CN1266706C - Oxide material for molten core catcher of nuclear reactor - Google Patents
Oxide material for molten core catcher of nuclear reactor Download PDFInfo
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- CN1266706C CN1266706C CNB028075889A CN02807588A CN1266706C CN 1266706 C CN1266706 C CN 1266706C CN B028075889 A CNB028075889 A CN B028075889A CN 02807588 A CN02807588 A CN 02807588A CN 1266706 C CN1266706 C CN 1266706C
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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 inventive oxide material for the molten core catcher of a nuclear reactor comprises a chilling and oxidising agent for chilling said molten core catcher and oxidising the more active components thereof. Said agent also comprises a target additive consisting at least of an oxide which is selected from a group which contains Gd2O3, Eu2O3, and Sm2O3, preferably equal to 4 mass % and more preferably ranging from 0.1 to 4 mass %. The preferable chilling and oxidising agent comprises Fe2O3 and/or Fe3O4 and Al2O3, the Fe2O3 and/or Fe3O4 content ranging from 46 to 80 mass % and the Al2 O3 content ranging from 16 to 50 mass %. The inventive material can also comprise up to 4 % of SiO2, preferably ranging from 1 to 4 mass %.
Description
Technical field
The present invention relates to atomic energy industry, relate to so-called expendable material (sacrificialmaterials) particularly, be the material of molten-core catcher of nuclear reactor, be used in the fusing lining (molten corium) of locating airtight water cooled nuclear reactor when hypothetical accident occurring.When this accident occurring, the lining of this material and nuclear reactor high temperature melting reacts to each other, make melt stop (location) in trap (trap) and with it cooling, form subcritical state simultaneously, and prevent from promptly to prevent from the nuclear reaction in the melt is converted to overcritical pattern from the generation of keeping chain reaction of nuclear fission.Thus, expendable material itself dissolves gradually by the physical and chemical process of complexity, and no longer exists with its original form.
Background technology
After extensive accident takes place in Chernobyl Plant the 4th heap and U.S.'s TMI nuclear power station, and after some other accident of nuclear plant, make the expendable material in the device of fusing lining location of formation in the exploitation nuclear power plant accident, seem particularly important.At present, the nuclear power industrial expansion depends on the reliable system of location nuclear reactor fusing lining and the manufacturing of the effective expendable material of nuclear reactor under many circumstances.
Expendable material fundamentally is a kind of new material, and relative research and development is also few, and owing to can not directly carry out the experiment of full-scale, therefore can only be according to using theoretical calculating and the systematic approach of model experiment.
Be well known that nuclear reactor fusing lining comprises two-phase: metal phase (lighter) and oxide be (heavier) mutually.In order effectively to reduce the temperature of over-heat metal component in the melt, can use iron and steel as cooling agent.But iron and steel can not affect the oxide part of melt, and main radiation is arranged in oxide and nuclear chain reaction can take place.And, this cooling agent can not oxidation dissolution in melt oxidation thing part and part enter zirconium in the metal part, cause unoxidized zirconium and steam reaction to generate hydrogen, burning is also exploded.
Be well known that the use oxide material, be used for molten-core catcher of nuclear reactor, contain monox or aluminium oxide in the oxide material as cooling medium and oxygenant (seeing: RU2165106, ICL G21C9/016,12/10, April 10 calendar year 2001).These oxides mix with a large amount of uranium dioxide that exist in the melt, reduce its concentration, thereby reduce the possibility of nuclear reaction in the melt that reaches overcritical pattern; And because its quite high thermal capacitance, these oxides make melt cooling and are positioned in the trap.Except using this material, zirconium can oxidized silicon and aluminium oxide oxidation, and the degree of oxidized silicon oxidation is greater than aluminium oxide.
In order to make more effectively oxidation of zirconium, having proposed another kind of oxide material is used for molten-core catcher of nuclear reactor and (sees: Markus Nie.Application of sacrificial concrete for the retention andconditioning of molten corium in the EPR core melt retention concept.OECDWorshop on Ex-Vessel Debris Coolability, Karlsruhe, Germany, 15-18 day in November, 1999).In this material, use to comprise that the hopcalite of iron oxide, silicon dioxide and aluminium oxide and boron, calcium, magnesium and chromium is as cooling medium and oxygenant.Contain the about 22-45% of iron oxide in this material, silicon dioxide is about 25%, aluminium oxide about 2%.
