CN1174381A - Reactor cavity flooding system - Google Patents
Reactor cavity flooding system Download PDFInfo
- Publication number
- CN1174381A CN1174381A CN97113391A CN97113391A CN1174381A CN 1174381 A CN1174381 A CN 1174381A CN 97113391 A CN97113391 A CN 97113391A CN 97113391 A CN97113391 A CN 97113391A CN 1174381 A CN1174381 A CN 1174381A
- Authority
- CN
- China
- Prior art keywords
- water
- reactor
- pressure vessel
- load chamber
- containment shell
- 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.)
- Granted
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
-
- 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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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
In order to ensure enough water will be fed into a reactor cavity during the process that a pressure vessel is cracked and a fuel assembly is leaked, the water cumulated in a water pool adjacent to the reactor cavity is fed into the reactor cavity through a conduit which connected with them. The conduit is kept closed by a remote valve unless it receives an instruction for water supply, in order to keep the depth of the water cumulated in a frame groove under the reactor cavity and in the reactor pressure vessel, thereby protects various devices disposed in the frame groove and/or the cavity.
Description
The present invention relates generally to nuclear reactor.More particularly, the present invention relates to a kind of equipment relevant with nuclear reactor, this equipment can water filling in the containment shell building of loading reactor when reactor takes place to be scheduled to accident.
In the major accident process that exceeds nuclear power plant's design code incident, reactor vessel might break, thereby the most nuclear reactor that will burn is discharged in the containment shell building.Major accident occurs in the following situation: (1) is if the safe injection system can't carry chilled water in reactor vessel before nuclear fuel cools off fully; (2) if reactor vessel breaks, the most reactor core (fuel assembly promptly mainly is the core material potpourri of fuel and steel) that burns can be discharged in core device (ICI) the frame groove below the reactor vessel.In ICI frame groove, carry chilled water can reduce the possibility that fuel assembly leaks out from the containment shell building.
More particularly, in the reactor cooling system water pipe breaks incident (being a kind of design code incident), the water in the safe injection jar is discharged in the reactor vessel so that reactor core is cooled off.After above-mentioned discharging, utilize the safe injection pump that the water in the refuel water tank (RWST) is drawn in the reactor vessel, and by the containment shell spraying system with in the water spirt containment shell to be condensate in the water vapor that produces in the containment shell building.In case the water in the refuel water tank (RWST) exhausts, water pump can change operating path again, the water that draws water and leak from the reactor coolant water system from the emergent reactor core chilled water storage jar that is arranged in containment shell building with the repetitive cycling utilization, and from the containment shell spraying system, eject.
If for a certain reason, the safe injection pump can not continue water is pumped in the reactor vessel, just is easy to take place major accident, and fuel assembly flows out into from the crack of reactor vessel in core device (ICI) the frame groove.The chilled water that fuel assembly needs sufficient amount does not break to guarantee the containment shell building, will cause radiomaterial to enter in the atmosphere if break.
Yet because the xsect that the containment shell spraying system is built with respect to containment shell is evenly to spray, the share of spraying the water that enters the reactor load chamber equals the area of reactor vessel and the ratio of containment shell cross-sectional area substantially.Therefore, limit the water that makes injection and mainly be accumulated in ratio in the high-risk zone.
An object of the present invention is to provide a kind of simple relatively equipment, this equipment is except tending to injection water is accumulated in the reactor load chamber when the containment shell spraying system sprays, and can carry more water to the reactor load chamber as required.
In brief, above-mentioned purpose is realized by a kind of like this equipment, in this equipment, be accumulated in a pond and can replenish by a conduit that connects two-part structure as the water that is arranged near the refuel pond the reactor load chamber and be input to the reactor load chamber.Need supplementary water injection unless obtain instruction; usually this conduit keeps closed condition under the control of a remote control valve; so that be accumulated in the degree of depth minimum of the water of the frame groove neutralization reaction heap container that is arranged in below the reactor load chamber, thereby protection is arranged in this groove and/or the various devices in the load chamber.
