CN202855320U - Heat pipe cooling device for spent fuel water tank of pressurized-water nuclear power station - Google Patents
Heat pipe cooling device for spent fuel water tank of pressurized-water nuclear power station Download PDFInfo
- Publication number
- CN202855320U CN202855320U CN2012205124789U CN201220512478U CN202855320U CN 202855320 U CN202855320 U CN 202855320U CN 2012205124789 U CN2012205124789 U CN 2012205124789U CN 201220512478 U CN201220512478 U CN 201220512478U CN 202855320 U CN202855320 U CN 202855320U
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- CN
- China
- Prior art keywords
- heat pipe
- spent fuel
- heat
- cooling device
- power station
- 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
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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
- F28D15/0275—Arrangements for coupling heat-pipes together or with other structures, e.g. with base blocks; Heat pipe cores
-
- 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
Abstract
The utility model relates to a heat pipe cooling device for a spent fuel water tank of a pressurized-water nuclear power station. The heat pipe cooling device comprises at least one heat pipe radiation component arranged on the wall of the spent fuel water tank, wherein the part, arranged in the spent fuel water tank, of the heat pipe radiation component is a heat adsorption segment; and the part, penetrating through the wall of the spent fuel water tank and arranged outside the spent fuel water tank, of the heat pipe radiation component is a radiation segment. According to the utility model, in a manner of arranging a heat pipe heat-conduction component on the side wall of the spent fuel water tank, under the condition that a cooling system of the original spent fuel water tank fails, the heat generated by spent fuel is led out of a spent fuel plant through passive heat conduction of heat pipes so as to perform cooling, thus making up the defect of the original system in case of beyond design basis accidents, delaying the boiling time after loss of cooling of the spent fuel water tank and protecting the safety of spent fuel components.
Description
Technical field
The utility model relates to a kind of auxiliary device of setting-out nuclear power station spent fuel reservoir, more particularly, relates to a kind of heat pipe cooling device for setting-out Nuclear Power Station's Exhausted Fuels battery pond.
Background technology
In the existing compressed water reactor nuclear power technology, Spent Fuel Pool is cooled off by the cooling circuit that ebullator, heat exchanger and respective lines form, and low-temperature receiver is the nuclear power plant equipment chilled water.In this cooling circuit, no matter the work of pond ebullator or providing of component cooling water are provided, all need enough electric power supports.And nuclear power station is after facing beyond design basis accident (such as violent earthquake, tsunami), probably face the situation of full factory dead electricity, this moment, original cooling way lost efficacy, Spent Fuel Pool will face the danger of boiling, evaporate to dryness, serious consequence may cause melting down such as the spent fuel rods in the Fukushima nuclear accident, and a large amount of radioactivity are controlled release not.
The utility model content
The technical problems to be solved in the utility model is, for the defects of prior art, provides a kind of heat pipe cooling device for the setting-out nuclear power station spent fuel reservoir.
The technical scheme that its technical matters that solves the utility model adopts is: the heat pipe cooling device of constructing a kind of setting-out nuclear power station spent fuel reservoir, comprise that at least one is arranged on the heat pipe heat radiation assembly on the described Spent Fuel Pool pool wall, described heat pipe heat radiation spare assembly is arranged on the endotherm section that is in the described Spent Fuel Pool, pass described Spent Fuel Pool pool wall be arranged on described Spent Fuel Pool outer be radiating segment.
Heat pipe cooling device for the setting-out nuclear power station spent fuel reservoir described in the utility model, wherein, the position of described endotherm section in the vertical direction is lower than the position of described radiating segment on same direction.
Heat pipe cooling device for the setting-out nuclear power station spent fuel reservoir described in the utility model, wherein, each described heat pipe heat radiation assembly includes many parallel heat pipes that arrange and pass described Spent Fuel Pool pool wall, in described heat pipe comprises for the body of subnormal ambient and be arranged on the interior liquid-sucking core of described body, be filled with working fluid in the heat pipe of described endotherm section, the heat pipe of described radiating segment is outside equipped with low-temperature receiver.Heat pipe cooling device for the setting-out nuclear power station spent fuel reservoir described in the utility model, wherein, described liquid-sucking core can be the liquid-sucking core of being made by the capillary porosint.
Heat pipe cooling device for the setting-out nuclear power station spent fuel reservoir described in the utility model, wherein, described radiating segment parallel interval is provided with the polylith heat radiator, and the plane at described heat radiator place is vertical with the axis of the heat pipe of described radiating segment.
