CN101079333A - Nuclear reactor non-energy and multi-function pool voltage-stabling system - Google Patents
Nuclear reactor non-energy and multi-function pool voltage-stabling system Download PDFInfo
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- CN101079333A CN101079333A CNA2006100815366A CN200610081536A CN101079333A CN 101079333 A CN101079333 A CN 101079333A CN A2006100815366 A CNA2006100815366 A CN A2006100815366A CN 200610081536 A CN200610081536 A CN 200610081536A CN 101079333 A CN101079333 A CN 101079333A
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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 discloses a non-active multi-functional ponded stabilivolt system of atomic reactor, which comprises the following parts: high-pressure pond, air cavity on the interior of high-pressure pond, level measuring channel made of concrete structure in the air cavity, wherein the injecting pipe is set on the bottom of high-pressure pond to connect the reacting pile inlet cavity with stop valve on the injecting pipe; the fluctuating pipe is set on the bottom of the high-pressure pond to connect the main pump inlet; the rising pipe is set in the middle of the high-pressure pond to connect the reacting pile output cavity with pneumatic separating valve on the rising pipe; the small-flow circulating pipeline is set on the rising pipe between pneumatic separating valve and reacting pile output cavity, which connects the main pump inlet pipe. The invention improves the safety of reacting pile, which reduces the building and operating cost greatly with wide applying prospect.
Description
Technical field
The present invention relates to the voltage-stabilizing system of light-water reactor, be specifically related to a kind of nuclear reactor non-energy and multi-function pool voltage-stabling system.
Background technology
Common nuclear reactor coolant voltage-stabilizing system all belongs to the High Temperature High Pressure system, its principle of stabilized voltage is to rely on active electric heater to boost and multilevel security valve and pressure-release valve unload and be depressed into the release case, system is provided with complexity, only has voltage stabilizing function, must rely on the power supply of 1E level power supply.When reactor coolant forfeiture (LOAC) accident occurring, main system is vaporized rapidly because of decompression will cause the water in the voltage stabilizer, can't replenish the cooling medium loading amount to reactor, must start ad hoc safety injection system at the appointed time fast.
Low temperature cell shell-type reactor coolant loop belongs to the low-temp low-pressure system, and this kind heap type need be built in apart from densely populated city near zone, and is more strict to the requirement of nuclear safety.Although low-temperature heat supply nuclear reactor conceptual design kind is a lot of both at home and abroad at present, countries in the world have been carried out the exploration of decades, because economy and safety issue are not also accepted extensively by people.Therefore, seeking that a kind of high safety is reliable, operation is simple and construction and the cheap voltage-stabilizing system of operating cost, is the key that can pond formula low temperature heating reactor widespread use.
Summary of the invention
The object of the present invention is to provide a kind of system simple, reliable, have non-passive safety, can reduce significantly that nuclear reactor is built and the nuclear reactor non-energy and multi-function pool voltage-stabling system of operating cost.
Nuclear reactor non-energy and multi-function pool voltage-stabling system of the present invention comprises the pressure accumulation pond, and pressure accumulation pond internal upper part is provided with air cavity, adopts reinforced concrete structure to form the level measuring passage in air cavity; The pressure accumulation basin bottom is provided with the peace that links to each other with the reactor entrance chamber and annotates pipe, and peace is annotated on the pipe non-return valve is set; The pressure accumulation basin bottom also is provided with the fluctuation pipe that links to each other with the main pump inlet pipeline; Pressure accumulation pond middle part is provided with the tedge that links to each other with the reactor export chamber, and pneumatic isolation valve is set on the tedge, is provided with the low discharge circulation line that links to each other with the main pump inlet pipeline on pneumatic isolation valve and tedge that the reactor export chamber links to each other.
Aforesaid nuclear reactor non-energy and multi-function pool voltage-stabling system, described pressure accumulation pond are impervious steel reinforced concrete pool formula structure, the inner liner stainless steel clad can; The pressure accumulation pond is cylindrical or square.
Aforesaid nuclear reactor non-energy and multi-function pool voltage-stabling system is filled with nitrogen or pressurized air in the described air cavity, the air cavity internal pressure is 0.1Mpa～0.3Mpa.
