CN1210723C - Oxide material for molten core catcher of nuclear reactor - Google Patents
Oxide material for molten core catcher of nuclear reactor Download PDFInfo
- Publication number
- CN1210723C CN1210723C CNB028075870A CN02807587A CN1210723C CN 1210723 C CN1210723 C CN 1210723C CN B028075870 A CNB028075870 A CN B028075870A CN 02807587 A CN02807587 A CN 02807587A CN 1210723 C CN1210723 C CN 1210723C
- Authority
- CN
- China
- Prior art keywords
- oxide
- melt
- content
- nuclear reactor
- zirconium
- 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.)
- Expired - Fee Related
Links
Images
Classifications
-
- 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
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
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 up to 15 mass % of SrO, CeO 2, BaO, Y2O3 and La2O3, preferentially ranging from 2 to 15 mass % and most preferably ranging from 3 to 15 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 (molten corium trap), make fusing lining (molten corium) location (localization) of airtight water cooled nuclear reactor when being intended for 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, to prevent preventing promptly that from the generation of keeping chain reaction of nuclear fission the nuclear reaction in the melt is converted to overcritical pattern.Thus, expendable material itself dissolves gradually by complex physicochemical process, 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 under many circumstances and makes nuclear reactor melt the reliable system of lining location and the manufacturing of the effective expendable material of nuclear reactor.
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 the systematic approach that uses Theoretical Calculation and 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 medium.But iron and steel can not influence the oxide part of melt, and main radiation is arranged in oxide and nuclear chain reaction can take place.And, this cooling medium 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.
The gaseous products that from melt, forms during by the oxide oxidation of silicon or aluminium when zirconium, cause radioactive nuclide to increase fast with the release of smog form, smog enters container (the containment) (space at nuclear reactor place, when nuclear power station has an accident, seal) and pass the shell formation that seals described space and reveal, the radioactive contamination of environment caused.
Radioactive nuclide is the radioactive isotope that is present in the various chemical elements of fusing in the lining, and is that atomic nucleus radiation decay by radioelement is deformed into.Radioactive isotope depends on that to the pollution level of environment they enter the quantity of gas phase from melt, so correspondingly depends on their quantity (concentration) and volatility in melt.Radioisotopic concentration and volatility are high more, volatilization and to enter the quantity of environment by all means big more from melt.Particular isotope is to the harm of the radioactive contamination generation of environment, and promptly to biology, especially Ren Lei harm is depending on its half life period and the ability of gathering in human body on the large program very much, particularly in marrow and lung.The isotopic half life period is long more, and is long more to the harm of environment.Isotope is difficult to remove from human body more, and its harm is long more, and this will cause a lot of diseases, particularly cancer.
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 the melt cooling and are positioned in the trap.
In addition, when using this material, oxidized silicon of zirconium and aluminium oxide oxidation.But this oxidation occurs over just high temperature, promptly in a short period of time, reduces owing to contacting with expendable material until temperature of fusion.For example, the oxidation of the oxidized aluminium of zirconium occurs over just the temperature more than 2300 ℃.When temperature reduced, the zirconium of complete oxidation was not retained in the fusing lining, as mentioned above, just discharged hydrogen when zirconium and water vapor interaction.
In order to make more effectively oxidation of zirconium, having proposed a 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 iron oxide, silicon dioxide and aluminium oxide and boron, calcium, magnesium, with the hopcalite of chromium 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%.
Although use iron oxide to improve the oxidation of zirconium, because the temperature that this reaction takes place is lower than the temperature of the oxidized aluminaization of zirconium, but the iron oxide that exists with above-mentioned quantity in the known expendable material can not will cause hydrogen to generate the zirconium complete oxidation that exists in a large number in the fusing lining.Use silicon dioxide also can generate gaseous products, since silicon dioxide and zirconium reaction, the silicon monoxide of generation gaseous state in the course of reaction.As a result, increased distributing of radioactive nuclide.