Heat pipe cooling device for the setting-out nuclear power station spent fuel reservoir described in the utility model, wherein, described endotherm section parallel interval is provided with the polylith heat radiator, and the plane at described heat radiator place is vertical with the axis of the heat pipe of described endotherm section.
Heat pipe cooling device for the setting-out nuclear power station spent fuel reservoir described in the utility model, wherein, the length of described radiating segment is greater than the length of described endotherm section.
Heat pipe cooling device for the setting-out nuclear power station spent fuel reservoir described in the utility model, wherein, described endotherm section comprises at least one evaporator section heat pipe bundle, described radiating segment comprises at least one condensation segment heat pipe bundle, one end of described evaporator section heat pipe bundle and described condensation segment heat pipe bundle is by pipeline communication in the vapor collection, and the other end is communicated with by the coolant return line road.
Heat pipe cooling device for the setting-out nuclear power station spent fuel reservoir described in the utility model wherein, is filled with working fluid in the described evaporator section heat pipe bundle, and described condensation segment heat pipe bundle is outside equipped with low-temperature receiver.
Heat pipe cooling device for the setting-out nuclear power station spent fuel reservoir described in the utility model, wherein, described coolant return line also is provided with the separatory baffle plate in the road.
Implement the heat pipe cooling device for the setting-out nuclear power station spent fuel reservoir of the present utility model, have following beneficial effect: the utility model is by arranging the mode of heat pipe for thermal conductivity assembly at the Spent Fuel Pool sidewall, in the situation that original Spent Fuel Pool cooling system lost efficacy, non-active heat conduction by heat pipe is cooled off the heat derivation spentnuclear fuel factory building that spentnuclear fuel produces outward, remedied the deficiency of original system under beyond design basis accident, delay the boiling time after the Spent Fuel Pool mistake is cold, protected the safety of irradiated fuel assembly;
And the rescue personnel need not to enter the spentnuclear fuel factory building after making accident when the cooling Spent Fuel Pool, greatly reduces personnel's irradiation risk.Heat pipe for thermal conductivity assembly not only heat transfer efficiency is high but also simple and reliable for structure, does not need power to take the decay heat of weary pond out of the spentnuclear fuel factory building, also can work under the full factory of nuclear power station dead electricity operating mode.
Description of drawings
The utility model is described in further detail below in conjunction with drawings and Examples, in the accompanying drawing:
Fig. 1 is the structural representation of a kind of heat pipe cooling device the first embodiment for the setting-out nuclear power station spent fuel reservoir of the utility model;
Fig. 2 is the wiring layout of a kind of heat pipe cooling device the first embodiment for the setting-out nuclear power station spent fuel reservoir of the utility model;
Fig. 3 is the structural representation of a kind of heat pipe cooling device the second embodiment for the setting-out nuclear power station spent fuel reservoir of the utility model;
Fig. 4 is the wiring layout of a kind of heat pipe cooling device the second embodiment for the setting-out nuclear power station spent fuel reservoir of the utility model;
Fig. 5 is the wiring layout of a kind of heat pipe cooling device the 3rd embodiment for the setting-out nuclear power station spent fuel reservoir of the utility model;
Fig. 6 is the front view of a kind of heat pipe cooling device the 3rd embodiment for the setting-out nuclear power station spent fuel reservoir of the utility model.
Embodiment
Shown in Fig. 1-2, in the first embodiment of the present utility model, the heat pipe cooling device that should be used for the setting-out nuclear power station spent fuel reservoir comprises that at least one is arranged on the heat pipe heat radiation assembly on the Spent Fuel Pool pool wall, the quantity of heat pipe heat radiation assembly can be according to field condition, such as the maximum decay heat power of spentnuclear fuel, heat radiation power and low-temperature receiver selection etc. carries out concrete selection.This heat pipe heat radiation spare assembly is arranged on and is endotherm section 100 in the Spent Fuel Pool, pass the Spent Fuel Pool pool wall be arranged on Spent Fuel Pool outer be radiating segment 200.Further, in the first embodiment, the heat pipe heat radiation assembly includes many parallel heat pipes 300 that arrange and pass the Spent Fuel Pool pool wall, the interlude of heat pipe 300 passes Spent Fuel Pool and does not affect the sealing of Spent Fuel Pool, so that the heat in the pond can be derived the spentnuclear fuel pond under the isolation condition.Further, in heat pipe 300 comprises for the body of subnormal ambient and be arranged on the interior liquid-sucking core of body, be filled with working fluid in the heat pipe 300 of endotherm section 100, and the heat pipe 300 of radiating segment 200 is outside equipped with low-temperature receiver, and the position of endotherm section 100 in the vertical directions is lower than the position of radiating segment 200 on same direction.