Aforesaid nuclear reactor non-energy and multi-function pool voltage-stabling system is the balance water level of gravity water filling with top mark height between the loop, and the pressure accumulation pond is equal to or greater than the summation of free volume between the hole of reactor and loop in the water yield more than the balance water level.
Nuclear reactor non-energy and multi-function pool voltage-stabling system of the present invention, under nominal situation, the water in the pressure accumulation pond relies on gravity to change by the volume fluctuations of fluctuation pipe for reactor coolant loop pressurization, voltage stabilizing and compensation cooling medium; Pneumatic isolation valve on the tedge is in closed condition at this moment, makes the water in the tedge keep the very flow state and the hot state of low discharge by the low discharge circulation line.Under the loss of-coolant accident (LOCA) situation, if this moment, main pump was stopped transport, the water in the pressure accumulation pond relies on gravity to annotate the automatic piii reactor of pipe by peace; If main pump operation this moment, the water in the pressure accumulation pond rely on gravity by the automatic piii reactor of fluctuation pipe.Under reactor emergency shut-down situation, pneumatic isolation valve is opened, if this moment, main pump was stopped transport, then between reactor and pressure accumulation pond, form " tedge-pressure accumulation pond-An annotates pipe-reactor-tedge " Natural Circulation waste heat passing away, with the residue heat release importing pressure accumulation pond of reactor; If this moment, main pump moved, then between reactor and pressure accumulation pond, form the forced circulation waste heat passing away of " tedge-pressure accumulation pond-fluctuation pipe-main pump-reactor-tedge ", with the residue heat release importing pressure accumulation pond of reactor.When cold-refueling, after reactor was uncapped, the water in pressure accumulation pond relied on gravity to inject and be full of refuelling pool automatically by peace notes pipe.
Nuclear reactor non-energy and multi-function pool voltage-stabling system of the present invention is except pressurization, voltage stabilizing and cubage compensation that normal when operation reactor coolant loop can be provided, also can provide non-passive safety injection under the accident conditions, emergent waste heat to discharge, and can be used as the multiple functions such as water source and gravity water-filling of reloading.System of the present invention gathers multi-function in integral whole, and the while can guarantee the successful execution of various functions again and not disturb mutually.Owing to adopt passive system, the security of reactor is improved greatly, system is greatly simplified, and moves more easyly, has solved the safety issue of pond shell-type low temperature heating reactor well, has reduced construction and operating cost greatly.The present invention can be widely used in process heat reactor, desalination reactor, research reactor and low parameter power reactor, for nuclear reactor has been opened up wide prospect in the application in nuclear desalination and district heating field.
Description of drawings
The synoptic diagram of Fig. 1 nuclear reactor non-energy and multi-function pool voltage-stabling system.
Among the figure: 1. reactor; 2. low discharge circulation line; 3. main pump inlet pipeline; 4. main pump; 5. non-return valve; 6. pressure accumulation pond; 7. peace is annotated pipe; 8. tedge: 9. level measuring passage; 10. air cavity; 11. fluctuation pipe; 12. pneumatic isolation valve; 13. main heat exchanger.
Embodiment
The pond shell-type low temperature heating reactor that is used for desalinization with a thermal power 245MW is an example below, in conjunction with the accompanying drawings 1, nuclear reactor non-energy and multi-function pool voltage-stabling system of the present invention is specifically described.
Reactor 1 is a shell structure that adopts rustless steel container with reactor core and associated component and cooling medium containing and sealing.Entire reaction heap 1 places below the ground elevation, is supported on the step of reactor pit by the support ring that is welded on the reactor vessel middle cylinder.Reactor core upper surface absolute altitude is-9.0m, and the reactor building operating platform absolute altitude that reloads is+4.5m.Reactor coolant moves in the forced circulation mode by main pump 4, the heat of reactor core is derived by reactor coolant loop, by main heat exchanger 13 heat is passed to secondary coolant circuit system, pass to three loops by secondary heat exchanger again, produce hot water for user's use.Pressurization, voltage stabilizing and the cubage compensation of reactor coolant loop during normal the operation, non-passive safety injection under the accident conditions, emergent waste heat are discharged, and the multiple functions such as water source and gravity water-filling of reloading are finished by the reactor non-energy and multi-function pool voltage-stabling system.