More particularly, a first aspect of the present invention relates to a kind of nuclear reactor cavity flooding system, this system comprises: the jetting system that is used for selectively water being sprayed into the containment shell building interior, this device draws water from predetermined water source, is mounted with reactor pressure vessel and adjacent refuel pool construction that holds the reactor load chamber in said containment shell building; The pipe guide that controllably connects a said pond and a frame groove, said groove are communicated with the reactor load chamber and are positioned at below the reactor; And be used to be controlled at the by-pass valve control the selected device of fluid flow between said pond and said the groove below reactor pressure vessel.
A second aspect of the present invention relates to a kind of safety equipment that are used for nuclear reactor containment shell building, it is characterized in that it comprises: be used for when first scheduled event takes place water sprayed into said containment shell jetting system building, that comprise a water tank; Be formed on reactor load chamber in the said containment shell building, make the position that the water that ejects can accumulate from jetting system, this reactor load chamber is used to load reactor pressure vessel; Be communicated with the bottom of said reactor load chamber and be positioned at a frame groove below the said reactor pressure vessel; Be arranged in a pond of the position that the water that sprays from jetting system can accumulate, the bottom position in said pond is higher than said the groove that is arranged on said load chamber bottom; With said pond and said the passage that the concentrated flow body is communicated with; Usually be in the valving of closed condition, this valving is arranged in the said passage, is used for opening said passage selectively under predetermined state so that collect in the water in said pond and can be discharged in the said load chamber when second scheduled event takes place.
A third aspect of the present invention relates to a kind of method of water filling in the load chamber that nuclear reactor is set, and this method may further comprise the steps: when first incident of generation water is sprayed in the containment shell building; The water that sprays in the containment shell building is accumulated in the reactor vessel load chamber; Be accumulated in a near pond that is arranged in the reactor pressure vessel load chamber with spraying into water in the containment shell building; With when second scheduled event takes place, will be accumulated in the bottom that water in the said pond is discharged into said reactor pressure vessel load chamber.
Another aspect of the present invention relates to a kind of equipment that is used for to the load chamber water filling of loading nuclear reactor pressure container, and this equipment comprises: be used for when first incident of generation water sprayed into the device in the containment shell building; Be used for to spray into the device that the interior water of containment shell building is accumulated in the reactor vessel load chamber; The water that is used for will spraying in the containment shell building is accumulated in the device that is positioned at a near pond of said reactor pressure vessel load chamber; Be discharged into the device of the bottom of said reactor pressure vessel load chamber with the water that is used for when second scheduled event takes place, will being accumulated in said pond.
By the detailed description of preferred embodiment being done below in conjunction with accompanying drawing, it is clearer that various advantages and features of the present invention will become.
Fig. 1 is the vertical cross section of expression one embodiment of the present of invention.
According to the present invention, a part of injection water enters in the refuel pond 100 shown in Figure 1, and is accumulated in the zone that is lower than reactor vessel flange 102.These zone formation bottom reactor components or reactor core stop sleeve (CSB) and top reactor component or upper guide are to the water reserve of shelf structure (UGS).As mentioned above, because the containment shell spraying system represented with reference number 104 in Fig. 1 is evenly to spray with respect to the xsect of containment shell building 106, the share that is accumulated in the water in the refuel pond 100 equals the ratio of the interior cross-sectional area that sump area and containment shell build substantially.This area ratio is approximately 8% in the illustrated embodiment, and the flow rate minimum of containment shell jetting pump 108 is 3500 gallon per minute.So, after pump water operation is carried out 3 hours, extracted about 50000 gallons water and be accumulated in the CSB zone in refuel pond 100.After about 7 hours, the water yield that said CSB accumulates in the zone reaches its capacity, promptly 105000 gallons.
