WO2016099326A1 - Система локализации и охлаждения расплава активной зоны ядерного реактора водоводяного типа - Google Patents
Система локализации и охлаждения расплава активной зоны ядерного реактора водоводяного типа Download PDFInfo
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- WO2016099326A1 WO2016099326A1 PCT/RU2015/000781 RU2015000781W WO2016099326A1 WO 2016099326 A1 WO2016099326 A1 WO 2016099326A1 RU 2015000781 W RU2015000781 W RU 2015000781W WO 2016099326 A1 WO2016099326 A1 WO 2016099326A1
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- melt
- vessel
- layer
- filler
- heat
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- 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
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/10—Means for preventing contamination in the event of leakage, e.g. double wall
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- 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
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/02—Details
- G21C13/024—Supporting constructions for pressure vessels or containment vessels
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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
Definitions
- the invention relates to the field of nuclear energy, in particular to systems that ensure the safety of nuclear power plants (NPPs), and can be used in severe accidents that lead to the destruction of the reactor vessel and its hermetic shell.
- NPPs nuclear power plants
- the greatest radiation hazard is accidents with core melting, which can occur during multiple failure of core cooling systems.
- the prior art device for the localization and cooling of the corium of a nuclear reactor located in the subreactor space of a concrete mine including a water-cooled casing, briquettes of a diluent material of uranium oxide corium bound with cement mortar and placed in steel blocks in several horizontal layers, the bottom of the lower block is identical in shape to the bottom of the case, the blocks located above it have a central hole, and the attachment points of the blocks to the case and to each other are placed in vertical slots of the blocks (see RF patent N ° 2514419, 04/27/2014).
- the bottom of the lower block identical in shape to the bottom of the body, does not have a central hole, and the blocks located above it have such holes, therefore, briquettes of the diluent material are “locked” in the lower block upon receipt of the first portion of the core melt, consisting mainly of made of liquid steel and zirconium. Given the angle of inclination of the bottom from 10 to 20 degrees, the mass of "locked" briquettes of the diluent material is from 25 to 35% of the total mass of briquettes located in the housing.
- the subsequent receipt of the second portion of the core melt consisting mainly of uranium and zirconium oxides, one to three hours after the first portion will not be able to create conditions for thermochemical interaction with briquettes in the lower block, since the steel that has arrived earlier will either freeze in the lower block (and then the interaction of the briquettes with uranium and zirconium oxides will be blocked), or the previously overheated steel will destroy the steel frame of the lower block with all the fasteners (and then the briquettes in it will float, forming slag ovoy cap over the corium);
- the formula that determines the mass of the diluent material of the uranium-containing oxide corium incorrectly determines the lower limit of the required mass of the diluent material, which is due to incorrect consideration of the ratio of the thickness of the layers of oxides and metals coming from the nuclear reactor.
- the lower limit should be increased by 35% when blocking briquettes in the lower block and should be increased by another 15% when blocking briquettes with liquid steel in the upper blocks before the inversion of oxide and metal layers. In this way, the lower limit for calculating the mass of the diluent material must be multiplied by a factor of 1.5.
- the prior art also knows the device wall of the heat exchanger casing, designed for melt localization and cooling, including an inner and outer wall and a filler placed between them made of granular ceramic material chemically similar to a sacrificial material, at least 100 mm thick (see RF Patent for Useful model JSTel00326, 12/10/2010).
- granular ceramic material does not provide effective protection of the outer wall of the heat exchanger body from thermal shock from the high-temperature melt due to the fact that this material is an effective thermal insulator with thermal conductivity, on average, less than 0.5 W / ( m K), and until the end of its melting, heat practically does not transfer heat to the outer wall of the casing, which increases the risk of destruction of the heat exchanger during convection leaching of granular material with a melt;
- granular ceramic material does not provide reliable chemical protection of the outer wall of the heat exchanger casing due to the fact that when the inner wall of the heat exchanger casing is destroyed, this material can spill out of the vertical inter-wall space with a flow rate determined by the destruction area, this process empties the inter-wall space, depriving the outer wall of the casing chemical and thermal protection, which increases the risk of destruction of the heat exchanger;
- the objective of the invention is to eliminate the disadvantages of analogues.
