CN110274501B - Nuclear power plant spent fuel pool cooling system based on passive separation type heat pipe exchanger - Google Patents
Nuclear power plant spent fuel pool cooling system based on passive separation type heat pipe exchanger Download PDFInfo
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- CN110274501B CN110274501B CN201910437832.2A CN201910437832A CN110274501B CN 110274501 B CN110274501 B CN 110274501B CN 201910437832 A CN201910437832 A CN 201910437832A CN 110274501 B CN110274501 B CN 110274501B
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- cooling
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- pipe
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F28—HEAT EXCHANGE IN GENERAL
- F28D—HEAT-EXCHANGE APPARATUS, NOT PROVIDED FOR IN ANOTHER SUBCLASS, IN WHICH THE HEAT-EXCHANGE MEDIA DO NOT COME INTO DIRECT CONTACT
- F28D15/00—Heat-exchange apparatus with the intermediate heat-transfer medium in closed tubes passing into or through the conduit walls ; Heat-exchange apparatus employing intermediate heat-transfer medium or bodies
- F28D15/02—Heat-exchange apparatus with the intermediate heat-transfer medium in closed tubes passing into or through the conduit walls ; Heat-exchange apparatus employing intermediate heat-transfer medium or bodies in which the medium condenses and evaporates, e.g. heat pipes
- F28D15/0266—Heat-exchange apparatus with the intermediate heat-transfer medium in closed tubes passing into or through the conduit walls ; Heat-exchange apparatus employing intermediate heat-transfer medium or bodies in which the medium condenses and evaporates, e.g. heat pipes with separate evaporating and condensing chambers connected by at least one conduit; Loop-type heat pipes; with multiple or common evaporating or condensing chambers
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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
Abstract
The invention relates to a nuclear power plant spent fuel pool cooling system based on a passive separation type heat pipe exchanger, which comprises a heat pipe group, a cold pipe section liquid phase region and an air-cooled pipe section, wherein the heat pipe group is connected with the cold pipe section liquid phase region; the heat pipe group is arranged in the spent fuel pool and is connected with the liquid phase region of the cold pipe section to form a natural circulation pipe section; one end of the air cooling pipe section is connected with the heat pipe group, and the other end of the air cooling pipe section is connected with the liquid phase region of the cold pipe section. The beneficial effects of the invention are as follows: the separated heat pipe is used for cooling the spent fuel assembly, so that the efficiency is high; the cooling system takes nano fluid as a coolant, and is designed with a natural circulation loop to maintain the dispersibility of the nano fluid, so that the heat transfer efficiency is greatly increased while the low-pressure boiling heat exchange is realized, and the cooling heat exchange is facilitated.
Description
Technical Field
The invention belongs to the field of design of spent fuel pool cooling systems of nuclear power plants, and particularly relates to a spent fuel pool cooling system of a nuclear power plant based on a passive separation type heat pipe exchanger.
Background
According to past experience, the nuclear industry has always set the risk of serious accidents of the spent fuel pool to be extremely small, and the importance of the safety of the spent fuel pool in the design process of the spent fuel pool is far smaller than that of a reactor. However, the 2011 japanese foodland nuclear accident suggests that it is necessary to strengthen the ability of the spent fuel pool to prevent external events, so as to ensure safe cooling of the spent fuel pool in the event of a full plant outage and in the event of an off-plant rescue failure, thereby preventing the escape of radioactive products.
At present, the existing spent fuel pool matched with the fuel factory of the nuclear power station mostly adopts active cooling, and takes the external air cooling or water cooling as a final hot well. The spent fuel pool is internally provided with spent fuel assemblies stored in racks, and one rack can store a plurality of groups of fuel assemblies (30-36 for reference, 49 for example) and the racks are arranged in a partitioned manner and cooled by cooling water in the pool. However, under the serious accident condition, the whole plant is very likely to be powered off, the standby power supply is generally used for emergency shutdown of the reactor, primary loop cooling and residual heat removal of the reactor, and the cooling and heat dissipation requirements of a spent fuel pool are hardly met, so that great potential safety hazards are caused. In response to this problem, the industry has developed a series of studies such as: a spent fuel pool cooling and purification system (CN 103021487B) designed to take into account both active and passive technologies; in addition, a great number of scholars are striving to promote the spent fuel pool cooling technology, and among a plurality of technical means, the utilization of the heat pipe cooling technology is attracting a great deal of attention, for example, a split type heat pipe heat exchanger (CN 104457349A) utilizes the low-pressure boiling heat exchange characteristic of a heat pipe to strengthen heat transfer cooling.
