions, Main Coolant temperature anomaly raises (being greater than 385 DEG C), exceed the setting valve of separation valve door, separation valve door is opened automatically, and outside air is entered by cold air decline pipeline, enters hot-air increase in pipeline through the bottom of decline pipeline, outside reactor core, hot dividing plate relies on heat radiation and heat transfer, make air just start to be heated in the bottom entering hot-air increase in pipeline, the air after heating rises and flows into chimney, enters air; Leaked-in air cooling reactor core lateral septal hot plate, thus reach the object of cooling reactor core, by calculating the temperature that can obtain reactor core lateral septal hot plate, temperature when judging whether it normally works higher than reactor core, thus judge that can apparatus of the present invention effectively discharge residual heat of nuclear core.
Illustrate (for bismuth cooled reactor plumbous in 100MW pond) with the enforcement parameter of instantiation
| Parameter | Unit | Numerical value |
| Residual heat of nuclear core | MW | 1 |
| Temperature of inlet air | ℃ | 50 |
| Pipe diameter | cm | 14 |
| Number of conduits | - | 40 |
| Air velocity in pipeline | m/s | 4.03 |
| MAF | kg/s | 3.79 |
| Volume of air flow | m 3/s | 4.47 |
| Air out medial temperature | ℃ | 313 |
| Average temperature of air | ℃ | 181.4 |
| The cross-ventilation coefficient of heat transfer | W/m 2K | 87 |
| Hot-air increase in pipeline wall surface temperature | ℃ | 233.9 |
| Cylindrical thermofin internal surface temperature | ℃ | 521.4 |
Claims (4)
1. liquid heavy metal cooled reactor Heat Discharging System of Chinese in a pond, it is characterized in that: described system can not rely on any external power source efficiently to be discharged by residual heat of nuclear core, comprising: chimney (1), separation valve door (2), hot pond (3), reactor vessel (4), cold drop (5), reactor core (6), hot-air increase in pipeline (7), cylindrical thermofin (8), hot pond lateral septal hot plate (9), cold air decline pipeline (10), cold drop medial septal hot plate (11) and reactor core lateral septal hot plate (12); Wherein reactor core lateral septal hot plate (12) is arranged in reactor core (6) periphery, and hot pond lateral septal hot plate (9) is positioned at periphery, hot pond (3) and is connected with reactor core lateral septal hot plate (12); Cold drop medial septal hot plate (11) is arranged on cold drop (5) inner side, from reactor core (6) bottom until reactor vessel (4) top, cold drop medial septal hot plate (11) and reactor core lateral septal hot plate (12), hot pond lateral septal hot plate (9) are suspended in cold drop (5) jointly, wherein reactor core lateral septal hot plate (12) adopts the good material of thermal conductivity, and hot pond lateral septal hot plate (9) and cold drop medial septal hot plate (11) adopt thermal insulation material; Hot pond lateral septal hot plate (9) is connected with reactor core lateral septal hot plate (12), and leaves appropriate gap with cold drop medial septal hot plate (11); Form semi-enclosed hot diaphragm structure, hot pond lateral septal hot plate (9) and reactor core lateral septal hot plate (12) and cold drop medial septal hot plate (11) bosom, cylindrical thermofin (8) is installed, keep certain distance between cylindrical thermofin (8) bottom and cold drop medial septal hot plate (11) bottom, and cylindrical thermofin (8) is all identical with the distance of cold drop medial septal hot plate (11) with hot pond lateral septal hot plate (9) and reactor core lateral septal hot plate (12); Hot-air increase in pipeline (7) and cold air decline pipeline (10) lay respectively at the both sides of cylindrical thermofin (8), what be positioned at cold drop medial septal hot plate (11) side is cold air decline pipeline (10), and what be positioned at lateral septal hot plate (9) side, hot pond is hot-air increase in pipeline (7); Hot-air increase in pipeline (7) and cold air decline pipeline (10) all extend to the outside of reactor vessel (4), air after heating is directly flowed into chimney (1) by hot-air increase in pipeline (7), enter air, and cold air decline pipeline (10) is communicated with outside air.
2. liquid heavy metal cooled reactor Heat Discharging System of Chinese in a kind of pond according to claim 1, it is characterized in that: at reactor core lateral septal hot plate (12), hot pond lateral septal hot plate (9) and cold drop medial septal hot plate (11) zone line install cylindrical thermofin (8), certain space will be left with cold drop medial septal hot plate (11) bottom in cylindrical thermofin (8) bottom, cylindrical thermofin (8) and hot pond lateral septal hot plate (9), cold air decline pipeline (10), cold drop medial septal hot plate (11), the gap thickness of reactor core lateral septal hot plate (12) is suitable, cylindrical thermofin (8) material is adiabatic.