- the technical result of the invention is to increase the efficiency of heat removal from the melt and increase the reliability of the structure.
- the specified technical result is achieved due to the fact that the localization and cooling system of the core melt of the water-to-water nuclear reactor contains a funnel-shaped guide plate mounted under the bottom of the reactor vessel, a truss-console installed under the guide plate so that the plate rests on the truss console, a melt trap installed under the console farm and equipped with a cooled shell in the form of a multilayer vessel to protect the external heat exchange wall from dynamic, thermal and chemical influences and a filler for diluting the melt, placed in the aforementioned multilayer vessel, the vessel containing metallic inner and outer layers, between which an intermediate layer in the form of a nonmetallic filler is placed, and force ribs installed with an azimuthal pitch are placed between the inner and outer layers (s mar ) - with a step around the circumference in the diametrical plane of the multilayer vessel, satisfying the condition:
- a torus composite three-layer shell is installed, providing, on the one hand, a smooth hydrodynamic transition from conical to cylindrical parts of the vessel, and on the other, the temperature expansion of the inner layer regardless of the temperature expansion of the outer layer , - the vessel contains an additional anti-corrosion layer with a thickness
- the vessel contains an additional layer that increases convective heat transfer to water, a thickness of 0.5-5 mm, deposited on the outer layer.
- the system under consideration uses a melt trap having a three-layer shell with an external (external) and internal metal walls with a filler, while power ribs with an azimuthal step (3 step ) are installed between the external and internal walls - with a step along the circumference in the diametrical plane multilayer vessel satisfying the condition
- the indicated ratio of parameters provides an acceptable step for installing power ribs depending on the outer diameter of the vessel, which can vary from 3 to 12 m, and, for larger diameters, a smaller value of the quotient from division is chosen, and for smaller diameters - a larger one.
- the outer diameter of the vessel is 12 m
- the quotient of dividing by 15 is selected
- the outer diameter of the vessel is 3 m
- the quotient of dividing by 5 is selected, in this case the step of the arrangement of the edges in the azimuthal (diametric) plane is approximately 0.4 up to 0.8m.
- FIG. 1 schematically shows a system for localization and cooling of the melt
- FIG. 2 shows the design of the multilayer vessel for the melt trap.
- the structural elements are indicated in the drawings by the following positions:
- a guide plate (4) is installed, having the shape of a funnel, which rests on a truss-console (5) equipped with thermal protection (6).
- a melt trap (8) is installed, which has a cooled shell (case) in the form of a multilayer vessel, including metal outer (1 1) and inner (13) layers (walls), between which a layer of non-metallic aggregate is placed ( 12).
- a sacrificial filler (10) is placed inside the trap body (8) to dilute the melt.
- a pit (14) is made to accommodate a corium having a stepped, conical or cylindrical shape.
- thermal protection (9) of the flange of the multilayer vessel is provided.
- a service platform (7) is located in the space between the truss console (5) and the trap (8).
- the guide plate (4) is designed to direct the corium (melt) after the destruction or penetration of the reactor vessel into the trap (8).
- the guide plate (4) holds large fragments of the internals, fuel assemblies and the bottom of the reactor vessel from falling into the trap and protects the truss console (5) and its communications from destruction when the melt from the reactor vessel (1) enters the trap ( 8).
- the guide plate (4) also protects the concrete shaft (3) from direct contact with the core melt.
- the guide plate (4) is divided by power ribs into sectors along which the flow of the melt is ensured. Power ribs hold the bottom of the reactor vessel (2) with the melt, which does not allow the bottom to block the passage sections of the guide plate sectors (4) during its destruction or severe plastic deformation and disrupt the melt runoff.
- a layer of sacrificial concrete (based on aluminum and iron oxides) is located directly below the surface, and a layer of heat-resistant heat-resistant concrete (based on aluminum oxide) is under the sacrificial concrete.
- Sacrificial concrete dissolving in an active melt zone provides an increase in the bore in the sectors of the guide plate during the formation of blockades (when the melt solidifies in one or several sectors), which allows to prevent overheating and destruction of the power ribs, that is, complete blocking of the bore and, as a consequence, the destruction of the guide plate.