Known expendable material dilution nuclear reactor fusing lining helps the multiplicaiton factor of neutron that nuclear process is produced to be limited in certain below the numerical value, and the nuclear reaction when this numerical value in the melt reaches overcritical pattern, and this is unallowed.Yet, remaining on reliably under the subcritical neutron by the nuclear reaction in the fritting body, the problem of nuclear safety is still extremely important.
Basic purpose of the present invention provides oxide material, is used for molten-core catcher of nuclear reactor, more reliably melt is remained on subcritical pattern, thereby guarantees nuclear safety.Its composition can mix well with the urania that nuclear reactor melts in the lining, and with the zirconium complete oxidation that exists in the melt, reduce the generation of volatile materials in the melt, obtain to begin temperature, low crystallization start temperature and the stability of oxide expendable material with the higher rate of fusant reaction, low reaction.The reliable location that this provides melt makes that nuclear reaction is more difficult to reach overcritical pattern, prevents burning and the blast of hydrogen in the container, and reduces radionuclide to the release of environment.
Summary of the invention
Consider above-mentioned basic purpose, propose a kind of oxide material for nuclear reactor fusing lining, comprise cooling and oxidant, be used for cooling fusing lining and the most active composition oxidation that will be wherein.According to the present invention, also contain in the described material by from Gd
2O
3, Eu
2O
3And Sm
2O
3The subject additives that the middle at least a oxide of selecting forms.
In expendable material, introduce these oxides, can absorb the neutron in the wide energy spectral line scope, guarantee the more reliable nuclear safety of fusing lining, namely, the neutron of the radio isotope by effectively absorbing uranium in the melt and other radioactive element nuclear decay radiation remains under the subcritical neutron nuclear reactor fusing lining more reliably.In the melt solidifying process, under the condition that system's local dangerous (supercriticality) can not reach, that is, the neutron multiplication factor remains on and makes melt uranium-bearing oxide portion divide assurance under the condition of subcritical state, with Gd
2O
3The Gd that form exists is with Eu
2O
3The Eu that exists and with Sm
2O
3The Sm that form exists is with uranium dioxide and most of fissionable isotope cocrystallization.
The content of subject additives can be up to 4wt%.When using Gd
2O
3The time, its content is 0.1～0.4wt% preferably.When using Eu
2O
3And/or Sm
2O
3The time, its content is 1～4wt% preferably, because they absorb the energy force rate Gd of neutron
2O
3Low.
The cooling of the oxide material of preferred molten-core catcher of nuclear reactor and the Fe that oxidant comprises 46～80wt%
2O
3And/or Fe
3O
4And the Al of 16～50wt%
2O
3The composition of this oxidation and cooling agent can be to melting the well oxidation of zirconium in the body, because the aluminium oxide that contains high heat capacity can cool off efficiently to melt because containing iron oxide.Simultaneously, the oxide of iron and aluminium has good Combination with the oxide that melts uranium in the lining, and does not cause the layering (liquate) of oxide phase, thereby melt is diluted well, and still keeps subcritical state more reliably.And the oxide of iron and aluminium forms solid solution by reaction, and its Tc is lower than aluminium oxide.This has promoted the reaction between fusing lining and the expendable material, thus the diluting effect that melt is produced, and make it to remain on subcritical state.
The oxidation of expendable material of the present invention and cooling medium can also contain silicon dioxide, and its content can be up to 4wt%, preferably 1～4wt%.Yet, uranium dioxide Combination in silicon dioxide and the melt is poor, but so few content can be dissolved in the oxide part in the melt, and not stratified, beginning temperature with crystallization reduces thus, and this helps to dilute uranium dioxide and makes it to remain on subcritical state.And, add a small amount of silica like this and make the intensity of expendable material increase 40～50%, because generated SiO
2With Al
2O
3Compound (mullite).
Embodiment
Oxide expendable material according to sintering of the present invention obtains by the secondary clacining method, thereby obtains the brick of dimensionally stable.At initial period, prepare raw material by subsequently required mixed proportion, the raw material that then will represent cooling and oxidant stock mixes and the dry type vibratory grinding, and also with subject additives (Gd
2O
3, Eu
2O
3And/or Sm
2O
3) carry out separately the dry type vibratory grinding, finally all obtain the powder that granularity is no more than 63mm.When reaching the granularity of 63mm, stop to grind.The subject additives oxide powder mixes (not using subject additives in the comparative example) in 1/10 to 1/5 ratio with the part stock.After mixing, the potpourri that obtains adds again in remaining stock.After mixing once more, the subject additives fine powder is evenly distributed in the powder that contains stock.But then use the cementing agent of 5% polyvinyl alcohol water solution, be pressed into brick, 1280～1300 ℃ of calcinings 2 hours as burn off.After this with brick fragmentation, grinding, classification, mix with interim binding agent (5% polyvinyl alcohol water solution) and suppress.Finally in air, calcined 6 hours at 1320 ℃.
