DE2914872A1 - Molten core catch vat - for pressurised water reactor made or uranium oxide with cooled bottom - Google Patents
Molten core catch vat - for pressurised water reactor made or uranium oxide with cooled bottomInfo
- Publication number
- DE2914872A1 DE2914872A1 DE19792914872 DE2914872A DE2914872A1 DE 2914872 A1 DE2914872 A1 DE 2914872A1 DE 19792914872 DE19792914872 DE 19792914872 DE 2914872 A DE2914872 A DE 2914872A DE 2914872 A1 DE2914872 A1 DE 2914872A1
- Authority
- DE
- Germany
- Prior art keywords
- vat
- core
- uranium oxide
- pressurised water
- water reactor
- 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.)
- Withdrawn
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/016—Core catchers
-
- 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
Landscapes
- 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
Description
Auffangwanne bei der Coreschmeize von DruckwasserreaktorenCollecting basin in the core melting of pressurized water reactors
Beim Betrieb von Druckwasserreaktoren besteht die Gefahr der Coreschmelze wenn bei einem Rohrbruch im Primärkreislauf oder beim Ausfall von Xühlmittelpumpe irgendwelcher Art (Speisewasserpumpen, Pumpen für die Notkühlung, Pumpen der KUhikreise) des gesamten Primärsystems der Reaktorkern vorübergehend oder dauernd nicht voll von Wasser bedeckt ist oder zumindest von Wasser der Notkuhlung bespült wird.When operating pressurized water reactors, there is a risk of core melting if there is a broken pipe in the primary circuit or if the coolant pump fails of any kind (feed water pumps, pumps for emergency cooling, pumps for the KUhi circuits) of the entire primary system of the reactor core temporarily or permanently not full covered by water or at least flushed with emergency cooling water.
Im schlimmsten Fall ist damit zu rechnen, dass das flüssige Brennstoff-Hüllenmetallgemisch auf den Boden des Reaktordruckbehälters sinkt oder fällt und diesen infolge seiner hohen Temperatur in Verbindung mit seiner hohen Dichte nach unten durchschmilzt.In the worst case, it is to be expected that the liquid fuel-cladding metal mixture sinks or falls to the bottom of the reactor pressure vessel and this as a result of it high temperature combined with its high density.
Un dieser Gefahr zu begegnen , wird erfindungsgemäß vorgeschlagen unterhalb des Reaktorkernes , aber noch innerhalb des Druckkessels, eine aus des Oxid des natürlichen oder depletierten Urans , das noch mit guten Neutronenabsorbern vermischt oder durchsetzt sein kann , eine Wanne einzubauen , die die Coreschmelze auffängt. Diese Auffangwanne soll dabei so gestaltet werden , dass sie durch ein vom übrigen Kühlsystem getrenntes System gekühlt werden kann. Durch ihr hohes spezifisches Eigengewicht einerseits und durch cie unabhängige Kühl einrichtung andererseits soll verhindert werden ,dass diese Wanne vom herabtropfenden Core durchschnolzen werden kann. Unter diesen Umständen wird die Coreschrrelze in der Wanne schwimmen . Ausserdem wird die in ihr freiwerdende Wärmeenergie bei geeigneter Dimensionierung des für die Auffangwanne vorgesehenen Rühlkreislaufs laufend abgeführt werden können.To counter this danger is proposed according to the invention below the reactor core, but still inside the pressure vessel, one from the Oxide of natural or depleted uranium that still has good neutron absorbers can be mixed or interspersed to build a tub that melts the core catches. This drip pan should be designed in such a way that it is through a system separated from the rest of the cooling system can be cooled. By their high specificity Dead weight on the one hand and due to the independent cooling device on the other to prevent this tub from melting through from the dripping core can be. Under these circumstances, the core will float in the tub . In addition, the heat energy released in it, if dimensioned appropriately of the cooling circuit provided for the drip pan can be continuously removed.
Die Wanne wird dabei zweckmaßigerweise keinen glatten oder monoton gekriimmten Boden erhalten,sondern wabenförmig zu gestalten sein , damit das herabtropfende Core sich nicht zu einem nukleartechnisch überkritischen CHbilde zusaitnnfinden kann.The tub is expediently not smooth or monotonous Keep the curved bottom, but rather be honeycomb-shaped so that the dripping down Core do not come together in a nuclear supercritical CH formation can.
Die aus u.U. mehreren Teilen zusammengesetzte Wanne nuß selbst ein Hüllenmaterial tragen, das einen möglichst hohen Schelzpunkt besitzt. (z.B.The tub, which may be composed of several parts, must be installed by itself Wear cover material that has the highest possible felling point. (e.g.
Nickel,evtl.legiert mit weiteren Neutronenabsorbern) und natürlich dem korrosiven Angriff des unter hoherr Druck stehenden,heißen Kühl-und Moderatorwassers des Reaktors standhält.Nickel, possibly alloyed with other neutron absorbers) and of course the corrosive attack of the hot Cold and Withstands moderator water of the reactor.