- Heat-resistant heat-resistant concrete provides structural strength while reducing the thickness of sacrificial concrete. This concrete protects the underlying equipment from the effects of the melt, preventing the melt from melting or destroying the guide plate (4).
- the truss console (5) protects not only the trap (8), but also the internal communications of the entire localization and cooling system of the core melt from destruction from the corium side and is a support for the guide plate (4), which transfers static and dynamic effects to the truss console (5), unfastened in the reactor shaft (3).
- the truss console (5) also ensures the operability of the guide plate (4) in the case of its sector destruction when the bearing capacity of the power ribs is weakened.
- Farm console (5) contains:
- channels for the removal of steam, ensuring the removal of steam from the subreactor room of the concrete mine (3) into the containment zone at the stage of cooling the corium in the trap (8); channels ensure the removal of saturated steam without exceeding the permissible pressure in the concrete mine
- the trap (8) ensures the retention and cooling of the molten core in the subreactor room of the concrete mine (3) during the penetration or destruction of the reactor vessel (1) due to the developed heat exchange surface and heat transfer to water in boiling mode in a large volume.
- a trap (8) is installed at the base of a concrete shaft (3) on embedded parts.
- the shell of the trap (8) according to the claimed invention is a multilayer vessel having:
- the metal inner layer (13) is the inner body formed by the wall and the bottom.
- the outer layer (11) can be made of steel, for example, grades
- the inner layer (13) can be made of steel, for example, grades 22K, 20K, 09G2S and have a thickness of 15-40 mm at the walls and 20-40 mm at the bottom.
- the aggregate layer (12) may be made of a highly heat-conducting or low-heat-conducting material.
- a material with a melting point of 300-800 ° C, preferably of low-melting concrete, with a melting point of not more than 600 ° C and a thickness of 70-150 mm can be used.
- a material with a melting point of more than 800 ° C in particular concrete or ceramic filling, can be used.
- force ribs (15) (see Fig. 3) installed with an azimuthal pitch (s mar ) satisfying the condition:
- d Hap 15 is the outer diameter of the vessel.
- the azimuthal step means the step along the outer diameter of the circle in the diametrical plane of the multilayer vessel (in cross section), i.e. the distance between the points of intersection of the force ribs with the outer wall (outer layer) of the vessel (see Fig. 3).
- These power ribs (15) are rigidly connected to the outer layer (1 1) and may or may not be connected to the inner layer (12).
- the power ribs can be made of steel 22K and have a width of 10-60 mm, and the azimuthal pitch of the installation is 200-800 mm.
- a torus composite three-layer shell (18) is additionally installed, providing, on the one hand, a smooth hydrodynamic transition from conical to cylindrical parts of the vessel, and on the other hand, the thermal expansion of the inner layer, regardless of the temperature expansion of the outer layer
- the multilayer vessel of the trap (8) may contain an additional anti-corrosion layer with a thickness of 0.1-0.5 mm deposited on the outer layer.
- the vessel may include an additional layer that increases convective heat transfer to water, 0.5-5 mm thick, deposited on the outer surface of the outer layer.
- the multilayer trap vessel (8) has a flange in the upper part, the outer and inner diameters of which coincide with the outer and inner diameters of the outer and inner walls of the vessel, respectively.
- Filler (10) provides volumetric dispersion of the corium melt within the trap (8). Designed for additional oxidation of corium and its dilution in order to reduce the volume of energy release and increase the heat transfer surface of the energy-producing corium from the outer layer of the multilayer vessel (1 1), and also helps to create conditions for the flooding of fuel-containing corium fractions above the steel layer.
- the filler (10) can be made of steel and oxide components containing iron, aluminum, zirconium oxides, with channels for redistributing the corium not only in the cylindrical part, but also in the bottom conical volume.
- the service platform (7) provides thermal protection for the upper part of the trap (8) and allows external inspection of the reactor vessel (1) during scheduled preventive maintenance, providing access to:
- the claimed system operates as follows.
- the core melt under the action of hydrostatic and overpressure begins to flow onto the surface of the guide plate (4) by the supported truss-console (5).
- the melt flowing down the sectors of the guide plate (4) enters the multilayer vessel of the melt trap (8) and comes into contact with the filler (10).
