CN107767973B - Nuclear power plant spent fuel pool supplementary cooling device - Google Patents
Nuclear power plant spent fuel pool supplementary cooling device Download PDFInfo
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- CN107767973B CN107767973B CN201610692265.1A CN201610692265A CN107767973B CN 107767973 B CN107767973 B CN 107767973B CN 201610692265 A CN201610692265 A CN 201610692265A CN 107767973 B CN107767973 B CN 107767973B
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- spent fuel
- fuel pool
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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
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
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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
- G21C15/182—Emergency cooling arrangements; Removing shut-down heat comprising powered means, e.g. pumps
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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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- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention discloses a supplementary cooling device for a spent fuel pool of a nuclear power plant, which comprises a primary loop and a secondary loop, wherein the primary loop is positioned in a nuclear island plant, the secondary loop is positioned outside the nuclear island plant, spent pool water in the spent fuel pool can circularly flow in the primary loop, the primary loop transmits heat to the secondary loop through an intermediate heat exchanger, and fluid in the secondary loop discharges the heat through a cooling tower. Compared with the prior art, the invention limits the spent pool water in the nuclear island plant by the double-loop cold chain design, prevents radioactive substances from accidentally leaking outside the nuclear island plant, improves the safety and reliability of the device, obviously improves the cooling capacity of the spent fuel pool, adopts double-mode power supply, is additionally provided with an independent heat sink, and improves the emergency handling capacity of the spent fuel pool for power failure accidents and heat sink loss accidents of the whole plant.
Description
Technical Field
The invention belongs to the field of nuclear power, and particularly relates to a supplementary cooling device for a spent fuel pool of a nuclear power plant.
Background
The spent fuel pool in the nuclear power plant is used for storing spent fuel assemblies discharged from a reactor core in the previous refueling. The spent fuel assembly generates a certain decay heat in the spent fuel pool, the spent fuel pool cooling system is required to cool the spent fuel assembly, the temperature of water in the spent pool is maintained below a certain temperature, the equipment is prevented from being damaged due to overhigh temperature of the pool under a normal working condition, boiling of the water in the spent pool is inhibited under an accident working condition, and the water in the spent pool is prevented from being evaporated to dryness and the fuel assembly is exposed and melted to cause leakage of a large amount of radioactive substances.
In a pressurized water reactor nuclear power plant, a spent fuel pool cooling system is disclosed as shown in phantom in fig. 1, and consists of two rows of cooling subsystems, each row of subsystems containing 1 circulating cooling pump and 1 shell-and-tube heat exchanger. When the nuclear power plant is subjected to refueling and overhaul, the two cooling subsystems are put into operation, and the water temperature of the spent fuel pool is kept lower than a certain limit value. The technological configuration design standard of the spent fuel pool cooling system is as follows: the reactor takes 12 months as a refueling period, and 1/3 reactor core spent fuel assemblies are discharged into a spent fuel water pool each time of refueling.
However, with improvements in fuel management technology, nuclear power plant refueling models are upgraded to 18 month cycle refueling with the full core fuel assemblies dumped into the spent fuel pool each time the refueling occurs. Under the new refueling mode, the decay heat load of a fuel assembly in the spent fuel pool is higher, the cooling capacity of an original cooling system cannot meet the requirement of the new refueling mode, the nuclear power plant can only carry out refueling in winter with lower cooling water temperature (lower than a design reference temperature in a certain range), and the refueling operation strategy and the normal operation of the nuclear power plant are greatly influenced.
In addition, the heat discharge of the disclosed spent fuel pool cooling system depends on a cold chain of 'equipment cooling water/seawater', when the cold chain is unavailable due to equipment failure or the nuclear power plant is powered off, the spent fuel pool cooling is interrupted, and if the spent pool water is boiled for a long time, the internal sub-equipment of the spent fuel plant is damaged, and part of radioactive substances leak out, so that the personal safety of the public is affected.
In view of the above, there is a need for a nuclear power plant spent fuel pool supplementary cooling device that can solve the above problems.
Disclosure of Invention
The invention aims to: the defects of the prior art are overcome, and the nuclear power plant spent fuel pool supplementary cooling device with ideal cooling capacity and strong safety and reliability is provided.
In order to achieve the above purpose, the present invention provides a nuclear power plant spent fuel pool supplementary cooling device, which includes a primary loop inside a nuclear island plant and two loops outside the nuclear island plant, wherein spent pool water in the spent fuel pool can circulate in the primary loop, the primary loop transfers heat to the two loops through an intermediate heat exchanger, and fluid in the two loops discharges heat through a cooling tower.
As an improvement of the supplementary cooling device for the spent fuel pool of the nuclear power plant, except for the spent fuel pool, the fluids in other parts of the primary loop are in closed operation, and the two loops are closed loops.
