GB1588350A - Method of anchoring radioactive waste from nuclear fuel in a body resistant to leaching by water - Google Patents
Method of anchoring radioactive waste from nuclear fuel in a body resistant to leaching by water Download PDFInfo
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- GB1588350A GB1588350A GB4537977A GB4537977A GB1588350A GB 1588350 A GB1588350 A GB 1588350A GB 4537977 A GB4537977 A GB 4537977A GB 4537977 A GB4537977 A GB 4537977A GB 1588350 A GB1588350 A GB 1588350A
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- Prior art keywords
- leaching
- resistant
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/28—Treating solids
- G21F9/30—Processing
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- C—CHEMISTRY; METALLURGY
- C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
- C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
- C04B35/00—Shaped ceramic products characterised by their composition; Ceramics compositions; Processing powders of inorganic compounds preparatory to the manufacturing of ceramic products
- C04B35/622—Forming processes; Processing powders of inorganic compounds preparatory to the manufacturing of ceramic products
- C04B35/64—Burning or sintering processes
- C04B35/645—Pressure sintering
- C04B35/6455—Hot isostatic pressing
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- Engineering & Computer Science (AREA)
- Chemical & Material Sciences (AREA)
- Ceramic Engineering (AREA)
- Manufacturing & Machinery (AREA)
- Structural Engineering (AREA)
- Materials Engineering (AREA)
- Inorganic Chemistry (AREA)
- Organic Chemistry (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Processing Of Solid Wastes (AREA)
- Solid-Sorbent Or Filter-Aiding Compositions (AREA)
Description
(54) METHOD OF ANCHORING RADIOACTIVE WASTE FROM
NUCLEAR FUEL IN A BODY RESISTANT TO LEACHING BY WATER
(71) We, ASEA AKTIEBOLAG, a
Swedish Company of Västerås, Sweden, do herebv declare the invention, for which we pray tnat a Patent may be granted to us, and the method by which it is to be performed, to be particularly described in and by the following Statement:
This invention relates to a method of anchoring radioactive waste from nuclear fuel in a body resistant to leaching by water.
In the reprocessing of radioactive waste from nuclear reactors which are being used today, the high-level waste is obtained in a strong nitric acid solution. The dominating radioactive substances in the waste during the first centuries are strontium-90 and cesium-137. The waste also contains, among other things, minor amounts of uranium and plutonium and transuranic elements, which have considerably greater half-lives than strontium-90 and cesium-137. Those skilled in the art are generally of the opinion that it is advantageous, after a suitable period of cooling, to convert the liquid high-level waste into a solid. A solid product of good chemical resistance is aimed at. It must be stable to leaching out of radioactive material, contained in it, by water.It must withstand heating produced by the fission products and it must withstand stresses caused during handling and transportation.
Among materials that have been proposed for containment of the high-level waste may be mentioned glass such as boron silicate glass and phosphate glass, quartz. titanium dioxide, certain zeolites and other minerals existing in nature, particularly those having the ability to retain gases.
In a known method of containing highlevel waste in glass. the waste is evaporated and calcined and additives are added thereto which, when heated to 1000-1200 C, result in a glass melt. The melt is filled into tight steel containers which are transferred to a cooled and supervised storage plant.
Calcination of high-level waste can take place at a temperature of the order of from 300 to 500"C and results in the waste products being transformed into oxides.
The present invention relates to a method of containing radioactive waste from nuclear fuel which enables an extremely efficiently controllable handling of the material during the process of containment, as well as an efficient containment in a resistant material.
According to the invention, a method of anchoring radio active waste from nuclear fuel in a body which is resistant to leaching by water, is characterised in that a mass containing radioactive constituents and constituents which are resistant to leaching by water or which, when heated, form constituents resistant to leaching by water, is subjected to isostatic pressing enclosed in a casing at a pressure and temperature necessary for the formation of a coherent, dense body of the mass. The casing is preferably evacuated prior to sealing.
When the radioactive material has been isolated from solution, which may, for example, take place in conventional manner by evaporation, possibly followed by calcination, it is kept closed in a casing all the time during the containment process, and neither gaseous nor liquid products are able to escape from this casing. This result is obtained bv subjecting the casing after sealing to a hot-isostatic pressing. The isostatic pressure counteracts the formation of volatile constituents in the material contained in the casing during the heating that is required for the contained material to be transformed into a coherent, dense unit, while at the same time achieving the necessary compression of the material. An important advantage of the method is that it enables the material to be enclosed in a casing when the material is at room temperature.Another important advantage of the invention is that it affords great freedom in choosing resistant materials for the containment of the radioactive material therein.
In one emboidment of the invention, particles of a radioactive material are mixed with particles of a material resistant to leaching by water to form a mass which is subjected to isostatic pressing enclosed in a casing at the pressure and temperature required for the formation of said coherent, dense body of the mass.