- thermal shields (6) of the truss-console (5) and the service platform (7) are melted. Destroyed, these thermal shields, on the one hand, reduce the thermal effect of the core melt on the protected equipment, and on the other hand, reduce the temperature and chemical activity of the melt itself.
- the melt sequentially first fills the sump (14), and then, as the steel elements of the filler structure (10) melt, it fills the voids between the non-metallic elements of the filler (10).
- Non-metallic elements of the filler (10) are bonded to each other with special cement, which ensures the sintering of these non-metallic elements among themselves into a structure that excludes the ascent of the elements of the filler (10) in a heavier core melt.
- the sintering of non-metallic elements among themselves provides sufficient masonry strength during the period of loss of strength from the side of the steel fasteners of the filler (10).
- a decrease in the strength of the steel elements of the filler (10) with increasing temperature is compensated by an increase in the strength of the masonry of non-metallic elements of the filler (10) during sintering.
- the surface interaction of non-metallic filler elements (10) with the core melt components begins.
- the design, physical and chemical properties of the filler are selected in such a way as to ensure maximum dissolution efficiency of the filler in the core melt, to prevent the melt temperature from increasing, to reduce aerosol formation and radiant heat transfer from the melt mirror, and to reduce the formation of hydrogen and other non-condensable gases.
- iron oxide which has different oxidation states, oxidizes zirconium during the interaction with the core melt, oxidizes uranium and plutonium dioxides, which prevents the formation of their metal phases, provides additional oxidation of the remaining components of the melt, which eliminates the radiolysis of water vapor and blocks sorption of oxygen from the atmosphere over the melt mirror. This, in turn, leads to a significant decrease in hydrogen yield. Iron oxide in this process releases oxygen and can be reduced to metallic iron, inclusive.
- the process of entering the core melt into the filler (10) takes place in two stages: at the first stage, mainly liquid steel and zirconium with an admixture of oxides are supplied from the reactor vessel (1) to the filler (10), and at the second, the main component of the incoming melt are refractory liquid oxides with an admixture of metals.
- the core melt and the filler (10) there are two different types of interaction between the core melt and the filler (10): the first is that the metal components of the core melt interact with the filler elements, melting them, and the liquid metal zirconium from the core melt is oxidized during the boundary interaction with non-metallic filler elements, which, when melted float up, forming a layer of light aluminum oxides of iron and zirconium over a layer of molten metals, and the second - oxide components of the melt of the active zone of interactions tvuyut and metal structures and non-metallic elements with filler, melting and dissolving them, and zirconium, chromium and some other liquid metals included in the oxide core melt fraction are oxidized by reacting with non-metallic filler elements.
- the oxide fraction of the melt is oxidized and the most active ingredients are oxidized from the metal fraction of the melt, a corium appears with predetermined properties that allow its localization in a limited volume and safe effective long-term cooling.
- both natural and artificial slag caps are used, which is formed both during the melting of special concretes under the influence of thermal radiation from the side of the melt mirror and during the interaction of the liquid corium melt with the filler .
- the thickness and lifetime of the slag cap are chosen in such a way as to minimize the impact of the upstream equipment from the side of the melt mirror during the most unfavorable initial period of melt localization - during its entry into the filler (10) and accumulation in the trap (8).
- the period of receipt of the core melt in the trap can reach several hours, moreover, the input of the oxide phase is substantially uneven and may be accompanied by a significant change or temporary cessation of flow.
- the chemical reactions of the filler (10) with the core melt gradually change the composition and structure of the corium.
- the core melt can pass from a homogeneous structure to a two-layer structure: at the top, mainly, a mixture of liquid steel and zirconium, below - a melt of refractory oxides with an admixture of metals; the melt density of refractory oxides is, on average, 25% higher than the density of a mixture of liquid metals.
- the composition of the corium, especially its oxide part changes: the density of liquid oxides decreases more than the density of liquid metals.
- the initial mass of non-metallic sacrificial filler materials is selected in such a way as to ensure guaranteed dissolution in liquid refractory oxides of the core of such a quantity of non-metallic sacrificial materials so that the resulting density of the new oxide melt was less than the density of the liquid metal fraction of corium.
- an inversion occurs in the bath of the corium melt: liquid oxides float up, and the liquid-metal fraction of corium drops down.
- the new corium structure allows safe cooling of the molten mirror with water.