In use, oxide expendable material of the present invention is placed trap, for example be positioned at the nuclear reactor below, preferably put together with metal sacrificial.When accident and fusing occurring and penetrate the nuclear reactor wall, temperature reaches 2700 ℃ fusing lining and flows into downwards in the trap and with expendable material and react.In this case, expendable material fusing also mixes with the lining of fusing, at first with melt cooling to about 2000 ℃, prevent that it from melting the trap wall, thus fixing melt; Secondly, with the dilution of the uranium dioxide in the melt, thereby the nuclear reaction in the melt is remained on subcritical state.In addition, expendable material will melt the zirconium oxidation in the lining, reduce the amounts of hydrogen that the reaction of zirconium and water discharges.
In the process of cooling nuclear reactor fusing lining, the oxide of Gd, Eu and Sm is arranged in the oxide part of the active region of containing a large amount of fissile isotopes.The uranium dioxide cocrystallization that they are similar to physicochemical property.In the decay process of the radioactive isotope of uranium and other radioelement and fission product, radiate neutron; When neutron is caught by the atomic nucleus of other fissile material, can bring out nuclear chain reaction.The number of neutrons that produces in rear step decay is expressed as the neutron multiplication factor with the ratio of the number of neutrons that back produces, and is used for characterizing the pattern of nuclear reaction.If this factor is greater than 1, then nuclear reaction is in overcritical pattern, and this moment, the quantity of neutron increased as snowslide, caused blast.For the nuclear reaction that is in subcritical pattern, promptly neutron quantity does not increase, and above-mentioned K factor is less than 1.Gadolinium oxide (the Gd that exists in the oxide expendable material
2O
3), europium oxide (Eu
2O
3) or samarium oxide (Sm
2O
3), its metallic atom nuclear absorbs neutron, because these atomic nucleus have big neutron-absorbing effective cross-section in wide neutron energy spectrum, thereby prevent that these neutrons from being caught by described uranium nuclei, reduced the number of neutrons of generation in next step decay, namely reduced the neutron multiplication factor, and prevented that nuclear chain reaction from reaching overcritical pattern.
Although in basic oxide expendable material forms, introduce Gd
2O
3, Eu
2O
3Or Sm
2O
3Obtain identical technical result, but use Gd
2O
3Preferred, because its preferred content is 0.1～0.4wt%, than using Eu
2O
3And Sm
2O
3Preferred content 1～4wt% little 10 times.Use Eu
2O
3And Sm
2O
3Content must be greater than Gd
2O
3Because their neutron-absorbing ability is low.But, although Gd
2O
3The neutron-absorbing ability stronger, but use Eu
2O
3And Sm
2O
3More favourable, because they compare Gd
2O
3Considerably cheaper.
Gd
2O
3, Eu
2O
3Or Sm
2O
3The determining to be based on the neutron multiplication factor must be provided reliably of least concentration, be in subcritical state with the oxide portion branch that guarantees the melt uranium-bearing.The consideration of determining to be based on economy of the upper limit concentration of these oxides, i.e. Gd
2O
3, Eu
2O
3And Sm
2O
3Expensive; And cooling and the oxidant that must keep high-load, thereby expendable material cold fuse-element and make the zirconium oxidation effectively.
When melt arrives expendable material, expendable material fusing and cold fuse-element.When the material that uses preferred component, namely contain the Fe of 46～80wt% in cooling and the oxidant
2O
3And/or Fe
3O
4And the Al of 16～50wt%
2O
3The time, the forward position of contained a large amount of iron oxide reactions in melt and this oxide expendable material, because the strong oxidation of zirconium in the melt, the high speed exothermic reaction of heat release takes place, melt remains on liquid phase a period of time thus, helps it and even mixing of expendable material also effectively is sacrificed the material dilution.The high activity of described reaction makes the lining of expendable material and fusing form fast improving uniformity of melt, and owing to the trap wall absorbs heat the liquid in trap in a large number melt is cooled off fast.Described heat release between expendable material and the fusing lining on the interface prevents melt crystallization on the interface, thereby prevents that the reaction between expendable material and the fusing lining is converted to the solid phase reaction of low speed from liquid phase reactor at a high speed.This prevents that also unreacted expendable material from forming the solid phase shell near the trap wall, reduces from described wall heat radiation, thereby slows down cooling velocity.