Basic purpose of the present invention provides a kind of oxide material, be used for molten-core catcher of nuclear reactor, thereby reduce distributing of radioactive nuclide by location (localization) to melt, and radioactive nuclide contaminated environment and greatly to biology, particularly the mankind cause great harm, reduce simultaneously thus pollution level with and harmful aftereffect.
Summary of the invention
Consider above-mentioned basic purpose, propose a kind of oxide material that is used for nuclear reactor fusing lining, comprise cooling and oxygenant, be used to cool off 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 SrO, CeO
2, BaO, Y
2O
3And La
2O
3The subject additives that the middle at least a oxide of selecting is formed.
Introduce this subject additives, make because the radioactive isotope oxide that exists in the melt is diluted by the stable isotope oxide of identical element, and because these oxides of being found by the present inventor depart from the Henry law, can reduce the concentration of radioactive isotope in gas phase of corresponding chemical element greatly, as what describe in detail below, these radioactive isotopes belong to those to environment and biology, especially harmful to mankind isotope.
The present inventor finds that the partial vapour pressure of the oxide of Sr, Ce, Ba, La and Y departs from known Henry law, is nonlinear relationship with the concentration of corresponding oxide in the liquid phase (melt).These nonlinear relation tables are shown curve, and the derivative of oxide concentration (derivative) descends fast with respect to the concentration of identical oxide in the liquid phase in its gas phase.As a result, by in expendable material, introducing the corresponding oxide of stable isotope, can obviously reduce radioisotopic concentration in the gas phase (doubly a lot) to the dilution of radioactive isotope oxide in the liquid phase.
The content of described subject additives can be up to 15wt%, preferably 2～15wt%, more preferably 3～15wt%.
The cooling and the oxygenant of the oxide material of molten-core catcher of nuclear reactor preferably include Fe
2O
3And/or Fe
3O
4, and Al
2O
3Fe
2O
3And/or Fe
3O
4Content be 46～80wt%, Al
2O
3Content be 16～50wt%.
The present inventor finds, uses this cooling and oxygenant, because the iron oxide content height, and, reduced the generation of hydrogen to the oxidation more up hill and dale of the zirconium in the melt.And iron oxide and zirconium instead would not generate gaseous products, and this has also reduced the release of radioactive nuclide.
Because the oxide Combination of uranium is good in the oxide of iron and aluminium and the melt, the density of the oxide part of melt obviously reduces, and causes inversion, that is, oxide partly rises to the surface of metal part top.This has also hindered the generation of hydrogen, and described hydrogen is that the Metal Contact in water or water vapour and the metal part that lacks melt oxidation thing part produces.
The oxide of iron and aluminium forms solid solution in course of reaction.Aluminium oxide forms the zirconium oxidation Al of gaseous state when its free state
2O, and in the solution of iron oxide, do not react with zirconium, therefore do not form gaseous products, also reduced radioisotopic release.
Oxide expendable material of the present invention can further contain silicon dioxide, and its content can be up to 4wt%, preferably 1～4wt%.
Because fully with the zirconium oxidation, therefore when using a spot of silicon dioxide like this, silicon dioxide does not react with zirconium and does not produce gaseous products (silicon monoxide) in real process for the iron oxide of high-load.Simultaneously, add a spot of silicon dioxide like this and make the intensity of expendable material increase 40～50%, because generated SiO
2With Al
2O
3Compound (mullite).
Description of drawings
Fig. 1 represents, after the expendable material reaction, and strontium oxide strontia concentration (dividing potential drop) p in the gas phase
SrO(r) with the fusing lining in the strontium oxide strontia concentration C
SrORelation curve.
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 required subsequently blending ratio, then will represent the raw material of cooling and oxygenant stock to mix and the dry type vibratory grinding, and also with subject additives (SrO and/or CeO
2) carry out the dry type vibratory grinding separately, 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 transition cementing 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 places trap, for example is positioned at the nuclear reactor below, preferably puts 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 melt is cooled to about 2000 ℃, prevents 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.