In the nuclear energy field, heat pipe technology application research has made preliminary progress, such as: an integrated pressurized water reactor passive waste heat discharge system (CN 106816186A) based on a separated heat pipe uses the heat pipe to strengthen heat exchange, and adopts a shell-and-tube heat exchanger to take the separated heat pipe as an intermediate heat transfer loop of a main coolant system and a final heat trap; the multi-stage long-distance passive heat pipe cooling system (CN 106653106A) of the spent fuel pool of the nuclear power plant is provided with an initial heat conduction link and at least one final heat conduction link, and is cooled step by utilizing heat pipe cooling heat exchange, so that long-distance efficient cooling is realized; a nuclear power plant floating type spent fuel pool passive cooling device and system (CN 105006258B) utilizes a grid to enable a heat exchange tube group to float on the liquid level of a spent fuel pool, and greatly improves heat exchange capacity by increasing heat exchange area.
However, the heat exchange performance of the existing heat exchange mode cannot meet the ideal requirement.
In view of this, the present invention has been made.
Disclosure of Invention
Aiming at the defects in the prior art, the invention aims to provide a nuclear power plant spent fuel pool cooling system based on a passive separation type heat pipe heat exchanger.
The technical scheme of the invention is as follows:
a nuclear power plant spent fuel pool cooling system based on a passive separation type heat pipe exchanger comprises a heat pipe group, a cold pipe section liquid phase region and an air-cooled pipe section; the heat pipe group is arranged in the spent fuel pool and is connected with the liquid phase region of the cold pipe section to form a natural circulation pipe section; one end of the air cooling pipe section is connected with the heat pipe group, and the other end of the air cooling pipe section is connected with the liquid phase region of the cold pipe section.
Further, in the nuclear power plant spent fuel pool cooling system based on the passive separation type heat pipe exchanger, the heat pipe group comprises a plurality of cooling coils connected in parallel, and the cooling coils are rotary and are matched with a plurality of groups of spent fuel assemblies on the fuel grillwork for cooling.
Further, in the nuclear power plant spent fuel pool cooling system based on the passive separation type heat pipe heat exchanger, the plurality of cooling coil terminals are converged at the front end of the air cooling pipe section, and share the same air cooling pipe section.
Further, in the nuclear power plant spent fuel pool cooling system based on the passive separation type heat pipe exchanger, the cooling coil is communicated with the cold pipe section liquid phase region through a connecting pipe; the joint of the connecting pipe and the pipe end of the cooling disk is provided with a transition pipe section with an inclination angle of 30-80 degrees.
Furthermore, in the nuclear power plant spent fuel pool cooling system based on the passive separation type heat pipe heat exchanger, the connecting pipe is provided with the heat insulation layer.
Further, in the nuclear power plant spent fuel pool cooling system based on the passive separation type heat pipe heat exchanger, the cooling coil is rectangular and convoluted, the screw pitch of the cooling coil is 8-15cm, and the rectangular convoluted corner is set to be an elbow.
Further, in the nuclear power plant spent fuel pool cooling system based on the passive separation type heat pipe exchanger, the air cooling pipe section is a plurality of parallel heat pipe cooling loop collecting pipe sections and is provided with a plurality of cooling pipes, and the cooling pipes are provided with wavy ribs.
Further, in the nuclear power plant spent fuel pool cooling system based on the passive separation type heat pipe exchanger, the natural circulation pipe section is nano fluid coolant with the volume fraction of 0.1-0.5% and the average grain diameter of less than 20 nm.
Furthermore, in the nuclear power plant spent fuel pool cooling system based on the passive separation type heat pipe exchanger, a pulse oscillator is arranged in a liquid phase region of the cold pipe section.
Further, in the nuclear power plant spent fuel pool cooling system based on the passive separation type heat pipe exchanger, the impeller of the pulse oscillator is driven by the coolant circulation in the natural circulation pipe section, so that pulse oscillation waves are generated.