Because strong zirconium oxidation, avoided the reaction of water vapour in zirconium and the container and cause burning with the reaction of the water of cold fuse-element and generation and accumulation hydrogen and explode.
Because the oxide of aluminium and iron dilutes the oxide of uranium in the melt well, therefore more reliably the chain reaction of the oxide of uranium is remained on subcritical neutron.Although alumina content height, but the system's fusing point that comprises trap inner oxide material and fusing lining, can not raise when adding dystectic aluminium oxide, this helps system to remain liquid in longer a period of time, therefore improves and has accelerated the melt dilution and kept more reliably subcritical state.This be because, the oxide of iron and aluminium forms compound (solid solution), its fusing point is starkly lower than pure alumina.
Preferably, in the composition of expendable material of the present invention, the content of iron and aluminium is balance, forms reaction at a high speed between trap oxide material and the melt thereby make; The acceleration of melt dilution also helps to remain on subcritical neutron.
If the Fe in the material
2O
3And/or Fe
3O
4Content is less than 46wt%, then the reaction rate of trap oxide material and melt will can be very not high, has reduced the reliability that melt remains on subcritical neutron.And, owing to lack oxygen and can not make the zirconium oxidation fully, cause the forming of other gaseous state of hydrogen and harmfulness with volatile products.If the Fe in the material
2O
3And/or Fe
3O
4Content surpasses 80wt%, and the overall reaction effect will be heat release, causes a large amount of and formation unallowed gaseous state and volatile products.
If Al
2O
3Content is less than 16wt%, and then exothermic reaction can not be heated the endothermic effect that the trap oxide material produces and offsets, and the exothermic effect that obtains will heat whole melt navigation system certainly.If Al
2O
3Content surpasses 50wt%, and then the liquidus temperature of melt raises, and correspondingly melt is descended by the speed of the oxide material of trap dilution, keeps the reliability of subcritical neutron to reduce, and because Fe
2O
3And/or Fe
3O
4Lazy weight and zirconium be can not be completely oxidized causes unoxidized zirconium to contact with water vapour and generates hydrogen, obviously increases the possibility of combustion of hydrogen and blast.
As mentioned above, a small amount of SiO that adds in the material of the present invention
2, can obviously improve its intensity, the dilution of the oxide of uranium in the melt that makes moderate progress simultaneously, thus help nuclear reaction to remain on subcritical pattern.
If SiO
2Content surpasses 4wt%, and then the release of gaseous products increases, because forming the possibility of melt layering, the liquate process also increases, thus the dilution of the oxide of uranium in the reduction melt.If SiO
2Content is less than 1wt%, and the intensity of expendable material is obviously increased.
Therefore, oxide expendable material of the present invention is applied to molten-core catcher of nuclear reactor, after melt enters trap, make nuclear reaction remain on subcritical pattern reliably, the while is cold fuse-element effectively, reliably is positioned at melt in the trap, prevent that hydrogen gas accumulation from arriving enough quantity, cause burning and blast.
By model experiment and calculation of thermodynamics, assessed the ability that material of the present invention melts nuclear reactor the lining effective location.
The model experiment of on experimental facilities, carrying out, be in cold crucible, to realize the high-frequency induction melting process, according to test specifically developed program for this, measured following numerical value: the reaction velocity of material of the present invention and nuclear reactor fusing lining, the temperature that begins to react, the liquidus temperature of melt and expendable material potpourri.The sample of expendable material of the present invention is placed on the bottom of cold crucible.By a water-cooled shielding system and induction coil are isolated.The sealing quartz container of stove fills a lid above cold crucible, covers to have perforate, is used for installing pyrometer, measures pool depth and observes bath surface.Before this, use cold reactor fuel,, melt is contacted with the expendable material piece by the expendable material piece is moved to the zone that contacts with melt by the preparation of induction melting in cold crucible fusing lining.The crucible that melt is housed is placed on equipment to be made on the worktable of crucible with respect to inductive coil and shielding vertical moving.Rigidly connect by melt and to touch the hot junction timing immediately that is contained in the thermopair on the expendable material, assaying reaction forward position movement velocity.