As shown in Figure 1, nuclear reactor non-energy and multi-function pool voltage-stabling system comprises:
The pressure accumulation pond 6 of columniform impervious steel reinforced concrete pool formula structure, its inner liner stainless steel clad can.6 end of pressure accumulation pond absolute altitude is-8.5m that the top mark height is+16.0m total water capacity 2500m
3, normal operating water level+14.0m, 30 ℃ of water temperatures.Pressure accumulation pond 6 internal upper parts are provided with air cavity 10, adopt reinforced concrete structure to form level measuring passage 9 in air cavity 10 at pressure accumulation pond 6 internal upper parts.Air cavity 10 volumes are 220m
3, the nitrogen of interior covering 0.1MPa pressure.Adopt light section level measuring passage 9 to measure the water level in big section high capacity pond, improved the susceptibility that SEA LEVEL VARIATION is measured greatly, can be the breakdown protection high responsive signal reliably is provided.Water in the pressure accumulation pond 6 relies on the gravity water filling, (is the balance water level of gravity water filling approximately+3.5m) with top mark height between the loop.Water capacity under these pressure accumulation pond 6 balance water levels is 1500m
3, the above water capacity of balance water level is 1000m
3Pressure accumulation pond 6 is equal to or greater than the summation of free volume between the hole of reactor 1 and loop in the water yield more than the balance water level.
6 bottoms, pressure accumulation pond are provided with the peace that links to each other with reactor 1 entrance cavity and annotate pipe 7, and peace is annotated on the pipe 7 non-return valve 5 is set.The water that non-return valve 5 can stop the reactor coolant loop is annotated the heat interchange in pipe 7 pressure accumulation pond 6 and reactor 1 loop when pressure accumulation pond 6 directions flow and normally move, the water-filling function when having guaranteed 4 operations of loss of-coolant accident (LOCA) main pump again by peace.6 bottoms, pressure accumulation pond also are provided with the fluctuation pipe 11 that links to each other with main pump inlet pipeline 3.
Under nominal situation, pressure accumulation pond 6 interior water are in higher water level, and it is the volume fluctuations variation of reactor coolant loop pressurization, voltage stabilizing and compensation cooling medium by fluctuation pipe 11 that Chi Shui relies on gravity head, guarantees the normal operation of reactor.
Under the loss of-coolant accident (LOCA) situation, when main pump 4 was stopped transport, the water in the pressure accumulation pond 6 relied on gravity head to annotate pipe 7 automatic piii reactors 1 by peace; When main pump 4 operations, the water in the pressure accumulation pond 6 relies on gravity head by fluctuation pipe 11 automatic piii reactors 1.This pond formula voltage-stabilizing system is non-enabling fashion, realizes emergent reactor core cooling.Contain between reactor pit that the water that runs off from reactor coolant loop is closed and loop, water level rises between the loop, and until reaching the balance water level, leakage and water filling stop.Pressure accumulation pond 6 balance water levels can guarantee all to flood between the hole of reactor 1 and loop.
6 middle parts, pressure accumulation pond also are provided with the tedge 8 that links to each other with reactor 1 outlet plenum, and tedge 8 is provided with the pneumatic isolation valve 12 of quick unlatching.Before tedge 8 pneumatic isolation valves 12, be provided with the low discharge circulation line 2 that links to each other with main pump inlet pipeline 3.During normal the operation, pneumatic isolation valve 12 is in closed condition, make in the tedge 8 water keep the very flow state of low discharge by the low discharge circulation line 2 that links to each other with main pump inlet pipeline 3 always, and guaranteed that the water in the tedge 8 is in the state of heat all the time, thereby guaranteed that scram signal triggers tedge 8 and can set up the residue heat release that enough big natural circulation flow is derived reactor 1 rapidly after pneumatic isolation valve 12 is opened.