Be pumped into negative pressure state in the body, working fluid boiling point in the body is reduced, be more prone to volatilization, the liquid-sucking core in the body is made of porous materials, when endotherm section 100 is heated, working fluid in the liquid-sucking core evaporates rapidly, and steam flows to radiating segment 200 under small pressure differential, and releases heat, regelation becomes liquid, liquid flows back to endotherm section 100 along porosint by the effect of capillary force again, and so circulation is more than, and heat reaches an other end by heat pipe 300 1 ends.This circulation is carried out fast, and heat can be come by continuously conduction.And by the characteristic of heat pipe as can be known, the position of radiating segment 200 in the vertical directions is higher than the position of endotherm section 100 on same direction, strengthening the gravity reflux of working fluid, and guarantees that working fluid rests in the radiating segment 200 under the off working state.
Understandable, also can omit liquid-sucking core, the position of radiating segment 200 is higher than endotherm section 100, directly utilizes the effect of gravity reflux, and condensed working fluid is back to endotherm section 100.
Under the accidental conditions of power station, the temperature of Spent Fuel Pool is lower than the start-up temperature of heat pipe 300, and the working fluid in the heat pipe 300 will not undergo phase transition, so assembly can not carry out heat transfer, does not affect the normal operation in power station.
Under accident conditions, after Spent Fuel Pool loses cooling, the pond temperature will rise because of the spentnuclear fuel decay heat, when temperature reaches the start-up temperature of heat pipe 300 in the heat-conductive assembly, the hydraulic fluid heat absorption boiling vaporization in heat pipe 300 endotherm sections 100, steam takes heat to the radiating segment 200 of heat pipe 300, steam condensation after the low-temperature receiver heat release, by capillary action and the Action of Gravity Field of liquid-sucking core, working fluid refluxes to endotherm section 100, and the boiling of again being heated.Radiating segment 100 can use the various ways such as fire water, seawater, air-cooled, absorption refrigeration as low-temperature receiver, specifically can be determined by nuclear power station environment of living in.
In this embodiment, because the natural convection of Chi Shui when endotherm section 100 adds the work of heat radiator meeting barrier components, therefore only be fixedly installed the heat radiator 400 that the polylith parallel interval arranges at radiating segment 200, and the plane at heat radiator 400 places is perpendicular to the axis of the heat pipe of radiating segment 200, heat radiator 400 has the effect of strengthening heat exchange, endotherm section 100 hangs down along the pool wall in spentnuclear fuel pond, can the integrality of pool wall not impacted.
And in this embodiment, when the heat radiation power of used low-temperature receiver hangs down, can also make the heat pipe bundle that stretches out body of wall in the pond shorter, and the heat pipe bundle that stretches out body of wall outside the pond is longer, and short heat pipe Shu Buhui has influence on the normal loading and unloading of spentnuclear fuel in the pond, but and the heat pipe bundle increasing heat radiation area of growing in the pond outside, strengthen radiating effect, make the starting stage of accident, when low-temperature receiver can only provide by fire truck, the heat pipe heat radiation assembly also can be derived the heat in the spentnuclear fuel pond effectively.Certainly, radiating segment 200 also comparable endotherm section 100 is short, with the power of the restriction that adapts to the factory building space outerpace or low-temperature receiver greater than different demands such as spentnuclear fuel decay heat power.
As shown in Figure 3-4, in the second embodiment of the present utility model, each ingredient, function and the operation principles of being somebody's turn to do the heat pipe heat radiation assembly that is used for the setting-out nuclear power station spent fuel reservoir are all identical with the first embodiment, different is, on the endotherm section 100 also parallel interval be provided with polylith heat radiator 400, and the heat pipe heat radiation assembly is seen on the whole than the structure of the first embodiment level comparatively.By increasing polylith heat radiator 400, can increase endothermic effect, better derive the heat in the pond.