As an improvement of the nuclear power plant spent fuel pool supplementary cooling device, all power equipment in the nuclear power plant spent fuel pool supplementary cooling device adopts a dual-mode power supply mode.
As an improvement of the nuclear power plant spent fuel pool supplementary cooling device, one of the two modes of power supply supplies power for the diesel generator.
As an improvement of the nuclear power plant spent fuel pool supplementary cooling device, the cooling tower is a reverse flow closed cooling tower.
As an improvement of the nuclear power plant spent fuel pool supplementary cooling device, the cooling tower comprises four small cooling towers, when the nuclear power plant spent fuel pool supplementary cooling device is operated, three small cooling towers are operated, and the other small cooling tower is reserved.
As an improvement of the nuclear power plant spent fuel pool supplementary cooling device, fluid in the two loops is conveyed through the two cooling pumps which are connected in parallel, when the nuclear power plant spent fuel pool supplementary cooling device operates, one cooling pump is put into operation, and the other cooling pump is in standby.
As an improvement of the nuclear power plant spent fuel pool supplementary cooling device, the intermediate heat exchanger is a plate heat exchanger.
As an improvement of the nuclear power plant spent fuel pool supplementary cooling device, a volume control surge tank is arranged in the two loops.
As an improvement of the supplementary cooling device for the spent fuel pool of the nuclear power plant, the fluid medium in the two loops is non-radioactive cooling water.
Compared with the prior art, the nuclear power plant spent fuel pool supplementary cooling device at least has the following technical effects:
(1) the cooling capacity of the spent fuel pool is remarkably improved, so that the nuclear power plant can meet the operation requirement of a fuel management mode characterized by taking 18-month-period refueling and unloading the fuel assemblies in the whole reactor core into the spent fuel pool during each refueling, and the normal operation of the nuclear power plant is ensured.
(2) The power equipment reserves an external diesel engine power supply interface, and when a nuclear power plant has a power outage accident, the spent fuel pool can be cooled normally, so that safety accidents caused by leakage of radioactive substances are prevented.
(3) The method is characterized in that the atmospheric environment is used as a hot trap to provide a new independent cold chain system for the spent fuel pool, and when the nuclear power plant has a hot trap loss accident, the spent fuel pool can be cooled normally, so that the safety accident caused by the leakage of radioactive substances is prevented.
(4) Through the design of the double-loop cold chain, the spent pool water is limited in the nuclear island plant, so that radioactive substances are prevented from being accidentally leaked outside the nuclear island plant, and the safety and reliability of the device are improved.
Drawings
The invention provides a nuclear power plant spent fuel pool supplementary cooling device and a beneficial technical effect thereof, which are described in detail with reference to the accompanying drawings and the specific implementation mode.
Fig. 1 is a schematic structural diagram of a nuclear power plant spent fuel pool supplementary cooling device of the present invention.
Detailed Description
In order to make the objects, technical solutions and technical effects of the present invention more clearly apparent, the present invention is further described in detail below with reference to the accompanying drawings and the detailed description. It should be understood that the detailed description and specific examples, while indicating the preferred embodiment of the invention, are intended for purposes of illustration only and are not intended to limit the scope of the invention.
Referring to fig. 1, a loop shown by a dotted line in fig. 1 is a disclosed nuclear power plant spent fuel pool cooling device, and a loop shown by a solid line is a nuclear power plant spent fuel pool supplementary cooling device according to the present invention.
The invention discloses a nuclear power plant spent fuel pool supplementary cooling device which comprises a primary loop and a secondary loop, wherein the primary loop is positioned in a nuclear island plant, the secondary loop is positioned outside the nuclear island plant, spent pool water in the spent fuel pool can flow in a circulating mode in the primary loop, the primary loop transmits heat to the secondary loop through an intermediate heat exchanger, and fluid in the secondary loop discharges the heat through a cooling tower.
The primary circuit comprises a primary circuit pipeline, a spent fuel pool, an intermediate heat exchanger and a primary circuit cooling pump. The spent fuel pool contains spent pool water with higher temperature. The intermediate heat exchanger is a plate heat exchanger. The spent fuel pool, the intermediate heat exchanger and the primary loop cooling pump are connected in series in a primary loop pipeline. The system comprises an intermediate heat exchanger and a primary loop cooling pump, wherein all power equipment in the primary loop adopts a dual-mode power supply mode, namely a nuclear power plant service power supply and an external emergency diesel generator power supply two-way power supply mode. The nuclear power plant station power supply is used during normal operation, and the external emergency diesel generator is used for supplying power when a power failure accident of the whole plant occurs, so that the flexibility of power supply and the independence of system operation are improved.
