CN1941217A - Special non-kinetic safety equipment of reactor - Google Patents
Special non-kinetic safety equipment of reactor Download PDFInfo
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- CN1941217A CN1941217A CNA2005101056486A CN200510105648A CN1941217A CN 1941217 A CN1941217 A CN 1941217A CN A2005101056486 A CNA2005101056486 A CN A2005101056486A CN 200510105648 A CN200510105648 A CN 200510105648A CN 1941217 A CN1941217 A CN 1941217A
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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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Abstract
A special-designed motionless safety reactor study and low temperature heat input reactor facilities in nuclear reactor field. To the side of the reactor installed a large volume water pool whose top is 10-30 meters higher than the reactor top. To the bottom of the water pool a water injection pipe is linked to the reactor inlet, a pipe linked to the reactor outlet is connected to the pool and in a position higher than water level. Outside the plant there is an emergency water tank which is 25-28 meters higher than the main heat exchanger and an air cooler which is 15-18 meters higher than the main heat exchanger. Both the water tank and the air cooler are linked to the recycle pipe between the main heat exchanger and the second heat exchanger.
Description
Technical field
The present invention relates to the nuclear reactor technology field, be specially a kind of special non-kinetic safety equipment that is applicable to low temperature heating reactor and research reactor.
Background technology
Utilizing nuclear heating is an important means that solves heating and desalinization.Although low-temperature heat supply nuclear reactor conceptual design kind is a lot of both at home and abroad at present, but because economy and security are not also accepted extensively by people, especially low temperature heating reactor can not be too far away apart from densely populated zone, nuclear safety is even more important, therefore will seek the higher and cheap heap type of inherent safety, this is the key that decision nuclear heating heap is promoted.
At present, nuclear power station is provided with complicated safety injection system, waste heat guiding system and voltage-stabilizing system for guaranteeing the safety of reactor.Adopt the security system setting of nuclear power station also can solve nuclear safety problems such as the emergent reactor core cooling of low temperature heating reactor, emergent waste heat discharge.But the security system structure relative complex of nuclear power station, active component is many, needs regular detection and maintenance, more needs operating personnel's proper operation just can make system finish its design function after accident takes place, lack non-energy dynamic characteristic, and its construction is all relative with operating cost higher.
Summary of the invention
The objective of the invention is to design a kind of special non-kinetic safety equipment that is applicable to low temperature heating reactor, research reactor, to guarantee the safety of reactor assembly.
Technical scheme of the present invention is as follows: a kind of special non-kinetic safety equipment of reactor, be provided with a pressure accumulation pond that exceeds 10～30 meters at reactor core top in reactor vessel one side, the pressure accumulation basin bottom is provided with and piles the water injection pipe that entrance cavity communicates, and the tedge of being drawn by the heap outlet plenum passes the pond and exceeds the pond water surface.
Aforesaid special non-kinetic safety equipment of reactor, wherein, outside reactor building, be provided with the emergent water injecting tank that exceeds 25～28 meters of main heat exchangers, with the air cooler that exceeds 15～18 meters of main heat exchangers, air cooler is arranged in the air cooling tower, air cooler top is provided with the water storage tank that is communicated with air cooler, and meet an urgent need water injecting tank and air cooler all are connected on the secondary circuit pipeline between main heat exchanger and the secondary heat exchange device by pipeline.
Special non-kinetic safety equipment provided by the present invention is simple relatively on the structure when finishing the nuclear reactor safety function, there is not active component, can put into operation automatically timely and effectively under the accident conditions, especially any valve that need not to move can be realized waste heat derivation and safety injection, effectively raise the inherent safety of reactor, accident takes place not need personnel to interfere in back 24 hours and can guarantee reactor safety, make reactor core never melt, never burn, under anything event operating mode, all satisfy requirement environment " "dead" consequence ".
Description of drawings
Fig. 1 is the structural representation of special non-kinetic safety equipment of reactor.
1. pressure accumulation ponds, 2. water injection pipes, 3. tedges, 4. emergent water injecting tank 5. air cooling towers 6. water storage tanks 7. air coolers 8. main heat exchangers 9. reactor vessels among the figure
Embodiment
As shown in Figure 1, be provided with a high capacity pressure accumulation pond 1 that exceeds 10～30 meters at reactor core top in reactor vessel 9 one sides, 1 bottom, pressure accumulation pond is provided with a water injection pipe 2 that communicates with the heap entrance cavity, and a tedge 3 of being drawn by the heap outlet plenum passes the pond and exceeds the pond water surface.When normal operation, keep reactor core pressure by pressure accumulation pond 1, water injection pipe 3.
When hoisting power or power swing, realize the volume fluctuations of temperature variation by water injection pipe 3.