- cooling water does not pose a threat of vapor explosions, which is associated with the thermophysical features of liquid oxides, and does not enter into chemical reactions with them with the formation of hydrogen, does not experience thermal decomposition due to the relatively low temperature of the melt mirror.
- Inversion of liquid oxides and metals allows for a more uniform heat flow through the multilayer vessel of the trap to the final heat absorber - water, due to various thermophysical properties of liquid oxides and liquid metals.
- Heat transfer from the corium to the trap (8) occurs in three stages.
- the first stage when mainly liquid metals enter the sump (14) of the filler (10), the heat exchange between the layers of the multilayer vessel (11-13) of the trap (8) and the melt does not differ in particular intensity: the heat accumulated by the melt is spent mainly on heating and partial melting of structural elements of the filler (10).
- the heating of the lower part of the trap (8) is uniform and does not have pronounced features.
- the conical bottom of the trap (8) has an average thickness of 30% greater than its cylindrical part, and vertical convective heat transfer from top to bottom has significantly lower efficiency than radial convective heat transfer, or vertical convective heat transfer from bottom to top, is a process
- the bottom of the trap (8) is heated much more slowly than the subsequent heating of its cylindrical part.
- the level of the corium melt increases significantly (taking into account the dissolution of the sacrificial filler materials).
- the oxide component of corium is energy-generating.
- the distribution of energy release between the oxide and metal components of the corium is approximately 9 to 1, which leads to significant heat fluxes from the oxide component of the corium.
- the oxide crust consisting of a melt of refractory oxides (skull), is formed as a result of cooling of the oxide melt at the oxide-metal interface, as a result of the fact that the metal has an order of magnitude higher thermal conductivity than oxides and can provide higher heat transfer to the final absorber heat to water.
- This effect is used to reliably localize the melt, preventing the chemical interaction of the corium components with the outer layer of the multilayer vessel (11), cooled by water, and ensuring its thermal protection.
- Liquid metals, located above the liquid oxides receive energy, mainly due to convective heat transfer with liquid oxides, the direction of convective heat transfer from the bottom up.
- This factor can lead to overheating of the liquid metal fraction of the corium and a substantially uneven distribution of heat fluxes through the layers of the multilayer vessel (11-13) of the trap (8) to the final heat sink, and, in addition, increase the heat flux density radiation from the melt mirror.
- the skull In the zone of interaction of the layers of the multilayer vessel (11-13) of the trap (8) with the liquid metal fraction of the corium, the skull does not form and there is no natural barrier from overheating of the multilayer vessel. The solution to this problem is provided by constructive measures.
- the outer layer of the multilayer vessel (11) from the side of the reactor shaft (3) is filled with water.
- the melt trap (8) is installed in the reactor shaft (3) and communicates with the pit, in which, during design and beyond design basis accidents, the coolant of the primary circuit of the reactor installation, as well as the water entering the primary circuit from the safety systems, enter.
- the melt trap (8) is made in the form of a multilayer vessel described above.
- the main thermal loads are absorbed by the inner layer (13), and the main mechanical loads (shock and pressure) are absorbed by the outer layer (11).
- the transfer of mechanical loads from the inner layer (13) to the outer layer (11) is provided by ribs mounted on the inner surface of the outer layer (11), to which the inner layer (13) is welded.
- the inner layer (13) through the ribs transfers forces from thermal deformation to the outer cooled layer (11).
- the connection between the ribs and the outer layer (11) is made in a special way using thermal damping.
- aggregate (12) of highly heat-conducting material low-melting concrete
- it provides heat transfer from the inner layer of the vessel (13) to the outer (11).
- the inner layer (13) is heated by corium and heat is transferred to the aggregate (12) (low-melting concrete).
- the aggregate is heated to the melting onset temperature, then, as the width of the molten zone increases, convective heat transfer begins between the inner layer (13) and the still not molten part of the aggregate (12). This process continues until the aggregate (12) is completely melted and the heat flux leaves the inner layer to the outer one.
- the process of melting of the aggregate (12) is fast enough, due to the high thermal conductivity of the material, therefore, practically, the entire heat flux from the side of the inner layer of the vessel will be absorbed by the aggregate material.