The intermediate heat trap that water in the pressure accumulation pond 6 is also discharged as emergent waste heat, after reactor 1 emergency shut-down, guard signal triggers the pneumatic isolation valve 12 of tedge 8 simultaneously and opens fast, if main pump 4 stoppages in transit this moment, then pass through " tedge 8-pressure accumulation pond 6-peace is annotated pipe 7-reactor 1-tedge 8 " and between reactor 1 and pressure accumulation pond 6, form Natural Circulation waste heat passing away, with the residue heat release importing pressure accumulation pond 6 of reactor 1; If main pump 4 moves at this moment, then by " tedge 8-pressure accumulation pond 6-fluctuation pipe 11-main pump 4-reactor 1-tedge 8 " formation forced circulation waste heat passing away between reactor 1 and pressure accumulation pond 6, with the residue heat release importing pressure accumulation pond 6 of reactor 1.
When cold-refueling, after reactor 1 was uncapped, the water in pressure accumulation pond 6 can lean on gravity to inject and be full of refuelling pool automatically by peace notes pipe 7, is used as the water that reloads.
In order to satisfy single failure criteria, guarantee the execution of security function, peace is annotated pipe 7, tedge 8 and fluctuation pipe 11 and has all been adopted redundant setting.In air cavity 10, pressurized air be can also be filled with, normal pressure or suitably pressurization kept.
The 245MW of employing non-energy and multi-function pool voltage-stabling system of the present invention is used for the normal operation pressure stabilization of pond shell-type low temperature heating reactor of desalinization, and the cubage compensation ability is big, and system is simple, and operation is convenient.Have under the accident conditions fast and discharge ability (deriving the residue heat release of reactor with non-enabling fashion safety injection and Natural Circulation) with enough big emergent reactor core cooling power and emergent waste heat.
The present invention utilizes natural driving forces such as gravity and Natural Circulation to provide complete non-active voltage-stabilizing system for pond shell-type low temperature heating reactor, and leaning on the gravity head of high water stage Chi Shui is reactor coolant loop pressurization, voltage stabilizing and cubage compensation.When reactor generation coolant loss (LOAC) accident, can postreaction reactor coolant in time loading amount, having provides the accident of reactor coolant loop safety injection, emergent waste heat discharge, reload water source and the multiple function of gravity water-filling, and the while can guarantee the successful execution of various functions again and not disturb mutually.The present invention can be according to different height, the gentle cavity pressures of water loading amount of needs design of main system and ad hoc security function.
Claims (5)
1. nuclear reactor non-energy and multi-function pool voltage-stabling system, it is characterized in that: this system comprises pressure accumulation pond (6), pressure accumulation pond (6) internal upper part is provided with air cavity (10), adopts reinforced concrete structure to form level measuring passage (9) in air cavity (10); Bottom, pressure accumulation pond (6) is provided with the peace that links to each other with reactor (1) entrance cavity and annotates pipe (7), and peace is annotated on the pipe (7) non-return valve (5) is set; Bottom, pressure accumulation pond (6) also is provided with the fluctuation pipe (11) that links to each other with main pump inlet pipeline (3); Middle part, pressure accumulation pond (6) is provided with the tedge (8) that links to each other with reactor (1) outlet plenum, pneumatic isolation valve (12) is set on the tedge (8), on pneumatic isolation valve (12) and tedge (8) that reactor (1) outlet plenum links to each other, is provided with the low discharge circulation line (2) that links to each other with main pump inlet pipeline (3).
2. nuclear reactor non-energy and multi-function pool voltage-stabling system according to claim 1 is characterized in that: described pressure accumulation pond (6) is impervious steel reinforced concrete pool formula structure, the inner liner stainless steel clad can.
3. nuclear reactor non-energy and multi-function pool voltage-stabling system according to claim 2 is characterized in that: described pressure accumulation pond (6) is for cylindrical or square.
4. nuclear reactor non-energy and multi-function pool voltage-stabling system according to claim 1 and 2 is characterized in that: described air cavity is filled with nitrogen or pressurized air in (10), and air cavity (10) internal pressure is 0.1Mpa～0.3Mpa.