Under pipeline large break accident, reactor core pressure descends rapidly, and this moment, pressure accumulation pond 1 to a large amount of water fillings of reactor core, made reactor core be in floodage forever by potential difference, after water is full of between major loop, still utilized pressure accumulation pond 1 to keep reactor core pressure.
Be provided with outside reactor building and exceed main heat exchanger 84, one about 25～28 meters of emergent water injecting tanks and exceed about 15～18 meters air cooler 7 of main heat exchanger 8, air cooler 7 is arranged in the air cooling tower 5, and air cooler 7 tops are provided with the water storage tank 6 that is communicated with air cooler 7.Emergent water injecting tank 4 and air cooler 7 all are connected on the secondary circuit pipeline between main heat exchanger and the secondary heat exchange device by pipeline.
When normal operation, the water balance that keep-ups pressure in secondary circuit circulating-pump outlet pressure head and the high-order emergent water injecting tank 4.
After the outage emergency shut-down, secondary circuit circulating-pump outlet pressure head disappears, water injects cold section of secondary circuit rapidly by potential difference in the emergent water injecting tank 4, heat after the secondary circuit hot arc is got back in the water storage tank 6 on air cooler 7 tops by main heat exchanger, this water storage tank 6 is communicated with air cooler 7, water injects the water junction and injects cold section of secondary circuit again in the water storage tank 6 after air cooler 7 is by the air cooling and in the emergent water injecting tank 4, and constantly the reactor core heat is taken in circulation out of.
At the emergency shut-down initial stage, because the removal of load influence, the heat that reactor core discharges will increase sharply at short notice, just reduce gradually after arriving a peak value.For spending this power peak period, emergent water injecting tank inner cold water injects secondary circuit rapidly with given pace and takes the reactor core heat out of through main heat exchanger, realizes the emergent cooling to reactor core.In the process that realizes this emergent cooling, set up the Natural Circulation between air cooler and the main heat exchanger simultaneously, in the emergency shut-down later stage, after promptly emergent water injecting tank inner cold water has been annotated, rely on this Natural Circulation for a long time the residue heat release that reactor core produces to be exported in the atmosphere timely and effectively, realize long-term cooling reactor core.
Claims (2)
1. special non-kinetic safety equipment of reactor, it is characterized in that: be provided with a pressure accumulation pond (1) that exceeds 10～30 meters at reactor core top in reactor vessel (9) one sides, bottom, pressure accumulation pond (1) is provided with and piles the water injection pipe (2) that entrance cavity communicates, and the tedge (3) of being drawn by the heap outlet plenum passes the pond and exceeds the pond water surface.
2. special non-kinetic safety equipment of reactor as claimed in claim 1, it is characterized in that: outside reactor building, be provided with the emergent water injecting tank (4) that exceeds (8) 25～28 meters of main heat exchangers and exceed the air cooler (7) of (8) 15～18 meters of main heat exchangers, air cooler (7) is arranged in the air cooling tower (5), air cooler (7) top is provided with the water storage tank (6) that is communicated with air cooler (7), and meet an urgent need water injecting tank (4) and air cooler (7) all are connected on the secondary circuit pipeline between main heat exchanger and the secondary heat exchange device by pipeline.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN200510105648A CN100578682C (en) | 2005-09-29 | 2005-09-29 | Special non-kinetic safety equipment of reactor |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN200510105648A CN100578682C (en) | 2005-09-29 | 2005-09-29 | Special non-kinetic safety equipment of reactor |
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| Publication Number | Publication Date |
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| CN1941217A true CN1941217A (en) | 2007-04-04 |
| CN100578682C CN100578682C (en) | 2010-01-06 |
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| CN200510105648A Active CN100578682C (en) | 2005-09-29 | 2005-09-29 | Special non-kinetic safety equipment of reactor |
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Cited By (13)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102169733A (en) * | 2011-02-14 | 2011-08-31 | 中国核电工程有限公司 | Passive and active combined special safety system for nuclear power plant |
| CN102426864A (en) * | 2011-12-12 | 2012-04-25 | 曾祥炜 | Passive emergency cooling system for severe accident in reactor |