3. liquid heavy metal cooled reactor Heat Discharging System of Chinese in a kind of pond according to claim 1, it is characterized in that: the hot-air increase in pipeline (7) that cylindrical thermofin (8) both sides are respectively and cold air decline pipeline (10), be divided into 4 groups, hot-air increase in pipeline (7) outlet directly communicates with chimney (1), the direct and contacting external air of cold air decline pipeline (10) entrance.
4. liquid heavy metal cooled reactor Heat Discharging System of Chinese in a kind of pond according to claim 1, it is characterized in that: with hot-air increase in pipeline (7) and cold air decline pipeline (10), separation valve door (2) is housed respectively, separation valve door (2) controls by the interior main coolant system temperature of reactor vessel (4), during normal operation, separation valve door (2) is in closed condition, due to Decay afterheat after shutdown, the interior main coolant system temperature of reactor vessel (4) raises, and separation valve door (2) is opened automatically.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201510559216.6A CN105261401B (en) | 2015-08-28 | 2015-08-28 | Liquid heavy metal cooled reactor Heat Discharging System of Chinese in a kind of pond |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201510559216.6A CN105261401B (en) | 2015-08-28 | 2015-08-28 | Liquid heavy metal cooled reactor Heat Discharging System of Chinese in a kind of pond |
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| CN105261401A true CN105261401A (en) | 2016-01-20 |
| CN105261401B CN105261401B (en) | 2017-07-11 |
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Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106653107A (en) * | 2016-09-26 | 2017-05-10 | 南华大学 | Passive decay heat removal system for liquid metal cooling pool type reactor |
| CN111899902A (en) * | 2020-09-08 | 2020-11-06 | 中国科学院合肥物质科学研究院 | Pool type reactor waste heat discharge system controlled by floating ball valve |
| CN112382420A (en) * | 2020-11-19 | 2021-02-19 | 中国核动力研究设计院 | Passive residual heat removal system based on water cooler |
| CN113140337A (en) * | 2021-03-05 | 2021-07-20 | 国科中子能(青岛)研究院有限公司 | Passive cooling system and method for multi-medium shared cooling channel and reactor |
| CN113421664A (en) * | 2021-06-23 | 2021-09-21 | 中国核动力研究设计院 | Lead-based fast reactor passive residual heat removal system based on containment and reactor vessel |
| CN113674881A (en) * | 2021-07-14 | 2021-11-19 | 中国核动力研究设计院 | Passive residual heat removal system for lead-bismuth reactor pressure vessel |
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| CN104269194A (en) * | 2014-10-13 | 2015-01-07 | 中国科学院合肥物质科学研究院 | Temperature-triggered passive accident residual heat removal system for pool type reactor |
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2015
- 2015-08-28 CN CN201510559216.6A patent/CN105261401B/en not_active Expired - Fee Related
Patent Citations (6)
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| US5043135A (en) * | 1989-05-18 | 1991-08-27 | General Electric Company | Method for passive cooling liquid metal cooled nuclear reactors, and system thereof |
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Cited By (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106653107A (en) * | 2016-09-26 | 2017-05-10 | 南华大学 | Passive decay heat removal system for liquid metal cooling pool type reactor |
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| CN112382420A (en) * | 2020-11-19 | 2021-02-19 | 中国核动力研究设计院 | Passive residual heat removal system based on water cooler |
| CN112382420B (en) * | 2020-11-19 | 2022-02-11 | 中国核动力研究设计院 | Passive residual heat removal system based on water cooler |
| CN113140337A (en) * | 2021-03-05 | 2021-07-20 | 国科中子能(青岛)研究院有限公司 | Passive cooling system and method for multi-medium shared cooling channel and reactor |
| CN113140337B (en) * | 2021-03-05 | 2023-09-15 | 国科中子能(青岛)研究院有限公司 | Passive cooling system, method and reactor for multi-medium shared cooling channel |
| CN113421664A (en) * | 2021-06-23 | 2021-09-21 | 中国核动力研究设计院 | Lead-based fast reactor passive residual heat removal system based on containment and reactor vessel |
| CN113674881A (en) * | 2021-07-14 | 2021-11-19 | 中国核动力研究设计院 | Passive residual heat removal system for lead-bismuth reactor pressure vessel |
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| CN105261401B (en) | 2017-07-11 |
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Granted publication date: 20170711 |