5. nuclear reactor non-energy and multi-function pool voltage-stabling system according to claim 1 and 2, it is characterized in that: with top mark height between the loop is the balance water level of gravity water filling, and pressure accumulation pond (6) are equal to or greater than the summation of free volume between the hole of reactor (1) and loop in the water yield more than the balance water level.
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| CN2006100815366A CN101079333B (en) | 2006-05-26 | 2006-05-26 | Nuclear reactor non-energy and multi-function pool voltage-stabling system |
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| CN2006100815366A CN101079333B (en) | 2006-05-26 | 2006-05-26 | Nuclear reactor non-energy and multi-function pool voltage-stabling system |
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| CN101079333A true CN101079333A (en) | 2007-11-28 |
| CN101079333B CN101079333B (en) | 2010-07-14 |
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|---|---|---|---|---|
| CN101719386B (en) * | 2009-12-21 | 2012-07-04 | 肖宏才 | Entire passive shutdown safe cooling device of advanced pressurized water reactor nuclear power plant and operation program thereof |
| CN102693764A (en) * | 2011-03-21 | 2012-09-26 | 常州市福驰电动车辆科技有限公司 | Nuclear power station with reactor placed in pit |
| CN103511320A (en) * | 2012-06-28 | 2014-01-15 | 江苏核电有限公司 | Pressure stabilizing system of cooling lubrication loop of main pump radial thrust bearing |
| CN103545001A (en) * | 2012-07-12 | 2014-01-29 | 韩国原子力硏究院 | Passive safety injection system using safety injection tank |
| CN103727140A (en) * | 2012-10-11 | 2014-04-16 | 中国核动力研究设计院 | Non-active pressure-boosting pressure-stabilizing system capable of alleviating cavitation abrasion of water lubricated main-pump bearing |
| CN104112482A (en) * | 2014-07-30 | 2014-10-22 | 中科华核电技术研究院有限公司 | Passive self-flow control water injection system |
| CN104183284A (en) * | 2013-05-22 | 2014-12-03 | 中国核电工程有限公司 | ''Passive forced circulation'' heat exporting system |
| CN104332207A (en) * | 2013-07-22 | 2015-02-04 | 中国核动力研究设计院 | Method for automatically stopping coolant pump under reactor coolant loss accident condition |
| CN104347132A (en) * | 2013-07-26 | 2015-02-11 | 中广核工程有限公司 | Method for protecting main pump in nuclear power plant shutdown condition |
| CN104681108A (en) * | 2014-12-03 | 2015-06-03 | 中国科学院合肥物质科学研究院 | Passive natural circulation intensifying system and method for liquid metal cooled reactor after flow loss |
| CN104979024A (en) * | 2015-05-20 | 2015-10-14 | 中国核动力研究设计院 | Passive pressure-relief, water-injection and cooling system for floating nuclear power plant and operation method therefor |
| WO2016078285A1 (en) * | 2014-11-19 | 2016-05-26 | 中科华核电技术研究院有限公司 | Secondary side passive waste heat removal system |
| CN105654994A (en) * | 2014-12-01 | 2016-06-08 | 上海核工程研究设计院 | Pressure stabilizer of integral reactor |
| CN109300556A (en) * | 2018-09-19 | 2019-02-01 | 中广核研究院有限公司 | A kind of reactor voltage-stabilizing system having peace pouring functions |
| GB2524453B (en) * | 2013-08-01 | 2020-06-17 | China Nuclear Power Eng Co Ltd | Safety injection system of a hot leg of a nuclear power station |
| CN111383782A (en) * | 2018-12-28 | 2020-07-07 | 国家电投集团科学技术研究院有限公司 | Passive safety system and pressurized water reactor with same |
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| JPS584999B2 (en) * | 1978-09-22 | 1983-01-28 | 株式会社日立製作所 | Control method for reactor residual heat removal system |
| FI90596C (en) * | 1991-04-22 | 1994-02-25 | Vaisala Oy | Method and apparatus for measuring the meteorological visibility of the prevailing weather |