The beneficial effects of the invention are as follows:
(1) The separated heat pipe is used for cooling the spent fuel assembly, so that the efficiency is high;
(2) The rectangular distributed parallel cooling coil groups are adopted to cool the spent fuel assemblies arranged in the spent fuel pool, and the rectangular convolution design of the cooling coils is used for cooling a plurality of groups of spent fuel assemblies on each fuel grid, so that the cooling coil groups are more close to the practical engineering application environment;
(3) The cooling system takes nano fluid as a coolant, and is provided with a natural circulation loop to maintain the dispersibility of the nano fluid, so that the low-pressure boiling heat exchange is realized, the heat transfer efficiency is greatly increased, and the cooling heat exchange is facilitated;
(4) The separated heat pipe cooling system adopts an passive design concept, and can meet long-term cooling requirements without manual operation, so that the safety is greatly improved;
(5) The common cooling pipe section adopts an air cooling design, and the purpose of high-efficiency cooling is achieved by adding cooling pipelines and ribs;
(6) The cooling of the multiple groups of spent fuel assemblies arranged in the partition mode is realized in the form of parallel heat pipe groups, so that the cooling device has more pertinence.
Drawings
FIG. 1 is a schematic diagram of a nuclear power plant spent fuel pool cooling system based on a passive separation type heat pipe exchanger.
Fig. 2 is a schematic structural view of the cooling coil of the present invention.
Fig. 3 is a schematic structural view of a rectangular array of heat pipe sets according to the present invention.
In the drawings, 1, a spent fuel pool; 2. a plurality of sets of spent fuel assemblies; 2a, an elbow; 2b, thread pitch; 2c, fixing the grillwork; 2d, a base; 2e, a support structure; 3. a valve; 4. a pipe; 5. a cooling coil; 6. a transition pipe section; 6a, inclination angle; 7. a connecting pipe; 8. a pulse oscillator; 9. an air-cooled tube section; 9a, cooling pipes; 9b, wave-shaped ribs; 10. a nanofluidic coolant; 11. a cold pipe section liquid phase region; 12. a rectangular array.
Detailed Description
The present invention will be described in detail with reference to the accompanying drawings and examples.
The improvement of the safety of the spent fuel pool is very important from the investigation of Japanese Fudao nuclear accidents, and in the past, the active cooling mode of the spent fuel pool has great potential safety hazards, and once the whole plant is powered off, the spent fuel pool is likely to further cause accidents due to insufficient heat dissipation, so that radioactive pollution is caused. Therefore, the passive separation type parallel heat pipe cooling system for the spent fuel pool of the pressurized water reactor nuclear power plant is provided by optimizing the heat pipe cooling technology which is focused at present from the perspective of improving inherent safety through passive design of the third-generation nuclear power plant and combining with the nano fluid technology, and aims to successfully realize passive long-term cooling of the spent fuel pool so as to improve safety and economy of the spent fuel pool.
In a heat exchange system of a nuclear plant, the internal pressure of a heat pipe is low, so that a cooling working medium has a low boiling point, and heat exchange is enhanced by utilizing a boiling heat exchange mode; the separated heat pipe mainly comprises a hot pipe section and a cold pipe section, wherein the hot pipe section absorbs ambient heat and transfers the heat to the cold pipe section in a steam form, and the cold pipe section is cooled by an external cold source to liquefy and reflux the steam. The nano fluid is a novel cooling working medium, belongs to colloid in strict sense, and has obvious heat exchange enhancement characteristic. The invention provides a system design capable of cooling a spent fuel pool for a long time from the point of passive design by combining a nanofluid reinforced heat exchange technology. The design sets up many rectangle cooling coil that revolve to the multiunit spent fuel subassembly that the subregion was settled in the spent fuel pond, cools off respectively to the multizone fuel subassembly. The cooling coil loop adopts nano fluid as a coolant, and a natural circulation loop is arranged, so that the purpose of passively cooling the spent fuel pool for a long time is realized.
As shown in FIG. 1, the invention provides a nuclear power plant spent fuel pool cooling system based on a passive separation type heat pipe exchanger, which comprises a heat pipe group, a cold pipe section liquid phase region 11 and an air-cooled pipe section 9; the heat pipe group is arranged in the spent fuel pool 1 and is connected with the cold pipe section liquid phase region 11 to form a natural circulation pipe section; one end of the air-cooled tube section 9 (provided with the valve 3) is connected to the heat pipe group, and the other end is connected to the liquid phase region 11 of the cooled tube section. In this embodiment, the working principle of the passive split parallel heat pipe cooling system is described by taking one parallel circuit as an example.