| CN102563590A (en) * | 2010-12-22 | 2012-07-11 | 清华大学 | Saturated steam generator |
| CN101521049B (en) * | 2008-02-29 | 2012-07-18 | 株式会社东芝 | Passive cooling and depressurization system and pressurized water nuclear power plant |
| CN103000233A (en) * | 2011-09-08 | 2013-03-27 | 韩电原子力燃料株式会社 | Passive cooling system of nuclear power plant |
| CN103310856A (en) * | 2013-05-20 | 2013-09-18 | 清华大学 | Pressurized water reactor power generation system with intrinsic safety |
| CN103377737A (en) * | 2012-04-27 | 2013-10-30 | 上海核工程研究设计院 | Wet-type spent fuel storage system |
| CN103778979A (en) * | 2012-10-22 | 2014-05-07 | 中国核动力研究设计院 | Secondary circuit coolant supply system and method for nuclear power station |
| CN104321826A (en) * | 2012-06-13 | 2015-01-28 | 西屋电气有限责任公司 | Combined core makeup tank and heat removal system for a small modular pressurized water reactor |
| CN104979023A (en) * | 2014-04-03 | 2015-10-14 | 国核（北京）科学技术研究院有限公司 | Passive containment heat exporting system and controlling method thereof, and pressurized water reactor |
| CN107393605A (en) * | 2017-07-07 | 2017-11-24 | 西安交通大学 | The passive air-cooling apparatus and method of a kind of modular small nuclear reactor |
| CN108665981A (en) * | 2018-07-03 | 2018-10-16 | 启迪新核（北京）能源科技有限公司 | The natural circulation cooling system and well formula normal pressure process heat reactor of well formula normal pressure process heat reactor |
| GB2564898A (en) * | 2017-07-27 | 2019-01-30 | Rolls Royce Power Eng Plc | Cooling system for a nuclear reactor |
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2005
- 2005-09-29 CN CN200510105648A patent/CN100578682C/en active Active
Cited By (22)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN101521049B (en) * | 2008-02-29 | 2012-07-18 | 株式会社东芝 | Passive cooling and depressurization system and pressurized water nuclear power plant |
| CN102563590B (en) * | 2010-12-22 | 2014-04-02 | 清华大学 | Saturated steam generator |
| CN102563590A (en) * | 2010-12-22 | 2012-07-11 | 清华大学 | Saturated steam generator |
| CN102169733A (en) * | 2011-02-14 | 2011-08-31 | 中国核电工程有限公司 | Passive and active combined special safety system for nuclear power plant |
| CN102169733B (en) * | 2011-02-14 | 2013-10-23 | 中国核电工程有限公司 | Passive and active combined special safety system for nuclear power plant |
| CN103000233B (en) * | 2011-09-08 | 2016-02-03 | 韩电原子力燃料株式会社 | Nuclear power station passive cooling systems |
| CN103000233A (en) * | 2011-09-08 | 2013-03-27 | 韩电原子力燃料株式会社 | Passive cooling system of nuclear power plant |
| CN102426864B (en) * | 2011-12-12 | 2014-03-26 | 曾祥炜 | Passive emergency cooling system for severe accident in reactor |
| CN102426864A (en) * | 2011-12-12 | 2012-04-25 | 曾祥炜 | Passive emergency cooling system for severe accident in reactor |
| CN103377737A (en) * | 2012-04-27 | 2013-10-30 | 上海核工程研究设计院 | Wet-type spent fuel storage system |
| CN103377737B (en) * | 2012-04-27 | 2015-12-02 | 上海核工程研究设计院 | A kind of wet-type spent fuel storage system |
| CN104321826B (en) * | 2012-06-13 | 2016-11-23 | 西屋电气有限责任公司 | Reactor core for the combination of little module pressurized water reactor feeds case and heat removal system |
| CN104321826A (en) * | 2012-06-13 | 2015-01-28 | 西屋电气有限责任公司 | Combined core makeup tank and heat removal system for a small modular pressurized water reactor |
| US9748004B2 (en) | 2012-06-13 | 2017-08-29 | Westinghouse Electric Company Llc | Combined core makeup tank and heat removal system for a small modular pressurized water reactor |
| CN103778979A (en) * | 2012-10-22 | 2014-05-07 | 中国核动力研究设计院 | Secondary circuit coolant supply system and method for nuclear power station |
| CN103310856A (en) * | 2013-05-20 | 2013-09-18 | 清华大学 | Pressurized water reactor power generation system with intrinsic safety |
| CN103310856B (en) * | 2013-05-20 | 2016-04-20 | 清华大学 | A kind of presurized water reactor electricity generation system with inherent safety |
| CN104979023A (en) * | 2014-04-03 | 2015-10-14 | 国核（北京）科学技术研究院有限公司 | Passive containment heat exporting system and controlling method thereof, and pressurized water reactor |
| CN104979023B (en) * | 2014-04-03 | 2017-12-22 | 国核（北京）科学技术研究院有限公司 | Passive containment thermal conduction system and its control method and pressurized water reactor |
| CN107393605A (en) * | 2017-07-07 | 2017-11-24 | 西安交通大学 | The passive air-cooling apparatus and method of a kind of modular small nuclear reactor |
| GB2564898A (en) * | 2017-07-27 | 2019-01-30 | Rolls Royce Power Eng Plc | Cooling system for a nuclear reactor |
| CN108665981A (en) * | 2018-07-03 | 2018-10-16 | 启迪新核（北京）能源科技有限公司 | The natural circulation cooling system and well formula normal pressure process heat reactor of well formula normal pressure process heat reactor |
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| Publication number | Publication date |
|---|---|
| CN100578682C (en) | 2010-01-06 |
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