The reactor core stop sleeve (CSB) that is accumulated in refuel pond 100 is if the water in the zone is discharged in core device (ICI) the frame groove 112, just can cool off fuel assembly.So according to the present invention, in order to utilize these water, be provided with a water pipe or conduit 110 so that core device (ICI) frame groove 112 fluids of the bottom in reactor core stop sleeve (CSB) zone in refuel pond 100 below being arranged in reactor load chamber 113 reactor pressure vessels 114 are communicated with.Therefore, this root water pipe 110 has formed a kind of connected relation, otherwise is this conveying that impossible realize water.Be equipped with a remote control valve 116 on the water pipe 110, this valve is arranged in and is arranged on the following canyon 118 in reactor core stop sleeve (CSB) zone.
Valve 116 is normally closed, and by 120 controls of a starting switch, this switch must not have locked before valve 116 can be opened.At least owing to two reasons, require Locked valve must have above-mentioned feature.The first, in the refuelling operating process, must prevent from from refuel pond 100, to draw water, because in this operating process, reactor internal will take out from reactor pressure vessel 114, perhaps to handle, if lack of water just may form high radiant quantity fuel.And, must keep water to transfer to the cooling of the fuel the guarantee fuel pond from pressure vessel 114.
Needing second reason of locking starting switch 120 is to be discharged into prematurely in core device (ICI) the frame groove 112 for the water in reactor core stop sleeve (CSB) zone that prevents refuel pond 100.When taking place to start the incident of containment shell spraying system unintentionally, owing to structural reason, should limit the water yield that flows in core device (ICI) the frame groove 112 and unnecessarily surpass the outside surface of core device (ICI) guide pipe and reactor pressure vessel 114 to prevent the water plane.In addition, if spraying system safe in utilization and containment shell spraying system are controlled the generation (being exactly to make in the reactor vessel to break) of this incident, owing to structural reason, the water logging that the outside surface of core device (ICI) guide pipe and reactor pressure vessel 114 should not be filled with in core device (ICI) the frame groove 112 does not have equally.
In more detail, when reactor cooling system (RCS) when break in the pressure boundary, major accident will take place.This incident is called as cooling forfeiture accident (LOCA).On the whole, has multiple effect to 113 water fillings of reactor load chamber for alleviating the consequence that this accident causes.These effects comprise: (1) makes fuel assembly minimum or elimination to concrete destruction; (2) make the generation of inflammable gas (hydrogen and carbon monoxide) minimum or eliminate; (3) reduce the release of the fusion products that produce owing to fuel assembly and concrete interaction; (4) clean the fusion products that from the reactor core remains of accumulating, discharge.In illustrated embodiment, be provided with a frame groove 112 base plate 112A, so that fuel assembly can be dispersed on the enough big area, thereby can utilize the water that injects frame groove 112 that it is cooled off.
The water filling of reactor load chamber normally utilizes existing emergent reactor core cooling (ECC) water source to finish.These water sources, just schematically represented in the accompanying drawings for simplicity, comprise: from water reactor cooling system (RCS), that leak from the reactor cooling system pressure boundary, said cooling system schematically shows with label 122 in the accompanying drawings (1); (2) from safe injection pipe system 124, be discharged into water in the reactor cooling system 122; (3) pump to water reactor cooling system and the containment shell building 106 by safe injection pump 128 and containment shell spraying system pump 108 from refuel water tank (RWST) 126.
When generation safe injection pump can't pump into the incident of reactor cooling system 122 with water from refuel water tank (RWST) 126, serious accident can be developed in the crack in the reactor cooling system in very short time.In this case, the water in the refuel water tank (RWST) 126 is discharged in the water tank 120 of the emergent reactor core cooling water source (ECCS) in the containment shell building 106.Make water can flow in core device (ICI) the frame groove 112 with the tank connected conduit of water storage to cool off these fuel assemblies.