Use the program of checking and the IVTANTHERMO database that comprises the macroscopic property data, gas be formed on experimentally and be defined as in theory under the formation temperature of molten bath the quantity of gaseous products (gas and steam) in the system, wherein system is made up of fusing lining and expendable material.
Use identical program and IVTANTHERMO database, by calculation of thermodynamics, fuel factor is calculated as enthalpy poor of system, that is, when the institute that takes place in taking into account system responds, the heat that discharges when melt is sacrificed material cooled.
When the critical parameters of the mixture of measuring the oxide expendable material that melts lining and contain or do not contain subject additives, use known SAPPHIRE program to calculate MF, this program is applied to neutronics and calculates, and through the checking of lot of experimental data storehouse.
Listed the embodiment of expendable material in the following table, these embodiment also contain subject additives of the present invention through present inventor's test, and it is as shown in the table for its composition and character.Embodiment 1-17 is the expendable material that the present invention contains subject additives, and embodiment 18 is the contrast materials that do not have adjuvant.
Show to add Gd in the basic oxide expendable material
2O
3, Eu
2O
3Or Sm
2O
3The uranium-bearing nuclear reactor is melted the influence of the subcritical neutron of lining
| The embodiment numbering | Material composition, wt% | Multiplicaiton factor (K) | ||||||
| Fe 2O 3 | Fe 3O 4 | Al 2O 3 | SiO 2 | Gd 2O 3 | Eu 2O 3 | Sm 2O 3 | ||
| 1 | 46.0 | - | 49.9 | 4.0 | 0.1 | - | - | 0.93 |
| 2 | 49.0 | - | 49.9 | 1.0 | 0.1 | - | - | 0.93 |
| 3 | 64.8 | - | 31.0 | 4.0 | 0.2 | - | - | 0.74 |
| 4 | 68.8 | - | 29.0 | 1.0 | 0.2 | - | - | 0.74 |
| 5 | 80.0 | - | 18.7 | 1.0 | 0.3 | - | - | 0.61 |
| 6 | - | 80.0 | 18.7 | 1.0 | 0.4 | - | - | 0.55 |
| 7 | - | 46.0 | 49.9 | 4.0 | 0.1 | - | - | 0.93 |
| 8 | - | 64.8 | 31.0 | 4.0 | 0.2 | - | - | 0.74 |
| 9 | 29.0 | 20.0 | 49.9 | 1.0 | 0.1 | - | - | 0.93 |
| 10 | 41.0 | 39.0 | 18.7 | 1.0 | 0.3 | - | - | 0.61 |
| 11 | 30.0 | 32.6 | 35.0 | 2.0 | 0.4 | - | - | 0.55 |
| 12 | 32.6 | 30.0 | 33.4 | 3.0 | - | 1.0 | - | 0.94 |
| 13 | 50.0 | - | 45.0 | 3.0 | - | 2.0 | - | 0.75 |
| 14 | - | 44.0 | 49.5 | 2.5 | - | 4.0 | - | 0.57 |
| 15 | 25.0 | 20.0 | 50.0 | 4.0 | - | - | 1.0 | 0.92 |
| 16 | 78.0 | - | 16.0 | 3.0 | - | - | 3.0 | 0.59 |
| 17 | - | 59 | 35.5 | 1.5 | - | - | 4.0 | 0.53 |
| 18 | 50.0 | 46.0 | 4.0 | - | - | - | - | 1.19 |
From top table, can find out, contain the oxide expendable material of subject additives of the present invention, compare with Quality control 18, the neutron multiplication factor is obviously reduced; The K value drops to 0.53 to 0.57, illustrates that the melt of simulation nuclear reactor fusing lining has dark subcritical state, guarantees reliable nuclear safety.Data from table it can also be seen that gadolinium oxide is especially effective as subject additives, surpass to use Eu
2O
3Or Sm
2O
3The result's who obtains the order of magnitude.
Industrial usability
Material of the present invention can be applicable in the trap of nuclear reactor fusing lining, particularly the reactor of nuclear power station and other nuclear power equipment.
Claims (5)
1, a kind of oxide material for molten-core catcher of nuclear reactor comprises for cooling and the oxidant of cooling fusing lining and the most active composition oxidation that will be wherein, it is characterized in that described material also contains subject additives, and described subject additives is by from Gd
2O
3, Eu
2O
3And Sm
2O
3The middle at least a oxide of selecting forms, and the content of described subject additives is 0.1-4 weight %.