When the melt lining cools off, radioactive nuclide, promptly the radioactive isotope of various chemical elements discharges from melt, when radioactive nuclide passes the border of container with contaminated environment.
In the radioactive isotope that from melt, discharges,
90Sr,
144Ce,
140Ba,
140La and
90Y is the most harmful.All these isotopes belong to those isotopes that accumulate in a large number in nuclear reactor fuel in the nuclear reactor operational process.In addition,
90Sr has the very long half life period (286 years), residual considerable time in environment, and have high volatility, can accumulation in a large number in marrow and lung.
144Ce also can keep (its half life period is 284.9 days) for a long time in environment, and has the strongest ability that accumulates in lung.
140Ba is one of element of volatility maximum, also can keep a lot of days (half life period is 12.75 days) in environment, and it can accumulate in marrow and lung.
140La can accumulate in marrow, particularly accumulation in a large number in lung.
90The quantity that Y accumulates in lung much larger than
140La.
As shown in Figure 1, the dividing potential drop of strontium oxide strontia steam and its concentration in melt is non-linear fully, that is, the speed that dividing potential drop increases descends fast with the increase of concentration.The relation curve of the oxide dividing potential drop of Ce, Ba, La and Y and their concentration in melt has similar shapes.As can be seen, described nonlinear relationship shows, can contain the identical oxide of non radioactive isotope by interpolation, reduces the content of radioisotopic oxide in gas phase of above-mentioned metal from curve.After adding the non radioactive isotope oxide, if the total concentration of given metal oxide in melt increases several times, the dividing potential drop of these oxides will increase lesser extent, reduce the dividing potential drop of radioisotopic oxide thus.For example, if the content of radioactivity strontium oxide strontia is 0.2% in the melt, its dividing potential drop is 0.3 * 10
-4Atm.When adding on-radiation strontium oxide strontia 2%, total dividing potential drop of strontium oxide strontia (radioactivity and on-radiation) owing to depart from the Henry law, will be 0.9 * 10
-4Atm promptly, is not big 11 times and only be 3 times.Because the radioactivity strontium oxide strontia accounts for 9% of its total quantity, so the dividing potential drop of radioactivity strontium oxide strontia will be 9% of total strontium oxide strontia dividing potential drop, promptly 0.08 * 10
-4Atm is perhaps than low 4 times approximately of initial values.If add 15% strontium oxide strontia in initial melt, total dividing potential drop of strontium oxide strontia will be 1.9 * 10
-4Atm, and the dividing potential drop of radioactivity strontium oxide strontia correspondingly is 0.025 * 10
-4Atm is promptly little 12 times than initial value.
Stable isotope adds in the fusing lining with the oxide expendable material with the form of oxide, can reduce corresponding radioisotope concentration in the gas phase doubly a lot.In this case, SrO will optionally act on
90The Sr isotope, CeO
2Optionally act on
144The Ce isotope, BaO optionally acts on
140The Ba isotope, La
2O
3Optionally act on
140The La isotope, Y
2O
3Optionally act on
90The Y isotope.The present inventor finds, SrO, CeO
2, BaO, Y
2O
3, La
2O
3Addition in expendable material can reduce during up to 15wt% greatly
90Sr,
144Ce,
140Ba,
90Y and
140The total defriment of La makes its danger change to the isotope suitable level very low with harmfulness.
Preferably, the upper limit of subject additives is 15wt%.When subject additives content was higher than 15wt%, the location validity that nuclear reactor is melted lining began to descend.Preferably, each the lower limit of content (or their summation) of these oxides is 2wt%, 3wt% more preferably, so that their additive effect unlikely too a little less than, because when described oxide content hangs down, the relation of content reaches the theoretical curve (promptly becoming straight line) that the Henry law is described in gaseous phase partial pressure and the melt.
When melt arrives expendable material, expendable material fusing and cold fuse-element.When using the material of preferred composition, promptly contain the Fe of 46～80wt% in cooling and the oxygenant
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 themopositive reaction of heat release takes place, melt remains on liquid phase a period of time thus, helps it and is diluted by expendable material effectively even the mixing also of expendable material.The high activity of described reaction makes the lining of expendable material and fusing form even melt fast, 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.