In this embodiment, the heat pipe group includes a plurality of cooling coils 5 connected in parallel, and the cooling coils 5 are convoluted and cooperate with the plurality of groups of spent fuel assemblies 2 on the fuel grillwork for cooling. As shown in fig. 2, the spent fuel assembly is mounted on the base 2d by a fixed grid 2 c. The cooling coil 5 is wound around the spent fuel assembly and supported by the support structure 2 e. The terminals of the cooling coils 5 are converged at the front end of the air cooling pipe section 9 through the pipeline 4, and share the same air cooling pipe section 9. As shown in fig. 2, the cooling coil 5 is in a rectangular convolution shape, the pitch 2b of the cooling coil 5 is 8-15cm, and the corner of the rectangular convolution is set as an elbow 2a. The rectangular convolution design enables the cooling coil 5 to be in more uniform contact with a plurality of groups of spent fuel assemblies 2, the elbow 2a is designed to reduce thermal stress impact, the spiral structure enables the heat pipe to have certain anti-telescoping property, and the reliability of the system is improved; the plurality of cooling coils 5 are arranged according to the rectangular array 12 (see fig. 3), so that the cooling coils are closer to the actual application conditions of engineering, and have more engineering significance.
In fig. 1, the cooling coil 5 is in communication with the cold leg liquid phase region 11 through a connecting tube 7; the joint of the connecting pipe 7 and the end of the cooling coil pipe 5 is provided with a transition pipe section 6 with an inclination angle of 30-80 degrees 6a, so that the disturbance of cooling working media is promoted while the steam interference is prevented. The connection pipe 7 is provided with a heat insulating layer (e.g. glass fiber, vacuum plate, etc.).
The air cooling pipe section 9 is a collection pipe section of a plurality of parallel heat pipe cooling circuits and is provided with a plurality of cooling pipes 9a, and the cooling pipes 9a are provided with wavy ribs 9b.
The natural circulation pipe section is a nanofluid coolant (such as water-based copper nanofluid, water-based carbon nano-tube nanofluid, water-based alumina nanofluid and the like) with the average grain diameter of less than 20nm and the volume fraction of 0.1-0.5%. In the embodiment, the nanofluid coolant 10 with the average particle diameter of 20nm and the volume fraction of 0.1% and with the lower concentration is adopted, and the physical properties of the nanofluid and pure water are very similar due to the lower concentration; compared with pure water, the nano fluid has higher heat transfer efficiency, and is beneficial to the rapid heat conduction; in general, the nanofluidic coolant 10 can be stabilized for more than 3 days without any assistance or disturbance without significant deposition.
In fig. 1, the cold pipe section liquid phase region 11 is provided with a pulse oscillator 8, and the pulse oscillator 8 can generate a pulse oscillation wave which is beneficial to nanofluid dispersion, similar to the working principle of an ultrasonic vibration disperser; the circulation of the cooling working medium is not only beneficial to the uniform distribution of temperature, but also can drive the rotating impeller of the pulse oscillator 8 to further provide energy for the pulse oscillator 8, and the pulse oscillator 8 disperses the water-based nano fluid, so that good dispersibility is maintained.
The interior of the heat pipe is negative pressure, and the pressure value tends to be vacuum, so that the cooling working medium has a lower boiling point. Under normal or accident conditions, the cooling medium absorbs heat from the multiple groups of spent fuel assemblies 2 to boil, and the intensity of the boiling depends on the cooling conditions of the multiple groups of spent fuel assemblies 2. Boiling absorbs heat and generates water vapor, and the water vapor enters the air cooling pipe section 9 through the pipeline 4, so that the liquefied water flows to the cold pipe section to complete one cycle; in the circulation process, the natural circulation loop is driven by the density difference of the cold and hot fluid to generate natural circulation to drive the rotary impeller, so that the pulse oscillator 8 is started, and the stability and the dispersivity of the nano fluid coolant 10 are maintained. The whole process is of passive design, and the heat in the spent fuel pool can be stably led out of the outside for a long time.