2, oxide material as claimed in claim 1 is characterized in that using Gd
2O
3As subject additives, its content is 0.1-0.4 weight %.
3, oxide material as claimed in claim 1 is characterized in that using Eu
2O
3And/or Sm
2O
3As subject additives, its content is 1-4 weight %.
4, oxide material as claimed in claim 1 is characterized in that described cooling and oxidant comprise Fe
2O
3And/or Fe
3O
4, and Al
2O
3Fe wherein
2O
3And/or Fe
3O
4Content be 46-80 weight %, Al
2O
3Content be 16-50 weight %.
5, as any described oxide material in the claim 1 to 4, it is characterized in that this material also comprises SiO
2, its content is 1-4 weight %.
Applications Claiming Priority (4)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| RU2001128176 | 2001-10-12 | ||
| RU2001128176/06A RU2191436C1 (en) | 2001-10-12 | 2001-10-12 | Oxide material of nuclear reactor molten core catcher |
| RU0200027 | 2002-01-25 | ||
| RUPCT/RU02/00027 | 2002-01-25 |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN1500273A CN1500273A (en) | 2004-05-26 |
| CN1266706C true CN1266706C (en) | 2006-07-26 |
Family
ID=20253808
Family Applications (2)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CNB028075870A Expired - Fee Related CN1210723C (en) | 2001-10-12 | 2002-04-02 | Oxide material for molten core catcher of nuclear reactor |
| CNB028075889A Expired - Fee Related CN1266706C (en) | 2001-10-12 | 2002-04-02 | Oxide material for molten core catcher of nuclear reactor |
Family Applications Before (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CNB028075870A Expired - Fee Related CN1210723C (en) | 2001-10-12 | 2002-04-02 | Oxide material for molten core catcher of nuclear reactor |
Country Status (3)
| Country | Link |
|---|---|
| CN (2) | CN1210723C (en) |
| FI (1) | FI118655B (en) |
| RU (1) | RU2191436C1 (en) |
Families Citing this family (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP1799962A2 (en) | 2004-09-14 | 2007-06-27 | Carbo Ceramics Inc. | Sintered spherical pellets |
| BRPI0609373A2 (en) | 2005-03-01 | 2010-03-30 | Carbo Ceramics Inc | methods for producing sintered particles of a slurry from an alumina-containing raw material |
| US7828998B2 (en) | 2006-07-11 | 2010-11-09 | Carbo Ceramics, Inc. | Material having a controlled microstructure, core-shell macrostructure, and method for its fabrication |
| CA2661799A1 (en) | 2006-08-30 | 2008-03-06 | Carbo Ceramics Inc. | Low bulk density proppant and methods for producing the same |
| US7721804B2 (en) | 2007-07-06 | 2010-05-25 | Carbo Ceramics Inc. | Proppants for gel clean-up |
| RU2517436C2 (en) * | 2012-09-03 | 2014-05-27 | Закрытое акционерное общество "НПО Петропромсервис" | Method of producing ceramic material for nuclear reactor core melt localising apparatus |
| RU2586224C1 (en) * | 2015-01-28 | 2016-06-10 | Федеральное государственное бюджетное образовательное учреждение высшего профессионального образования "Санкт-Петербургский государственный технологический институт (технический университет)" | Single-phase ceramic oxide material for core melt localisation device |
| CN111430051B (en) * | 2020-04-02 | 2022-02-22 | 中国核动力研究设计院 | Metal layer molten pool heat transfer characteristic simulation material, preparation method and application |
| CN115196930A (en) * | 2022-08-02 | 2022-10-18 | 南京林业大学 | Sacrificial mortar for reactor core catcher and preparation method |
-
2001
- 2001-10-12 RU RU2001128176/06A patent/RU2191436C1/en active
-
2002
- 2002-04-02 CN CNB028075870A patent/CN1210723C/en not_active Expired - Fee Related
- 2002-04-02 CN CNB028075889A patent/CN1266706C/en not_active Expired - Fee Related
-
2004
- 2004-04-08 FI FI20040517A patent/FI118655B/en not_active IP Right Cessation
Also Published As
| Publication number | Publication date |
|---|---|
| CN1500273A (en) | 2004-05-26 |
| FI20040517A (en) | 2004-06-11 |
| RU2191436C1 (en) | 2002-10-20 |
| CN1210723C (en) | 2005-07-13 |
| FI20040517A0 (en) | 2004-04-08 |
| CN1500272A (en) | 2004-05-26 |
| FI118655B (en) | 2008-01-31 |
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