The strong oxidation of zirconium, avoided water vapour in zirconium and the container reaction and with reaction and the generation and the accumulation hydrogen of the water of cold fuse-element, cause burning and blast.
Because the oxide of aluminium and iron dilutes the oxide of uranium in the melt well, the oxide of melt partly becomes light and swims on the surface of metal part in the melt, that is, melt is inverted.Metal partly moves downward, and prevents the metal in the metal part, as chromium, iron and nickel, is formed hydrogen by steam oxidation.Before all zirconium oxidations, these metals can be by the oxide oxidation of expendable material.Because zirconium has high dissolubility in melt oxidation thing part, therefore the oxidation of zirconium is still proceeded after melt is inverted.
In this case, although the content height of aluminium oxide in expendable material, the zirconium in the melt does not form gaseous products with the aluminium oxide reaction, causes the release of radioactive nuclide.This is because the oxide of iron and aluminium forms compound (solid solution).Aluminium oxide in this solid solution when when fusing, the zirconium in the not oxidation melt, thereby prevents the formation of gaseous products.
Preferably the content of iron and aluminium is balance in the composition of oxide expendable material of the present invention, thereby makes the zirconium complete oxidation in the fusing lining, prevent to generate hydrogen, and the accumulation of hydrogen will cause burning and blast; And prevent that the formation of other volatile matter and the radioactive nuclide of volatilization are discharged in the environment.
If the Fe in the material
2O
3And/or Fe
3O
4Content is less than 46wt%, then can not make the zirconium oxidation fully owing to lack oxygen, causes other gaseous state and formation volatile products of hydrogen and harmfulness, increases the release of radioactive nuclide.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, and then radioactive nuclide is discharged in a large number.
If Al
2O
3Content is less than 16wt%, and then themopositive 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 positioning system certainly.If Al
2O
3Content surpasses 50wt%, then because Fe
2O
3And/or Fe
3O
4Lazy weight and can not guarantee the oxidation of zirconium, the liquidus temperature of melt raises, and causes unoxidized zirconium to contact generation hydrogen with water vapour, 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, and not cause the layering of the system that comprises trap oxide material and nuclear reactor fusing lining.
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.
By model experiment and calculation of thermodynamics, assessed material of the present invention nuclear reactor has been melted the effectively ability of location of lining.
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 step 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, liquidus curve (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 inductive coil are isolated.On the sealing quartz container of stove above the cold crucible, adorn a lid, cover and have perforate, be used to install pyrometer, measure pool depth and also observe 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.The mensuration of isotope dividing potential drop is the high temperature mass spectrometer by the gas phase of corresponding melt top.
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,, thermal effect is calculated as enthalpy poor of system by calculation of thermodynamics, that is, when the institute that takes place in taking into account system responds, the heat of release when melt cool off by expendable material.
Listed the embodiment of expendable material that constitute according to the present invention and process present inventor test in the following table, it is as shown in the table for its composition and character.Embodiment 1 is the contrast oxide expendable material that does not have subject additives, and embodiment 2-9 is the expendable material that the present invention contains subject additives.