In the primary circuit, the spent fuel pool water is conveyed by a primary circuit cooling pump, flows through an intermediate heat exchanger, is cooled by fluid in the secondary circuit in the intermediate heat exchanger, is not merged with the disclosed cooling circuit, and directly returns to the spent fuel pool. The spent pool water is circulated for multiple times in the first loop, and the heat of the spent pool water is transferred to the fluid of the second loop. The spent pool water is in closed operation in other parts except the spent fuel pool in a loop, and the radioactive spent pool water is limited to flow in the nuclear island plant, so that radioactive substances are prevented from being discharged to the environment outside the nuclear island plant.
The second loop comprises a second loop pipeline, a cooling tower, a volume control fluctuation box and two parallel second loop cooling pumps. The cooling tower is a countercurrent closed cooling tower, spray water circulates outside a coil pipe of the cooling tower to absorb heat of fluid in the coil pipe, and the spray water is evaporated and finally transfers the heat to the atmospheric environment. The ventilation mode of the cooling tower is induced mechanical ventilation. The cooling tower adopts a 4 x 33% configuration mode, namely the cooling tower comprises four small cooling towers. When the cooling tower works normally, three small cooling towers are put into use, and the other small cooling tower is reserved. The capacity of two parallel two-loop cooling pumps is 2 multiplied by 100 percent. In normal operation, only one two-loop cooling pump is put into operation, and the other two-loop cooling pump is standby. The active equipment cooling tower and the cooling pump of the two loops are provided with redundant configuration, so that the overall equipment reliability of the cooling device can be enhanced, and the system availability is improved. The volume control surge tank is used for responding to the change of the fluid volume of the two circuits. The cooling tower, the volume control fluctuation box and the two parallel two-loop cooling pumps are connected in series in the two loops. The two circuits pass through an intermediate heat exchanger. The system comprises a cooling tower, a two-loop cooling pump and a volume control fluctuation box, wherein all power equipment in the two loops adopts a dual-mode power supply mode, namely a nuclear power plant service power supply and an external emergency diesel generator power supply two-way power supply mode. The nuclear power plant station power supply is used during normal operation, and the external emergency diesel generator is used for supplying power when a power failure accident of the whole plant occurs, so that the flexibility of power supply and the independence of system operation are improved.
In the two loops, the fluid receives the heat of the spent pool water and cools the spent pool water through the intermediate heat exchanger under the condition of not contacting with the spent pool water in the first loop, then the fluid enters a coil of a cooling tower under the conveying of a cooling pump in the two loops, and the cooling tower cools the hot fluid in the pipe through heat exchange modes such as water distribution evaporation, ventilation convection and the like on the outer surface of the coil. The fluid is circulated through the two circuits a number of times, the heat of which is ultimately transferred to the atmosphere. The fluid medium of the two loops is non-radioactive cooling water, and the two loops are closed loops and do not intersect with the first loop, so that radioactive substances cannot leak out of the nuclear island plant.
In combination with the above detailed description of the present invention, it can be seen that the beneficial technical effects of the supplemental cooling device for the spent fuel pool of the nuclear power plant of the present invention include, but are not limited to:
(1) through the design of the double-loop cold chain, the spent pool water is limited in the nuclear island plant, so that radioactive substances are prevented from being accidentally leaked outside the nuclear island plant, and the safety and reliability of the device are improved.
(2) The cooling capacity of the spent fuel pool is remarkably improved, so that the nuclear power plant can meet the operation requirement of a fuel management mode characterized by periodical refueling of 18 months and unloading of the fuel assemblies in the whole reactor core into the spent fuel pool during each refueling, and the normal operation of the nuclear power plant is ensured.
(3) The power equipment reserves an external diesel engine power supply interface, and when a nuclear power plant has a power outage accident, the spent fuel pool can be cooled normally, so that safety accidents caused by leakage of radioactive substances are prevented.
(4) The method is characterized in that the atmospheric environment is used as a hot trap to provide a new independent cold chain system for the spent fuel pool, and when the nuclear power plant has a hot trap loss accident, the spent fuel pool can be cooled normally, so that the safety accident caused by the leakage of radioactive substances is prevented.
The present invention can be modified and adapted appropriately from the above-described embodiments, according to the principles described above. Therefore, the present invention is not limited to the specific embodiments disclosed and described above, and some modifications and variations of the present invention should fall within the scope of the claims of the present invention. Furthermore, although specific terms are employed herein, they are used in a generic and descriptive sense only and not for purposes of limitation.