- the aggregate thickness was chosen so that the following two basic conditions were satisfied: the first — concrete melting time should be significantly less than the critical heating time of the inner layer of the vessel, leading to loss of strength, and the second — this level of convective heat transfer between the inner and outer layers should be ensured so that the heat flux density transferred from the inner layer to the molten concrete decreases from one and a half to two times when transferring from the molten concrete to the outside th layer of the vessel (outer wall) due to convective heat transfer in the molten concrete.
- the first basic condition is ensured by constructive measures - the choice of the macroporosity of the filler (10), which provides a moderate heat flux to the inner layer of the vessel at the initial stage of interaction of the core melt with the filler, which allows melt concrete without losing the strength of the inner layer of the vessel with increasing temperature.
- Such macroporosity allows a limited period of time at the initial stage of interaction to exclude the effect of the entire melt of the active zone on the inner surface of the inner layer of the vessel, limiting this effect to about a tenth of the total energy release in the melt provided by residual energy release and chemical reactions with filler components (10).
- the inner layer of the vessel warms up to the calculated temperature, and in the zone of thermal contact of the corium and the inner layer of the vessel, liquid fusible concrete provides convective heat transfer to the outer layer of the vessel, and then to the final heat sink - water.
- the second basic condition is ensured by the properties of liquid fusible concrete and the parameters of the space between the layers of the vessel, in which convective heat and mass transfer provides a given decrease in the density of the heat flow stream when it is transferred from the inner layer to the outer one.
- aggregate (12) from a low-heat-conducting material, it provides thermal insulation of the outer layer (11) of the trap (8) at the initial stage of the arrival of the core melt.
- the main purpose of the aggregate (12) is to protect against thermal shock and the formation of a skull on the inner surface of the outer layer (11) of the trap (8).
- the inner layer (13) is heated by the corium and melts, heat is transferred to the filler (12), which, when heated, melts and forms a skull crust on the relatively cold inner surface of the outer layer of the multilayer vessel (11). This process continues until the inner layer (13) and the aggregate (12) of the multilayer vessel are completely melted.
- the process of melting and dissolving the aggregate (12) in the corium occurs quickly enough, which is due to the low thermal conductivity of the aggregate, therefore, almost all of the heat flux from the corium to the inner layer (13) of the multilayer vessel will be spent on melting the inner layer (13) and the aggregate (12).
- the scull formed by the aggregate allows you to limit the heat flux to the outer layer (11) of the multilayer vessel, redistribute heat flow along the height of the outer layer (11) and align it with the local differences in height and azimuth.
- the limitation of the density of the heat flux passing through the outer layer (11) of the multilayer vessel is necessary to ensure stable crisis-free heat transfer to the final heat sink - water washing the melt trap (8). Heat transfer to water is carried out in the "boiling in large volume" mode, which allows for passive heat removal for unlimited time.
- the function of limiting the heat flux is performed by two elements of the localization and cooling system of the core melt of a nuclear reactor.
- the first element is a filler (10), which, on the one hand, provides dilution and an increase in the volume of the heat-generating part of the corium, which allows to increase the heat transfer area, thereby reducing the heat flux through the outer layer (11) of the trap (8), and with the other one provides inversion of the oxide and metal components of the corium, in which the oxide component moves up and the liquid metal component drops down, thereby reducing the maximum heat fluxes to the outer layer (11) due to the redistribution of heat outflows in the lower part of the trap (8).
- the second element is the filler (12) of the multilayer vessel, which ensures the reduction (alignment) of the maximum heat fluxes on the outer layer (11) due to the formation of a refractory skull crust, which redistributes the maximum heat fluxes from the corium side in height and azimuth (in the diametrical plane) of the outer layer (11) traps (8).
- the heat fluxes gradually equalize: the heat flux through the outer layer (11) becomes equal to the heat flux from the corium surface.
- the predominance of direct corium cooling can be observed by supplying water into the trap (8), which is possible in the case of the formation of a water-permeable structure during solidification of the corium.
- the indicated trap (8) of the localization and cooling system for the melt of the core of a water-water type nuclear reactor as a whole allows one to increase the efficiency of heat removal from the melt while maintaining the integrity of the outer layer of the multilayer vessel (11).
