CN105161145A - Method for improving effectiveness of IVR (in-vessel retention) of melt - Google Patents
Method for improving effectiveness of IVR (in-vessel retention) of melt Download PDFInfo
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- CN105161145A CN105161145A CN201510481065.7A CN201510481065A CN105161145A CN 105161145 A CN105161145 A CN 105161145A CN 201510481065 A CN201510481065 A CN 201510481065A CN 105161145 A CN105161145 A CN 105161145A
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- pressure vessel
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- filling
- filling pipe
- melt
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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
The invention discloses a method for improving effectiveness of IVR (in-vessel retention) of melt. The method comprises steps as follows: step one, pressure reduction of a main system is performed, and the inside of a pressure vessel is kept at the low pressure; step two, water injection is performed, wherein the water injection comprises outside water injection and inside water injection, the outside water injection is to inject water in a water injection source into the pressure vessel through a flow channel, and the inside water injection is to inject water in the water injection source into the pressure vessel through a water injection pipeline. With the method of inside water injection and outside water injection to the pressure vessel, the density of heat flux, transferred to the wall of the pressure vessel, of the melt is effectively reduced to be smaller than the density of critical heat flux of the pressure vessel after outer water cooling, the problem of influence caused by nondeterminacy of a physical phenomenon is solved in the aspect of engineering, and the effectiveness of the measure of IVR of the melt is improved.
Description
Technical field
The present invention relates to the interior delay of melt pressure container (IVR) technology of nuclear power plant, particularly relate to a kind of method improving delay validity in melt pressure container.
Background technology
(IVR) technology of being detained in melt pressure container refers to the integrality taking measures to keep pressure vessel under the condition of major accident occurs in nuclear power plant, thus means fused mass is trapped in pressure vessel, the method of usual employing is by water piii reactor heap chamber, reactor pressure vessel is made to be dipped in water, rely on the boiling heat transfer cooling pressure container wall of water, and shift out fused mass decay heat.IVR measure is applied comparatively widely because the advantages such as its embodiment is simple, implementation result is good obtain in the nuclear power plant run or building.
The successful necessary condition of IVR measure is that the heat flow density that fused mass reaches pressure vessel wall is less than the outer water cooling critical heat flux density of pressure vessel.But in some cases, the heat flow density reaching pressure vessel wall due to fused mass is too large, and this necessary condition cannot meet.
Summary of the invention
Because the above-mentioned defect of prior art, technical matters to be solved by this invention is to provide a kind of method improving IVR measure validity under nuclear power plant's severe accident conditions, to improve the security of nuclear power plant.
For achieving the above object, the invention provides a kind of method improving delay validity in melt pressure container, said method comprising the steps of:
Step one, implements main system step-down, makes the inner sustain low pressure of described pressure vessel;
Step 2, water filling;
Wherein, described water filling comprises:
First aspect, the water in water filling water source is by the external water flood of runner to described pressure vessel;
Second aspect, the water in water filling water source is by the intracontour waterflooding of filling pipe to described pressure vessel;
Described first aspect is implemented prior to described second aspect, or described second aspect is implemented prior to described first aspect, or described first aspect and described second aspect are implemented simultaneously.
Further, in described step one, the cut relying on described main system to exist or dependence unloading pressure means implement main system step-down, make the inner sustain low pressure of described pressure vessel.
Further, described water filling for relying on the natural force such as gravity, pressure gas, or is realized by active equipment such as pumps.
Further, described water filling water source is provided with one or more.
Further, described runner is provided with one or more.
Further, described filling pipe is one or more.
Further, described filling pipe is any one or more combination in the first filling pipe, the second filling pipe and the 3rd filling pipe.
Further, described first filling pipe is communicated with described pressure vessel with cold leg respectively by heat pipe section with described second filling pipe; Described 3rd filling pipe is directly communicated with the sidewall of described pressure vessel.
Further, described water filling water source and described filling pipe are the existing water source of power plant and pipeline or the water source set up in addition and pipeline.
Further, in described step 2, water enters by described runner the space that the sidewall and base plate that are positioned at described pressure vessel outside and described pressure vessel formed, and described pressure leaching vessel is ducked in drink.