Safe injection pump 128 and containment shell spraying system 104 pump into water in reactor cooling system 122 and the containment shell building 106 from refuel water tank (RWST) 126, the water in water tank 126 exhausts.At this moment, this system changes operating path again, from emergence core stacking cool system water tank 130 water suction containment shell is built in 106.The water that is accumulated in these water tanks 130 is repeated to recycle with cooled reactor reactor core and injection containment shell building peripheral region.Because safe injection system and containment shell spraying system are designed in cooling forfeiture accident and play a role, the water in the refuel water tank very may just exhaust before these thrashings.
As mentioned above, containment shell spraying system 104 forms uniformly on the cross-sectional area of containment shell building 106 and sprays, though most of water flow back in the emergent reactor core cooling water source water tank again and repeats to recycle, and still has quite a few injection water to be accumulated in the refuel pond.Utilize the present invention, can reuse be accumulated in other place and break away from this part water in the repetitive cycling loop with the fuel assembly in cooling core device (ICI) the frame groove 112, and owing to the effect of gravity head, this part water can automatically flow in core device (ICI) the frame groove 112 when opening valve 116.
Though only disclose one embodiment of the present of invention here, but under the prerequisite that does not depart from the scope of the present invention, can make various changes and improvements, scope of the present invention is only defined by the appended claims, and this is self evident for the technician of the technical field of the invention.
Claims (8)
1. nuclear reactor cavity flooding system, this system comprises:
Be used for selectively water being sprayed into the jetting system of containment shell building interior, this device draws water from predetermined water source, is mounted with reactor pressure vessel and adjacent refuel pool construction that holds the reactor load chamber in said containment shell building;
The pipe guide that controllably connects a said pond and a frame groove, said groove are communicated with the reactor load chamber and are positioned at below the reactor; With
Be used to be controlled at the by-pass valve control the selected device of fluid flow between said pond and said the groove below reactor pressure vessel.
2. one kind is used for the safety equipment that the nuclear reactor containment shell is built, and this equipment comprises:
Be used for when first scheduled event takes place water sprayed into said containment shell jetting system building, that comprise a water tank;
Be formed on reactor load chamber in the said containment shell building, make the position that the water that ejects can accumulate from jetting system, this reactor load chamber is used to load reactor pressure vessel;
Be communicated with the bottom of said reactor load chamber and be positioned at a frame groove below the said reactor pressure vessel;
Be arranged in a refuel pond that makes the position that the water that sprays from jetting system can accumulate, the bottom position in said pond is higher than said the groove that is arranged on said load chamber bottom;
With said pond and said the passage that the concentrated flow body is communicated with; With
Usually be in the valving of closed condition, this valving is arranged in the said passage, is used for opening said passage selectively under predetermined state so that collect in the water in said pond and can be discharged in the said load chamber when second scheduled event takes place.
3. a kind of safety equipment as claimed in claim 2 is characterized in that: said first scheduled event is meant the incident that just can't supply water before the fuel cooling in reactor pressure vessel in reactor pressure vessel.
4. a kind of safety equipment as claimed in claim 2 is characterized in that: said valving comprises a switch of locking usually, and when second scheduled event took place, said switch unlocked.
5. a kind of safety equipment as claimed in claim 4, it is characterized in that: said second scheduled event is meant that reactor pressure vessel breaks, thereby makes the fuel assembly comprise hot fuel leak from reactor pressure vessel and enter to be arranged in the incident of said groove below the reactor pressure vessel.
6. a kind of safety equipment as claimed in claim 5 is characterized in that: said groove is to constitute like this and be provided with, and it is had is enough to make fuel assembly to scatter and by the water-cooled base areas that enters in said the groove.
7. the method for a water filling in the load chamber of loading reactor pressure vessel, this method may further comprise the steps:
When first incident of generation, water is sprayed in the containment shell building;
The water that sprays in the containment shell building is accumulated in the reactor vessel load chamber that constitutes a containment shell building part;
Be accumulated in a near pond that is arranged in the reactor pressure vessel load chamber with spraying into water in the containment shell building; With
When taking place, second scheduled event will be accumulated in the bottom that water in the said pond is discharged into said reactor pressure vessel load chamber.