| KR0121554B1 (en) * | 1993-11-29 | 1997-11-22 | 임용규 | Mid-loop operating method for nuclear power plant, and facility therefor |
| CN1208781C (en) * | 2002-12-27 | 2005-06-29 | 中国核动力研究设计院 | Low temperature heat supply reactor having high safety |
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| CN101719386B (en) * | 2009-12-21 | 2012-07-04 | 肖宏才 | Entire passive shutdown safe cooling device of advanced pressurized water reactor nuclear power plant and operation program thereof |
| CN102693764A (en) * | 2011-03-21 | 2012-09-26 | 常州市福驰电动车辆科技有限公司 | Nuclear power station with reactor placed in pit |
| CN103511320A (en) * | 2012-06-28 | 2014-01-15 | 江苏核电有限公司 | Pressure stabilizing system of cooling lubrication loop of main pump radial thrust bearing |
| CN103545001A (en) * | 2012-07-12 | 2014-01-29 | 韩国原子力硏究院 | Passive safety injection system using safety injection tank |
| CN103545001B (en) * | 2012-07-12 | 2016-08-17 | 韩国原子力硏究院 | Use the passive safety injection system of Safety Injection case |
| CN103727140A (en) * | 2012-10-11 | 2014-04-16 | 中国核动力研究设计院 | Non-active pressure-boosting pressure-stabilizing system capable of alleviating cavitation abrasion of water lubricated main-pump bearing |
| CN103727140B (en) * | 2012-10-11 | 2016-07-06 | 中国核动力研究设计院 | The passive supercharging voltage-stabilizing system of water lubrication main pump bearing cavitation abrasion can be alleviated |
| CN104183284A (en) * | 2013-05-22 | 2014-12-03 | 中国核电工程有限公司 | ''Passive forced circulation'' heat exporting system |
| CN104332207B (en) * | 2013-07-22 | 2017-01-18 | 中国核动力研究设计院 | Method for automatically stopping coolant pump under reactor coolant loss accident condition |
| CN104332207A (en) * | 2013-07-22 | 2015-02-04 | 中国核动力研究设计院 | Method for automatically stopping coolant pump under reactor coolant loss accident condition |
| CN104347132A (en) * | 2013-07-26 | 2015-02-11 | 中广核工程有限公司 | Method for protecting main pump in nuclear power plant shutdown condition |
| GB2524453B (en) * | 2013-08-01 | 2020-06-17 | China Nuclear Power Eng Co Ltd | Safety injection system of a hot leg of a nuclear power station |
| CN104112482A (en) * | 2014-07-30 | 2014-10-22 | 中科华核电技术研究院有限公司 | Passive self-flow control water injection system |
| GB2535848A (en) * | 2014-11-19 | 2016-08-31 | China Nuclear Power Technology Res Inst Co Ltd | Secondary side passive waste heat removal system |
| WO2016078285A1 (en) * | 2014-11-19 | 2016-05-26 | 中科华核电技术研究院有限公司 | Secondary side passive waste heat removal system |
| GB2535848B (en) * | 2014-11-19 | 2020-05-06 | China Nuclear Power Technology Res Inst Co Ltd | Secondary side passive residual heat removal system |
| CN105654994A (en) * | 2014-12-01 | 2016-06-08 | 上海核工程研究设计院 | Pressure stabilizer of integral reactor |
| CN104681108B (en) * | 2014-12-03 | 2017-03-29 | 中国科学院合肥物质科学研究院 | Passive natural circulation consolidation system and method after a kind of liquid-metal cooled reactor defluidization |
| CN104681108A (en) * | 2014-12-03 | 2015-06-03 | 中国科学院合肥物质科学研究院 | Passive natural circulation intensifying system and method for liquid metal cooled reactor after flow loss |
| CN104979024A (en) * | 2015-05-20 | 2015-10-14 | 中国核动力研究设计院 | Passive pressure-relief, water-injection and cooling system for floating nuclear power plant and operation method therefor |
| CN109300556A (en) * | 2018-09-19 | 2019-02-01 | 中广核研究院有限公司 | A kind of reactor voltage-stabilizing system having peace pouring functions |
| CN111383782A (en) * | 2018-12-28 | 2020-07-07 | 国家电投集团科学技术研究院有限公司 | Passive safety system and pressurized water reactor with same |
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