Further, the water of the outside of described pressure vessel cools the outside wall surface of described pressure vessel by the flowing of water or boiling heat transfer.
Further, the water entering the inside of described pressure vessel takes the heat of described fused mass out of by the mode of boiling, convection heat transfer' heat-transfer by convection, and the heat flow density that described fused mass is acted on the wall of described pressure vessel reduces.
In a better embodiment of the present invention, when there is major accident in nuclear power plant, reactor core melts, in the process, on the one hand by the external water flood to pressure vessel of gravity or pump, rely on the other hand cut or unloading pressure means to make the pressure that described pressure vessel inner sustain is lower, utilize gravity or pump to the intracontour waterflooding of described pressure vessel, to realize being detained in melt pressure container by filling pipe.
In raising melt pressure container of the present invention, the feature of the method for delay validity is the inside and outside water filling to pressure vessel.The outside wall surface of pressure vessel can be made directly to contact with water to pressure vessel external water flood, rely on the flowing heat transfer of water or the outside wall surface of boiling heat transfer mode cooling pressure container, make the outside wall surface of pressure vessel maintain lower temperature.Effectively cooled making the fused mass in pressure vessel to pressure vessel intracontour waterflooding, even if very the injection of low discharge also will reduce fused mass and reach the heat flow density of pressure vessel wall greatly, it is made to be less than outside wall surface critical heat flux density, the uncertain impact brought of physical phenomenon is solved from engineering viewpoint, improve IVR validity, thus improve the security of nuclear power plant.
The advantage of being detained the method for validity in raising melt pressure container of the present invention is:
(1) implementation is simple, flexibly, by gravity or utilize pump to the inside and outside water filling of pressure vessel;
(2) implementation result is good, relies on pressure vessel external water flood that greater probability can be had to maintain pressure vessel complete, now, even if less to the flow of pressure vessel intracontour waterflooding, also will conscientiously improve IVR validity.
The present invention improves the validity of IVR in a simpler way, thus improves the security of nuclear power plant.
Be described further below with reference to the technique effect of accompanying drawing to design of the present invention, concrete structure and generation, to understand object of the present invention, characteristic sum effect fully.
Accompanying drawing explanation
Fig. 1 be a preferred embodiment of the present invention pressure vessel in reactor core intact time schematic diagram;
Fig. 2 be a preferred embodiment of the present invention pressure vessel in reactor core dissolve rear formation molten bath and by the schematic diagram after water filling.
Embodiment
As shown in Figure 1, under normal circumstances, reactor core 2 is intact and be positioned at the inside of pressure vessel 1.
As shown in Figure 2, a preferred embodiment of the present invention provides a kind of method improving delay validity in melt pressure container, said method comprising the steps of:
Step one, implements main system step-down: after major accident occurs in nuclear power plant, reactor core 2 will melt, move, and as shown in Figure 2, the fused mass 12 after reactor core 2 melts is gathered in the interior formation molten bath of end socket 3 of the bottom of pressure vessel 1.Before reactor core 2 melts, in fusion process or after fusing, the cut relying on main system to exist or dependence unloading pressure means implement main system step-down, make the inner sustain low pressure of pressure vessel 1.
" low pressure " is herein relative to the high pressure of reactor, in normal operation, the pressure of reactor is very high, such as pressure reaches 150 atmospheric pressure, therefore under accident conditions, make pressure vessel inner sustain in several, even 1 atmospheric level by cut or step-down means, be low pressure.
Step 2, water filling.
The water filling of the present embodiment comprises following two aspects:
First aspect, water in water filling water source by runner 11 to the external water flood of pressure vessel: melt at reactor core 2, in transition process, water enters by runner 11 space that the sidewall 9 that is positioned at pressure vessel 1 outside and base plate 10 formed with pressure vessel 1, make pressure vessel 1 be immersed in water, rely on the flowing of water or boiling heat transfer to carry out the outside wall surface of cooling pressure container 1.Wherein, runner 11 can be arranged on the below of pressure vessel 1 or sidepiece or other position.