8. be used for a kind of equipment to the load chamber water filling of loading reactor pressure vessel, this equipment comprises:
Be used for when first incident takes place water sprayed into the device in the containment shell building;
The water that is used for spraying in the containment shell building is accumulated in the device that constitutes a part of reactor vessel load chamber of containment shell building;
The water that is used for will spraying in the containment shell building is accumulated in the device that is positioned at a near pond of said reactor pressure vessel load chamber; With
The water that is used for will being accumulated in said pond when second scheduled event takes place is discharged into the device of the bottom of said reactor pressure vessel load chamber.
Applications Claiming Priority (3)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US70085196A | 1996-08-21 | 1996-08-21 | |
| US700851 | 1996-08-21 | ||
| US700,851 | 1996-08-21 |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN1174381A true CN1174381A (en) | 1998-02-25 |
| CN1116685C CN1116685C (en) | 2003-07-30 |
Family
ID=24815138
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN97113391A Expired - Lifetime CN1116685C (en) | 1996-08-21 | 1997-08-21 | Reactor cavity flooding system |
Country Status (2)
| Country | Link |
|---|---|
| KR (1) | KR100266506B1 (en) |
| CN (1) | CN1116685C (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102034559A (en) * | 2010-09-19 | 2011-04-27 | 中广核工程有限公司 | Rapid mutual-backup system of nuclear power station and mutual-backup method thereof |
Families Citing this family (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR101404646B1 (en) * | 2012-08-29 | 2014-06-09 | 한국과학기술원 | Inherent safety water cooled reactor system for thermal desalination |
| CN104008690A (en) * | 2013-02-26 | 2014-08-27 | 江苏核电有限公司 | Reactor pressure vessel simulation test platform for nuclear power plant |
| KR102040840B1 (en) | 2018-02-12 | 2019-11-27 | (주)엠큐더블유 | Apparatus for saving flowing water |
| US10446281B2 (en) * | 2017-08-15 | 2019-10-15 | Westinghouse Electric Company Llc | Detection apparatus and method of detecting the neutron absorption capability of a control element of a nuclear installation |
| KR101942915B1 (en) | 2018-07-02 | 2019-04-17 | (주)엠큐더블유 | Apparatus for saving flowing water supplying vitamin component |
| KR102009516B1 (en) | 2018-11-09 | 2019-10-21 | (주)엠큐더블유 | Water Tab supplying Vitamin |
-
1997
- 1997-08-07 KR KR1019970037689A patent/KR100266506B1/en not_active IP Right Cessation
- 1997-08-21 CN CN97113391A patent/CN1116685C/en not_active Expired - Lifetime
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102034559A (en) * | 2010-09-19 | 2011-04-27 | 中广核工程有限公司 | Rapid mutual-backup system of nuclear power station and mutual-backup method thereof |
| CN102034559B (en) * | 2010-09-19 | 2012-08-01 | 中广核工程有限公司 | Rapid mutual-backup system of nuclear power station and mutual-backup method thereof |
Also Published As
| Publication number | Publication date |
|---|---|
| KR19980018453A (en) | 1998-06-05 |
| CN1116685C (en) | 2003-07-30 |
| KR100266506B1 (en) | 2000-09-15 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C10 | Entry into substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| C06 | Publication | ||
| PB01 | Publication | ||
| C53 | Correction of patent for invention or patent application | ||
| CB02 | Change of applicant information |
Applicant after: ABB Combustion Engineering Nuclear Power Inc. Applicant before: Combustion Engineering Co. |
|
| COR | Change of bibliographic data |
Free format text: CORRECT: APPLICANT; FROM: BURNING ENGINEERING CO., LTD. TO: ABB BURNING ENGINEERING NUCLEAR FORCE CO., LTD. |
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| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| CX01 | Expiry of patent term |
Granted publication date: 20030730 |
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| CX01 | Expiry of patent term |