It will be apparent to those skilled in the art that various modifications and variations can be made to the present invention without departing from the spirit or scope of the invention. Thus, it is intended that the present invention also include such modifications and alterations insofar as they come within the scope of the appended claims or the equivalents thereof.
Claims (3)
1. A nuclear power plant spent fuel pool cooling system based on a passive separation type heat pipe heat exchanger is characterized in that: comprises a heat pipe section, a cold pipe section liquid phase region (11) and an air-cooled pipe section (9); the heat pipe group is arranged in the spent fuel pool (1) and is connected with the cold pipe section liquid phase region (11) to form a natural circulation pipe section; one end of the air cooling pipe section (9) is connected with the heat pipe group, and the other end of the air cooling pipe section is connected with the cold pipe section liquid phase region (11); the heat pipe group comprises a plurality of cooling coils connected in parallel, and the cooling coils (5) are rotary and are matched with a plurality of groups of spent fuel assemblies (2) on the fuel grillwork for cooling; the cooling coil (5) is in a rectangular convolution shape, the screw pitch (2 b) of the cooling coil is 8-15cm, and the rectangular convolution corner is set as an elbow (2 a); the natural circulation pipe section is provided with a nano fluid coolant (10) with the average grain diameter smaller than 20nm and the volume fraction of 0.1-0.5%; the cold pipe section liquid phase region (11) is provided with a pulse oscillator (8); the impeller of the pulse oscillator (8) is driven by the coolant circulation in the natural circulation pipe section, so as to generate pulse oscillation waves; the cooling coil (5) is communicated with the cold tube section liquid phase region (11) through a connecting tube (7); a transition pipe section (6) with an inclination angle (6 a) of 30-80 degrees is arranged at the joint of the connecting pipe (7) and the cooling coil pipe (5); the air cooling pipe section (9) is a plurality of parallel heat pipe cooling loop collecting pipe sections and is provided with a plurality of cooling pipelines (9 a), and wavy ribs (9 b) are arranged on the cooling pipelines (9 a).
2. The nuclear power plant spent fuel pool cooling system based on the passive separation type heat pipe exchanger according to claim 1, wherein: and the plurality of cooling coil terminals are converged at the front end of the air cooling pipe section (9), and share the same air cooling pipe section (9).
3. The nuclear power plant spent fuel pool cooling system based on the passive separation type heat pipe exchanger according to claim 1, wherein: the connecting pipe (7) is provided with a heat insulation layer.
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| CN201910437832.2A CN110274501B (en) | 2019-05-24 | 2019-05-24 | Nuclear power plant spent fuel pool cooling system based on passive separation type heat pipe exchanger |
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| CN201910437832.2A CN110274501B (en) | 2019-05-24 | 2019-05-24 | Nuclear power plant spent fuel pool cooling system based on passive separation type heat pipe exchanger |
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| CN110274501B true CN110274501B (en) | 2023-06-23 |
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| 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 |
| CN110689983B (en) * | 2019-10-11 | 2021-08-24 | 中国核电工程有限公司 | Spent fuel pool system and heat exchange method |
| CN112611247A (en) * | 2020-11-27 | 2021-04-06 | 中国核电工程有限公司 | Passive waste heat derivation heat pipe heat exchanger for spent fuel pool |
| CN113808766B (en) * | 2021-08-10 | 2023-12-22 | 中国核电工程有限公司 | Nanofluid cooling loop system suitable for pressurized water reactor nuclear power station |
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| CN1115372C (en) * | 2000-06-15 | 2003-07-23 | 南京理工大学 | Nanometer fluid high-effective heat-conductive cooling working medium and its preparation method |
| CN202216595U (en) * | 2011-05-12 | 2012-05-09 | 北京工业大学 | Liquid pump driving heat pipe cooling device for natural cooling |
| CN102644996B (en) * | 2012-04-09 | 2014-06-18 | 中国核电工程有限公司 | Spent fuel water tank natural ventilation and water recovery system responding to serious accident |
| CN203837543U (en) * | 2014-02-27 | 2014-09-17 | 中国核电工程有限公司 | Nuclear-grade heat pipe type heat exchanger for passive containment vessel cooling system |
| CN108643984A (en) * | 2018-05-04 | 2018-10-12 | 上海理工大学 | A kind of spentnuclear fuel pond passive cooling system based on organic rankie cycle |
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