Second aspect, the water in water filling water source is by the intracontour waterflooding of filling pipe to described pressure vessel 1.
In the present embodiment, external water flood to pressure vessel 1 and the intracontour waterflooding to pressure vessel 1 can occur simultaneously, also can first to the external water flood of pressure vessel 1 again to the intracontour waterflooding of pressure vessel 1, or first to the intracontour waterflooding of pressure vessel 1 again to the external water flood of pressure vessel 1.
The water filling water source of the present embodiment, runner and filling pipe all can be set to one or more.
Particularly, the intracontour waterflooding to pressure vessel 1 can pass through following path, as shown in Figure 2:
(1) by being connected to the first filling pipe 6 in heat pipe section 4, current enter the inside of pressure vessel 1 through superheater tube section 4, realize the cooling of fused mass 12 top.
(2) by being connected to the second filling pipe 7 on cold leg 5, current enter the inside of pressure vessel through cold leg 5, realize the cooling of fused mass 12 top.
(3) by being connected to the 3rd filling pipe 8 on pressure vessel sidewall, it is inner that current directly enter pressure vessel 1 through the 3rd filling pipe 8, carries out top cooling to fused mass 12.
Wherein, the first filling pipe 6 is communicated with pressure vessel 1 with cold leg 5 respectively by heat pipe section 4 with the second filling pipe 7, and heat pipe section 4 and cold leg 5 lay respectively at the both sides, top of pressure vessel 1.3rd filling pipe 8 is directly communicated with the sidewall of pressure vessel 1.
Realize melt pressure container 1 internal cooling to be realized by an above-mentioned paths or mulitpath.The water entering the inside of pressure vessel 1 takes the heat of fused mass 12 out of by the mode of boiling, convection heat transfer' heat-transfer by convection, the heat flow density that fused mass 12 is acted on the wall of pressure vessel 1 reduces greatly, improve fused mass 12 and be trapped in reliability in pressure vessel 1, also improve the security of nuclear power plant simultaneously.
The water filling water source of the present embodiment and filling pipe can be the existing water source of power plant and pipeline, also can be the water source and pipeline set up in addition
In the present embodiment, water filling for relying on the natural force such as gravity, pressure gas, or is realized by active equipment such as pumps.
Pay particular attention to, above-mentioned pipeline is heat pipe section 4, cold leg 5, the first filling pipe 6 be connected in heat pipe section 4, the 3rd filling pipe 8 that is connected to the second filling pipe 7 on cold leg 5 and is connected on pressure vessel 1 such as, these pipelines may refer to a pipeline, but more possible a kind of situation refers to one group of pipeline, and its quantity is determined by the different designs of power plant.
More than describe preferred embodiment of the present invention in detail.Should be appreciated that those of ordinary skill in the art just design according to the present invention can make many modifications and variations without the need to creative work.Therefore, all technician in the art, all should by the determined protection domain of claims under this invention's idea on the basis of existing technology by the available technical scheme of logical analysis, reasoning, or a limited experiment.
Claims (9)
1. improve a method of being detained validity in melt pressure container, it is characterized in that, comprise the following steps:
Step one, implements main system step-down, makes the inner sustain low pressure of described pressure vessel;
Step 2, water filling;
Wherein, described water filling comprises:
First aspect, the water in water filling water source is by the external water flood of runner to described pressure vessel;
Second aspect, the water in water filling water source is by the intracontour waterflooding of filling pipe to described pressure vessel;
Described first aspect is implemented prior to described second aspect, or described second aspect is implemented prior to described first aspect, or described first aspect and described second aspect are implemented simultaneously.
2. the method improving delay validity in melt pressure container as claimed in claim 1, it is characterized in that, in described step one, the cut relying on described main system to exist or dependence unloading pressure means implement main system step-down, make the inner sustain low pressure of described pressure vessel.
3. the method improving delay validity in melt pressure container as claimed in claim 1, is characterized in that, described water filling for relying on the natural force such as gravity, pressure gas, or is realized by active equipment such as pumps.