Claims (8)
1. The utility model provides a nuclear power plant spent fuel pond supplementary cooling device which characterized in that: the nuclear power plant spent fuel pool supplementary cooling device comprises a primary loop and a secondary loop, wherein the primary loop is positioned in a nuclear island plant, the secondary loop is positioned outside the nuclear island plant, spent pool water in the spent fuel pool can flow in a circulating mode in the primary loop, the primary loop conveys heat to the secondary loop through an intermediate heat exchanger, and fluid in the secondary loop discharges the heat through a cooling tower; all power equipment in the first loop and the second loop adopt a nuclear power plant service power supply and an external emergency diesel generator to supply power, the nuclear power plant service power supply is used for supplying power during normal operation, and the external emergency diesel generator is used for supplying power when a power failure accident of the whole plant occurs.
2. The nuclear power plant spent fuel pool supplemental cooling device of claim 1, wherein: except the spent fuel pool in the first loop, fluid in other parts of the first loop runs in a closed mode, and the two loops are closed loops.
3. The nuclear power plant spent fuel pool supplemental cooling device of claim 1, wherein: the cooling tower is a countercurrent closed cooling tower.
4. The nuclear power plant spent fuel pool supplemental cooling device according to claim 3, characterized in that: the cooling tower comprises four small cooling towers, when the nuclear power plant spent fuel water pool supplementary cooling device operates, three of the small cooling towers are put into operation, and the other small cooling tower is reserved.
5. The nuclear power plant spent fuel pool supplemental cooling device of claim 1, wherein: and fluid in the two loops is conveyed through the two cooling pumps connected in parallel, when the nuclear power plant spent fuel pool supplementary cooling device operates, one cooling pump is put into operation, and the other cooling pump is reserved.
6. The nuclear power plant spent fuel pool supplemental cooling device of claim 1, wherein: the intermediate heat exchanger is a plate heat exchanger.
7. The nuclear power plant spent fuel pool supplemental cooling device of claim 1, wherein: and a volume control fluctuation box is arranged in the two loops.
8. The nuclear power plant spent fuel pool supplemental cooling device of claim 1, wherein: the fluid medium in the two circuits is non-radioactive cooling water.
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| Application Number | Priority Date | Filing Date | Title |
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| CN201610692265.1A CN107767973B (en) | 2016-08-19 | 2016-08-19 | Nuclear power plant spent fuel pool supplementary cooling device |
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| CN201610692265.1A CN107767973B (en) | 2016-08-19 | 2016-08-19 | Nuclear power plant spent fuel pool supplementary cooling device |
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| CN107767973A CN107767973A (en) | 2018-03-06 |
| CN107767973B true CN107767973B (en) | 2020-05-05 |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN108492899B (en) * | 2018-03-29 | 2020-11-10 | 深圳中广核工程设计有限公司 | Movable emergency cooling device for spent fuel pool of nuclear power station |
| CN109524132B (en) * | 2018-10-12 | 2020-04-24 | 岭澳核电有限公司 | Control method and control system applied to spent fuel pool cooling branch |
| CN109599191A (en) * | 2018-10-16 | 2019-04-09 | 中国科学院合肥物质科学研究院 | A kind of cooling loop system based on Superconducting tokamak device |
| CN112361948B (en) * | 2020-10-29 | 2022-02-22 | 中国核动力研究设计院 | Heating device for simulating different temperature control of fuel rod-spent pool |
| CN113345608A (en) * | 2021-04-28 | 2021-09-03 | 中广核研究院有限公司 | Spent fuel pool cooling and purification system |
| CN113409968A (en) * | 2021-05-18 | 2021-09-17 | 中国核电工程有限公司 | Refrigerating system used under nuclear power plant heat sink loss working condition |
| CN113871044A (en) * | 2021-08-12 | 2021-12-31 | 中广核研究院有限公司 | Cooling control method and related equipment |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| US5488642A (en) * | 1994-08-22 | 1996-01-30 | Consolidated Edison Company Of New York, Inc. | Cooling system for spent fuel pool |
| CN102842349A (en) * | 2011-06-22 | 2012-12-26 | 上海核工程研究设计院 | Maintenance standby system for cooling water system of nuclear power plant |
| CN104347124A (en) * | 2013-07-26 | 2015-02-11 | 中广核工程有限公司 | Medium/long m term cooling system after nuclear-power-plant containment and spent fuel pool accident |
| CN105825900A (en) * | 2015-01-06 | 2016-08-03 | 中国科学院工程热物理研究所 | High-temperature liquid metal two-stage cooling device and method thereof |
| CN205177415U (en) * | 2015-11-06 | 2016-04-20 | 中广核工程有限公司 | Active heat pipe cooling system of spent fuel pool of nuclear power plant non - |
| CN205334971U (en) * | 2015-11-26 | 2016-06-22 | 中广核工程有限公司 | System for with weary pond of containment spraying system supplementary cooling |
| CN205211425U (en) * | 2015-12-03 | 2016-05-04 | 中广核工程有限公司 | Nuclear power station spent fuel pool cooling system |
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