Shown in Fig. 5-6, in the 3rd embodiment of the present utility model, the endotherm section 100 of this heat pipe heat radiation assembly comprises at least one evaporator section heat pipe bundle 500, radiating segment 200 comprises at least one condensation segment heat pipe bundle 600, evaporator section heat pipe bundle 500 is communicated with by steam localized ducting 700 with an end of condensation segment heat pipe bundle 600, and the other end is communicated with by coolant return line road 800.Wherein, be filled with working fluid in the evaporator section heat pipe bundle 500, condensation segment heat pipe art 600 is outside equipped with low-temperature receiver.Its principle of work is still identical with upper two embodiment, working fluid heat absorption in the evaporator section heat pipe bundle 500 of endotherm section 100 flashes to gas, then enter in the condensation segment heat pipe bundle 600 of radiating segment 200 along steam localized ducting 700, by the low-temperature receiver cooling in the solidifying section heat pipe bundle 600, liquid after the cooling flows back in the evaporator section heat pipe bundle 500 along coolant return line road 800 again, finishes a thermal cycle with this.Understandable, also liquid-sucking core can be set in this heat pipe heat radiation assembly, be beneficial to the backflow of working fluid; Certainly, also radiating segment 200 can be arranged on the position that is higher than endotherm section 100, utilize the Action of Gravity Field working fluid that refluxes, thereby can simplify the design of heat pipe.
Quantity that it should be noted that evaporator section heat pipe bundle 500 and condensation segment heat pipe bundle 600 can guarantee according to field condition adjustment the radiating effect of Spent Fuel Pool.
In addition, also be provided with the separatory baffle plate in the coolant return line road 800, the separatory baffle plate can make the working fluid that refluxes in the coolant return line road 800 in the 500 interior uniform distributions of multi-layer evaporation section heat pipe bundle.Because flowing of working fluid mainly concentrates in steam localized ducting 700 and the coolant return line road 800, the xsect that penetrates body of wall is few, therefore is conducive to reduce quantities, reduces the difficulty of maintenance of equipment and replacing.
Above embodiment only is explanation technical conceive of the present utility model and characteristics, and its purpose is to allow the personage who is familiar with technique can understand content of the present utility model and accordingly enforcement, can not limit protection domain of the present utility model.All equalizations of doing with the utility model claim scope change and modify, and all should belong to the covering scope of the utility model claim.
Claims (10)
1. heat pipe cooling device that is used for the setting-out nuclear power station spent fuel reservoir, it is characterized in that, comprise that at least one is arranged on the heat pipe heat radiation assembly on the described Spent Fuel Pool pool wall, described heat pipe heat radiation spare assembly is arranged on and is endotherm section (100) in the described Spent Fuel Pool, pass described Spent Fuel Pool pool wall be arranged on described Spent Fuel Pool outer be radiating segment (200).
2. the heat pipe cooling device for the setting-out nuclear power station spent fuel reservoir according to claim 1 is characterized in that, the position of described endotherm section (100) in the vertical direction is lower than the position of described radiating segment (200) on same direction.
3. the heat pipe cooling device for the setting-out nuclear power station spent fuel reservoir according to claim 1, it is characterized in that, each described heat pipe heat radiation assembly includes many parallel heat pipes (300) that arrange and pass described Spent Fuel Pool, in described heat pipe (300) comprises for the body of subnormal ambient and be arranged on the interior liquid-sucking core of described body, be filled with working fluid in the heat pipe of described endotherm section (100), the heat pipe of described radiating segment (200) is outside equipped with low-temperature receiver.
4. the heat pipe cooling device for the setting-out nuclear power station spent fuel reservoir according to claim 3 is characterized in that, the liquid-sucking core of described liquid-sucking core for being made by the capillary porosint.
5. the heat pipe cooling device for the setting-out nuclear power station spent fuel reservoir according to claim 3, it is characterized in that, described radiating segment (200) parallel interval is provided with polylith heat radiator (400), and the plane at described heat radiator (400) place is vertical with the axis of the heat pipe (300) of described radiating segment (200).
6. the heat pipe cooling device for the setting-out nuclear power station spent fuel reservoir according to claim 5, it is characterized in that, described endotherm section (100) parallel interval is provided with polylith heat radiator (400), and the plane at described heat radiator (400) place is vertical with the axis of the heat pipe (300) of described endotherm section (100).