Table adds SrO, CeO
2, BaO, Y
2O
3And La
2O
3Influence to oxide expendable material characteristic
| Material composition, wt% | The embodiment numbering | |||||||||
| 1 | 2 | 3 | 4 | 5 | 6 | 7 | 8 | 9 | ||
| Fe 2O 3 | 50 | 65 | - | - | 26 | 49.6 | - | - | 60 | |
| Fe 3O 4 | - | - | 79 | 62 | 30 | - | 52 | 55 | - | |
| Al 2O 3 | 46 | 23.8 | 16 | 20 | 23 | 31 | 40 | 25 | 17 | |
| SiO 2 | 4.0 | 1.0 | 1.0 | 4.0 | 4.0 | 4.0 | 4.0 | 1.0 | 4.0 | |
| SrO | - | 10 | - | - | 10 | - | - | - | - | |
| CeO 2 | - | - | 3.0 | 10 | 5 | - | - | - | - | |
| BaO | - | - | - | - | - | 15 | - | - | - | |
| Y 2O 3 | - | - | - | - | - | - | 3.0 | 1.5 | - | |
| La 2O 3 | - | - | - | - | - | - | - | - | 15 | |
| Oxide dividing potential drop atm * 10 6 | 90 | 15 | 3 | 15 | 16 | 3 | 16 | 15 | 15 | 15 |
| 144Ce | 31 | 32 | 12 | 5 | 10 | 32 | 31 | 31 | 31 | |
| 140Ba | 17 | 18 | 17 | 17 | 18 | 2 | 17 | 16 | 17 | |
| 90Y | 9 | 9 | 9 | 9 | 8 | 10 | 3 | 1 | 10 | |
| 140La | 12 | 11 | 13 | 12 | 12 | 11 | 12 | 13 | 2 | |
From top table, as can be seen, contain the expendable material of the present invention of subject additives, nuclear reactor is melted the burden of a radioisotope that volatilizees in the gas phase of lining top reduced a lot of doubly (reaching 7 times), particularly strontium and cerium.
Industrial usability
Material of the present invention is applied in the trap of nuclear reactor fusing lining, and the reactor of nuclear power station and other nuclear power equipment particularly is for they provide security.
Claims (7)
1. oxide material that is used for molten-core catcher of nuclear reactor, comprise the cooling and the oxygenant that are used to cool off the fusing lining and incite somebody to action the most active composition oxidation wherein, it is characterized in that described material also contains subject additives, described subject additives is by from SrO, BaO, Y
2O
3And La
2O
3The middle at least a oxide of selecting is formed.
2. oxide material as claimed in claim 1 is characterized in that the content of subject additives mostly is 15wt% most.
3. oxide material as claimed in claim 2, the content that it is characterized in that subject additives is 2～15wt%.
4. as claim 2 or 3 described oxide materials, the content that it is characterized in that subject additives is 3～15wt%.
5. oxide material as claimed in claim 1 is characterized in that described cooling and oxygenant comprise Fe
2O
3And/or Fe
3O
4, and Al
2O
3Fe wherein
2O
3And/or Fe
3O
4Content be 46～80wt%, Al
2O
3Content be 16～50wt%.
6. as claim 1 or 5 described oxide materials, it is characterized in that also comprising SiO
2, its content mostly is 4wt% most.
7. oxide material as claimed in claim 6 is characterized in that SiO
2Content be 1～4wt%.
Applications Claiming Priority (4)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| RU2001128176/06A RU2191436C1 (en) | 2001-10-12 | 2001-10-12 | Oxide material of nuclear reactor molten core catcher |
| RU20011281764 | 2001-10-12 | ||
| RUPCT/RU02/00027 | 2002-01-25 | ||
| RU0200027 | 2002-01-25 |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN1500272A CN1500272A (en) | 2004-05-26 |
| CN1210723C true CN1210723C (en) | 2005-07-13 |
Family
ID=20253808
Family Applications (2)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CNB028075889A Expired - Fee Related CN1266706C (en) | 2001-10-12 | 2002-04-02 | Oxide material for molten core catcher of nuclear reactor |
| CNB028075870A Expired - Fee Related CN1210723C (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 |
|---|---|---|---|
| CNB028075889A Expired - Fee Related CN1266706C (en) | 2001-10-12 | 2002-04-02 | Oxide material for molten core catcher of nuclear reactor |
Country Status (3)
| Country | Link |
|---|---|
| CN (2) | CN1266706C (en) |
| FI (1) | FI118655B (en) |
| RU (1) | RU2191436C1 (en) |
Families Citing this family (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US20060081371A1 (en) | 2004-09-14 | 2006-04-20 | Carbo Ceramics Inc. | Sintered spherical pellets |