Die Menge des für den Aufbau der Auffangwanne eingesetzten Uranoxids muss der des Reaktorkernes vergleichbar sein.The amount of uranium oxide used to build the sump must be comparable to that of the reactor core.
Claims (1)
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE19792914872 DE2914872A1 (en) | 1979-04-12 | 1979-04-12 | Molten core catch vat - for pressurised water reactor made or uranium oxide with cooled bottom |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE19792914872 DE2914872A1 (en) | 1979-04-12 | 1979-04-12 | Molten core catch vat - for pressurised water reactor made or uranium oxide with cooled bottom |
Publications (1)
Publication Number | Publication Date |
---|---|
DE2914872A1 true DE2914872A1 (en) | 1980-10-23 |
Family
ID=6068174
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
DE19792914872 Withdrawn DE2914872A1 (en) | 1979-04-12 | 1979-04-12 | Molten core catch vat - for pressurised water reactor made or uranium oxide with cooled bottom |
Country Status (1)
Country | Link |
---|---|
DE (1) | DE2914872A1 (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP0993000A2 (en) * | 1998-10-07 | 2000-04-12 | Forschungszentrum Jülich Gmbh | Apparatus for cooling and protecting a reactor pressure vessel in the event of a core melting accident |
FR2784785A1 (en) * | 1998-10-14 | 2000-04-21 | Commissariat Energie Atomique | NUCLEAR WATER REACTOR HAVING A RECEPTACLE CONTAINING DEFORMABLE INTERNAL STRUCTURES |
-
1979
- 1979-04-12 DE DE19792914872 patent/DE2914872A1/en not_active Withdrawn
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP0993000A2 (en) * | 1998-10-07 | 2000-04-12 | Forschungszentrum Jülich Gmbh | Apparatus for cooling and protecting a reactor pressure vessel in the event of a core melting accident |
EP0993000A3 (en) * | 1998-10-07 | 2000-12-13 | Forschungszentrum Jülich Gmbh | Apparatus for cooling and protecting a reactor pressure vessel in the event of a core melting accident |
FR2784785A1 (en) * | 1998-10-14 | 2000-04-21 | Commissariat Energie Atomique | NUCLEAR WATER REACTOR HAVING A RECEPTACLE CONTAINING DEFORMABLE INTERNAL STRUCTURES |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
DE68906727T2 (en) | PASSIVE FULL PRESSURE SYSTEM FOR GAP ZONE EMERGENCY COOLING AND HEAT EXHAUST FOR WATER-COOLED CORE REACTORS. | |
DE68925855T2 (en) | Pressurized water nuclear reactor with intrinsic security | |
US4587079A (en) | System for the emergency cooling of a pressurized water nuclear reactor core | |
DE69010977T2 (en) | Indirect passive cooling system for nuclear reactors with liquid metal cooling. | |
EP0030698A3 (en) | Boiling-water reactor | |
DE3877703T2 (en) | SYSTEM FOR HEAT TRANSPORT FOR SODIUM-COOLED REACTOR. | |
DE2914872A1 (en) | Molten core catch vat - for pressurised water reactor made or uranium oxide with cooled bottom | |
DE69008759T2 (en) | Steam generator for reactors cooled with liquid sodium. | |
DE2622050A1 (en) | Reactor core melt-down cooled by evaporation - of large continuous water supply, e.g. from river to sump exterior | |
DE69709995T2 (en) | Steam outlet system with internal condenser | |
DE102016218855A1 (en) | Freiraumquench with self-cooling, mehrmanteligem central tube | |
DE1949533A1 (en) | Insulated pipes for nuclear reactors | |
DE2514812A1 (en) | NUCLEAR REACTOR | |
DE2521269C3 (en) | Pressurized water reactor | |
DE60028164T2 (en) | Pressure relief device for a nuclear reactor vessel | |
DE1539728B1 (en) | Ship's nuclear reactor for steam generation and overheating and process for operating the nuclear reactor | |
DE2217863A1 (en) | Nuclear reactor | |
DE2734810C2 (en) | Safety device for the safety envelope of a pressurized water reactor | |
DE3036907C2 (en) | Pressurized water reactor with a reactor pressure vessel | |
AT217134B (en) | Nuclear reactor, the core of which contains a bed of fuel elements made up of shaped bodies such as spheres or the like | |
AT80002B (en) | Safety device for hot water heating. Safety device for hot water heating. | |
AT77430B (en) | Cooled piston for internal combustion engines. | |
AT217053B (en) | Device for cooling industrial furnaces, for waste heat recovery and steam generation | |
AT215640B (en) | Hot water heating system | |
EP0162337B1 (en) | Core support relieved of thermal stresses for a liquid metal-cooled nuclear reactor |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
8139 | Disposal/non-payment of the annual fee |