7. the heat pipe cooling device of each described setting-out nuclear power station spent fuel reservoir is characterized in that according to claim 1-6, and the length of described radiating segment (200) is greater than the length of described endotherm section (100).
8. the heat pipe cooling device for the setting-out nuclear power station spent fuel reservoir according to claim 1 and 2, it is characterized in that, described endotherm section (100) comprises at least one evaporator section heat pipe bundle (500), described radiating segment (200) comprises at least one condensation segment heat pipe bundle (600), described evaporator section heat pipe bundle (500) is communicated with by steam localized ducting (700) with an end of described condensation segment heat pipe bundle (600), and the other end is communicated with by coolant return line road (800).
9. the heat pipe cooling device for the setting-out nuclear power station spent fuel reservoir according to claim 8 is characterized in that, is filled with working fluid in the described evaporator section heat pipe bundle (500), and described condensation segment heat pipe bundle (600) is outside equipped with low-temperature receiver.
10. the heat pipe cooling device for the setting-out nuclear power station spent fuel reservoir according to claim 8 is characterized in that, also is provided with the separatory baffle plate in the described coolant return line road (800).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2012205124789U CN202855320U (en) | 2012-10-08 | 2012-10-08 | Heat pipe cooling device for spent fuel water tank of pressurized-water nuclear power station |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2012205124789U CN202855320U (en) | 2012-10-08 | 2012-10-08 | Heat pipe cooling device for spent fuel water tank of pressurized-water nuclear power station |
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| Publication Number | Publication Date |
|---|---|
| CN202855320U true CN202855320U (en) | 2013-04-03 |
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| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN2012205124789U Expired - Lifetime CN202855320U (en) | 2012-10-08 | 2012-10-08 | Heat pipe cooling device for spent fuel water tank of pressurized-water nuclear power station |
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| CN (1) | CN202855320U (en) |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103440887A (en) * | 2013-09-10 | 2013-12-11 | 华北电力大学 | Low-temperature negative-pressure heat tube of spent fuel pool |
| CN105006258A (en) * | 2015-06-17 | 2015-10-28 | 中科华核电技术研究院有限公司 | Floating passive cooling device and system of spent fuel pool in nuclear power plant |
| CN106653106A (en) * | 2017-01-19 | 2017-05-10 | 华南理工大学 | Nuclear power station spent fuel pool multistage long-distance passive heat pipe cooling system |
| CN113437328A (en) * | 2021-05-25 | 2021-09-24 | 中国舰船研究设计中心 | Latent multi-module fuel cell thermal management system |
-
2012
- 2012-10-08 CN CN2012205124789U patent/CN202855320U/en not_active Expired - Lifetime
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103440887A (en) * | 2013-09-10 | 2013-12-11 | 华北电力大学 | Low-temperature negative-pressure heat tube of spent fuel pool |
| CN105006258A (en) * | 2015-06-17 | 2015-10-28 | 中科华核电技术研究院有限公司 | Floating passive cooling device and system of spent fuel pool in nuclear power plant |
| CN106653106A (en) * | 2017-01-19 | 2017-05-10 | 华南理工大学 | Nuclear power station spent fuel pool multistage long-distance passive heat pipe cooling system |
| CN113437328A (en) * | 2021-05-25 | 2021-09-24 | 中国舰船研究设计中心 | Latent multi-module fuel cell thermal management system |
| CN113437328B (en) * | 2021-05-25 | 2023-03-14 | 中国舰船研究设计中心 | Latent multi-module fuel cell thermal management system |
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| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| C56 | Change in the name or address of the patentee | ||
| CP03 | Change of name, title or address |
Address after: 518000 Guangdong province Futian District Shangbu Road West of the city of Shenzhen Shenzhen science and technology building 15 layer (1502-1504, 1506) Patentee after: CHINA NUCLEAR POWER TECHNOLOGY RESEARCH INSTITUTE Co.,Ltd. Patentee after: CHINA GENERAL NUCLEAR POWER Corp. Address before: 518000 Guangdong, Futian District, Yitian Road, building A, block, building on the whole floor of A1301-1320 13 Patentee before: CHINA NUCLEAR POWER TECHNOLOGY RESEARCH INSTITUTE Co.,Ltd. Patentee before: CHINA GUANGDONG NUCLEAR POWER GROUP Co.,Ltd. |
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| CX01 | Expiry of patent term | ||
| CX01 | Expiry of patent term |
Granted publication date: 20130403 |