| WO2006094074A2 (en) | 2005-03-01 | 2006-09-08 | Carbo Ceramics Inc. | Methods for producing sintered particles from a slurry of 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 |
| WO2008028074A2 (en) | 2006-08-30 | 2008-03-06 | Carbo Ceramics Inc. | Low bulk density proppant and methods for producing the same |
| EA201000114A1 (en) | 2007-07-06 | 2010-06-30 | Карбо Керамикс Инк. | PROPPANT AND METHOD OF HYDRAULIC PLASTING OF THE PLATE (OPTIONS) |
| 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 CNB028075889A patent/CN1266706C/en not_active Expired - Fee Related
- 2002-04-02 CN CNB028075870A patent/CN1210723C/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 |
|---|---|
| FI118655B (en) | 2008-01-31 |
| CN1266706C (en) | 2006-07-26 |
| CN1500272A (en) | 2004-05-26 |
| RU2191436C1 (en) | 2002-10-20 |
| FI20040517A0 (en) | 2004-04-08 |
| FI20040517A (en) | 2004-06-11 |
| CN1500273A (en) | 2004-05-26 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| Lee et al. | Immobilisation of radioactive waste in glasses, glass composite materials and ceramics | |
| Kaushik et al. | Barium borosilicate glass–a potential matrix for immobilization of sulfate bearing high-level radioactive liquid waste | |
| CN1210723C (en) | Oxide material for molten core catcher of nuclear reactor | |
| CN1244933C (en) | Oxide material for molten-core catcher of nuclear reactor | |
| FI118444B (en) | Oxide material trapped in the melted core of a nuclear reactor | |
| Creek | Experiments on the Release of Fission Products from Molten Reactor Fuels | |
| US8969646B2 (en) | Ceramic ingot of spent filter having trapped radioactive cesium and method of preparing the same | |
| STCMTON et al. | Coating of crystalline nuclear waste forms to improve inertness | |
| Uda et al. | Decontamination of uranium-contaminated mild steel by melt refining | |
| Journeau et al. | Transient interactions of boron carbide with molten uranium oxide | |
| US6190582B1 (en) | Controlled atmosphere sintering process for urania containing silica additive | |
| Ding et al. | The radioactive materials within accident reactors: A review of damaged fuel-containing materials | |
| JP2002020827A (en) | Melting crucible | |
| Jeon et al. | Compositional design of an amphoteric chemical trap for the capturing of gaseous cesium and iodine in UO2 nuclear fuel | |
| Barinova et al. | Self-propagating high-temperature synthesis for disposal of radioactive waste | |
| Laffolley et al. | Thermodynamics of aerosols during a molten core-concrete interaction at Fukushima Daiichi Unit 2 estimated conditions | |
| Fischer et al. | Investigation of the distribution of fission products among molten fuel and reactor phases:(II). The distribution of fission products between molten iron and a molten uranium dioxide-basalt mixture | |
| Chellew et al. | The Melt Refining of Irradiated Uranium: Application to EBR-II Fast Reactor Fuel. XI. Behavior of Iodine in Melt Refining | |
| Lee et al. | Processing ceramics for radioactive waste immobilisation | |
| US3303140A (en) | Radioactive materials of low surface area | |
| Swift | Preparation and Evaluation of Uranium Alloys Based on Burnup | |
| Parker et al. | Source-term evaluations from recent core-melt experiments | |
| Strachan et al. | Fiscal Year 2010 Summary Report on the Epsilon-Metal Phase as a Waste Form for 99 Tc | |
| Chellew et al. | Laboratory Studies of Iodine Behavior in the EBR-II Melt Refining Process | |
| Smolik et al. | Volatility from copper and tungsten alloys for fusion reactor applications |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C06 | Publication | ||
| PB01 | Publication | ||
| C10 | Entry into substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| CF01 | Termination of patent right due to non-payment of annual fee |
Granted publication date: 20050713 Termination date: 20160402 |
|
| CF01 | Termination of patent right due to non-payment of annual fee |