4. the method improving delay validity in melt pressure container as claimed in claim 1, it is characterized in that, described water filling water source, described runner or described filling pipe are provided with one or more.
5. the method improving delay validity in melt pressure container as claimed in claim 1, it is characterized in that, described filling pipe is any one or more combination in the first filling pipe, the second filling pipe and the 3rd filling pipe.
6. the method improving delay validity in melt pressure container as claimed in claim 5, it is characterized in that, described first filling pipe is communicated with described pressure vessel with cold leg respectively by heat pipe section with described second filling pipe; Described 3rd filling pipe is directly communicated with the sidewall of described pressure vessel.
7. as claimed in claim 1 improve the method for being detained validity in melt pressure container, it is characterized in that, described water filling water source and described filling pipe are the existing water source of power plant and pipeline or the water source set up in addition and pipeline.
8. the method improving delay validity in melt pressure container as claimed in claim 1, it is characterized in that, in described step 2, water enters by described runner the space that the sidewall and base plate that are positioned at described pressure vessel outside and described pressure vessel formed, and described pressure leaching vessel is ducked in drink.
9. as claimed in claim 1 improve the method for being detained validity in melt pressure container, it is characterized in that, the water of the outside of described pressure vessel cools the outside wall surface of described pressure vessel by the flowing of water or boiling heat transfer; The water entering the inside of described pressure vessel takes the heat of described fused mass out of by the mode of boiling, convection heat transfer' heat-transfer by convection, and the heat flow density that described fused mass is acted on the wall of described pressure vessel reduces.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201510481065.7A CN105161145A (en) | 2015-08-03 | 2015-08-03 | Method for improving effectiveness of IVR (in-vessel retention) of melt |
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| CN201510481065.7A CN105161145A (en) | 2015-08-03 | 2015-08-03 | Method for improving effectiveness of IVR (in-vessel retention) of melt |
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| CN105161145A true CN105161145A (en) | 2015-12-16 |
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| CN201510481065.7A Pending CN105161145A (en) | 2015-08-03 | 2015-08-03 | Method for improving effectiveness of IVR (in-vessel retention) of melt |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109346196A (en) * | 2018-11-13 | 2019-02-15 | 中国核动力研究设计院 | Gaseous-waste holdup system in the fusant heap that a kind of active and passive cooling combines |
| WO2021128059A1 (en) * | 2019-12-25 | 2021-07-01 | 中广核研究院有限公司 | Test system for simulating rpv heat exchange characteristics of nuclear power plant, and heating and temperature measuring device |
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| CN104051030A (en) * | 2013-09-16 | 2014-09-17 | 国核（北京）科学技术研究院有限公司 | Passive core melt trapping system |
| CN104167229A (en) * | 2014-04-24 | 2014-11-26 | 国核华清（北京）核电技术研发中心有限公司 | Passive containment shell condensed water injection system |
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2015
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Patent Citations (3)
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| CN103426484A (en) * | 2012-05-25 | 2013-12-04 | 国家核电技术有限公司 | Method used for preventing pressure vessels from melting damages caused by molten materials in reactors, and system used for method |
| CN104051030A (en) * | 2013-09-16 | 2014-09-17 | 国核（北京）科学技术研究院有限公司 | Passive core melt trapping system |
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Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109346196A (en) * | 2018-11-13 | 2019-02-15 | 中国核动力研究设计院 | Gaseous-waste holdup system in the fusant heap that a kind of active and passive cooling combines |
| CN109346196B (en) * | 2018-11-13 | 2022-04-15 | 中国核动力研究设计院 | Active and passive cooling combined molten material in-pile retention system |
| WO2021128059A1 (en) * | 2019-12-25 | 2021-07-01 | 中广核研究院有限公司 | Test system for simulating rpv heat exchange characteristics of nuclear power plant, and heating and temperature measuring device |
| GB2606246A (en) * | 2019-12-25 | 2022-11-02 | China Nuclear Power Technology Res Inst Co Ltd | Test system for simulating RPV heat exchange characteristics of nuclear power plant, and heating and temperature measuring device |
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Application publication date: 20151216 |