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Abstract
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Priority Applications (11)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CA2971132A CA2971132C (en) | 2014-12-16 | 2015-11-16 | Water-cooled water-moderated nuclear reactor core melt cooling and confinement system |
EP15870434.6A EP3236472B1 (en) | 2014-12-16 | 2015-11-16 | System for confining and cooling melt from the core of a water cooled and moderated reactor |
MYPI2017702207A MY194315A (en) | 2014-12-16 | 2015-11-16 | Water-cooled water-moderated nuclear reactor core melt cooling and confinement system |
KR1020177019500A KR102198445B1 (ko) | 2014-12-16 | 2015-11-16 | 수냉각 수감속 원자로의 노심 용융물 냉각 및 가둠 시스템 |
CN201580076173.4A CN107210070B (zh) | 2014-12-16 | 2015-11-16 | 水冷、水慢化反应堆堆芯熔融物的冷却和封闭系统 |
UAA201707424A UA122402C2 (ru) | 2014-12-16 | 2015-11-16 | Система локализации и охлаждения расплава активной зоны ядерного реактора водоводяного типа |
US15/536,968 US20170323693A1 (en) | 2014-12-16 | 2015-11-16 | Water-Cooled Water-Moderated Nuclear Reactor Core Melt Cooling and Confinement System |
JP2017532090A JP6567055B2 (ja) | 2014-12-16 | 2015-11-16 | 加圧水型原子炉の溶融炉心を冷却して閉じ込めるシステム |
BR112017013046-7A BR112017013046B1 (pt) | 2014-12-16 | 2015-11-16 | Sistema de confinamento e resfriamento de material fundido de núcleo de reator nuclear moderado por água e resfriado a água |
EA201650092A EA032395B1 (ru) | 2014-12-16 | 2015-11-16 | Система локализации и охлаждения расплава активной зоны ядерного реактора водоводяного типа |
ZA2017/04784A ZA201704784B (en) | 2014-12-16 | 2017-07-14 | System for confining and cooling melt from the core of a water cooled-water modified reactor |
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JP2018200239A (ja) * | 2017-05-29 | 2018-12-20 | 株式会社東芝 | 溶融炉心保持冷却装置及び原子炉格納容器 |
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WO2023128809A1 (ru) * | 2021-12-29 | 2023-07-06 | Акционерное Общество "Атомэнергопроект" | Способ изготовления фермы-консоли устройства локализации расплава |
KR102649036B1 (ko) * | 2022-03-14 | 2024-03-18 | 한국수력원자력 주식회사 | 소형원자로 냉각장치 및 냉각방법 |
CN116030997B (zh) * | 2023-02-14 | 2024-02-27 | 上海核工程研究设计院股份有限公司 | 一种使用牺牲材料缓解核反应堆严重事故的方法及装置 |
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- 2015-11-16 EA EA201650092A patent/EA032395B1/ru not_active IP Right Cessation
- 2015-11-16 WO PCT/RU2015/000781 patent/WO2016099326A1/ru active Application Filing
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JP6567055B2 (ja) | 2019-08-28 |
US20170323693A1 (en) | 2017-11-09 |
KR102198445B1 (ko) | 2021-01-07 |
BR112017013046A2 (pt) | 2019-11-19 |
EA201650092A1 (ru) | 2017-09-29 |
CN107210070A (zh) | 2017-09-26 |
ZA201704784B (en) | 2019-07-31 |
RU2576517C1 (ru) | 2016-03-10 |
CA2971132A1 (en) | 2016-06-23 |
CA2971132C (en) | 2023-05-23 |
KR20170104474A (ko) | 2017-09-15 |
JP2018503811A (ja) | 2018-02-08 |
AR102994A1 (es) | 2017-04-05 |
MY194315A (en) | 2022-11-28 |
EP3236472B1 (en) | 2019-08-07 |
EP3236472A4 (en) | 2018-06-27 |
UA122402C2 (ru) | 2020-11-10 |
EP3236472A1 (en) | 2017-10-25 |
HUE047296T2 (hu) | 2020-04-28 |
BR112017013046B1 (pt) | 2022-12-27 |
EA032395B1 (ru) | 2019-05-31 |
CN107210070B (zh) | 2019-10-11 |
JO3698B1 (ar) | 2020-08-27 |
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