The material resistant to leaching by water may advantageously be composed of oxides of a kind normally comprised in glass of various kinds and in minerals, for example, SiO2, B203, Awl203, MgO, alkali metal oxides, alkaline earth metal oxides, TiO2,
ZrO2, Fe2O3, Fe304 and Cr203. Further, the material may consist, inter alia, of minerals existing in nature and well known for their long-term stability, for example minerals composed of silicates, aluminates, chromates and titanates. Minerals with the ability to retain gases may be of special interest, as well as zeolites with the ability to take up selectively strontium and ces;um from a solution. Also glass, such as boron silicate glass and phosphate glass may be used.Among preferred materials may be mentioned aluminium oxide, titanium oxide, quartz and rocks existing in nature.
The particle size of the radioactive material and of the resistant material may advantageously be below 325 mesh on the ASTM scale. Of the total weight of radioactive material and resistant material in the mixture, the weight of radioactive material constitutes preferably 15-40 per cent and the weight of resistant material preferably 60-85 per cent.
In another embodiment of the invention, a particulate mass containing a material resistant to leaching by water in which the radioactive material is fixed, or a material in which the radioactive material is fixed and which upon heating forms a material resistant to leaching by water, is subjected to isostatic pressing enclosed in a casing at the pressure and temperature necessary for the formation of said coherent. dense body of the mass.
The material resistant to leaching by water, in which the radioactive material is fixed, may consist, inter alia. of insoluble salts or other insoluble compounds of the radioactive material, for example titanates, aluminates, phosphates, silicates and oxides. The salts or the other compounds may be precipitated from solutions containing radioactive material by adding corresponding soluble salts. The particles of the resistant material suitably have a size of below 1 mm.
The material in which the radioactive material is fixed and which upon heating forms a material resistant to leaching by water may consist, inter alia, of ion exchangers which have taken up the radioactive material through ion exchange upon contact with a solution containing radioactive material. A suitable size of the particles of the material is from 0.1 to 1 mm. Examples of ion exchangers which may be used for taking up radioactive material are zeolites and compounds of the formula M [M'xOyH,in, where M is an exchangeable cation of tne charge +n and M' may be Ti,
Nb, Zr or Ta, for example NaTi2OsH. Ion exchangers which have taken up radioactive material normally form multi-phase polycrystalline, ceramic materials upon heating, which are resistant to leaching by water.For example, upon contact with a solution containing radioactive strontium, NaTi2O5H forms Sr [Ti2OsH] 2 which, when heated, is broken down into SrTiO3 and TiO2.
According to this second embodiment one or more materials resistant to leaching by water other than that in which radioactive material is fixed or that which is formed during the heating previously mentioned, respectively, may be incorporated in the particulate mass. As examples of such other resistant material may be mentioned oxides normally comprised in various minerals, for example, SiO2, B203, Awl203, MgO, alkali metal oxides, alkaline earth metal oxides,
TiO2, ZrO2, Fe2O3 and Cr2O3, and other minerals existing in nature and well-known for their long-term stability, for example minerals composed of silicates, aluminates, phosphate and titanates. Among preferred materials may be mentioned aluminium oxide, titanium oxide, quartz and minerals existing in nature.The mentioned resistant material may also be added to materials which are brought into contact with the radioactive material and in which the radioactive material is then fixed. Thus, said resistant materials rnay be mixed with ion exchangers before the ion exchangers are brought into contact with the radioactive material. Such a measure reduces the handling of radioactive material. A suitable amount of resistant material incorporated in the particle mass may be from 1 to 95 per cent of the total weight of particle mass and the incorporated material. The particles of the incorported resistant material suitably have a size of less than 1 mm, and preferably less than 0.5 mm.
The casing may consist, inter alia, of metallic sheet material, for example of tantalum, titanium, zirconium, alloys based on these metals, (for example, "Zircaloy"), steel. iron or nickel, or may consist of quartz glass or boron silicate glass. The casing material should be adapted to the resistant material so that it has a sufficiently high melting point for the casing to fulfil its duties, and substantially the same coefficient of thermal expansion in those cases in which the casing is left to provide a reinforced containment. When quartz or titanium oxide is used as the resistant material, quartz glass is preferred for the capsule, and with boron silicate glass as the resistant material a casing of this material is preferred.In certain cases it may be suitable to use a metallic casing which is provided internally with a layer of quartz or boron silicate glass.
Between the casing and the mass to contained it may be suitable to arrange an intermediate layer of a resistant material, for example any of the previously exemplifed resistant materials. It may be particularly suitable to use as intermediate layer a material of the same chemical composition as the mass, but without radioactive isotooes. The particles of the material in the intermediate layer suitably have a size of less than 1 mm and preferably less than 0.2 mm. The intermediate layer may, for example, be applied as a layer of a thickness of a few mm or cm on the inner wall of the casing.
The pressure during the isostatic pressing suitably amounts to at least 100 bar, and is suitably between 500 and 3000 bar. The temperature is, of course, dependent on what materials are included in the particulate compound but is at least 7000C. A suitable temperature for particulate masses containing titanates, quartz or titanium dioxide is from 1200 to 1300"C and for particulate masses containing aluminates and aluminium oxide from 12500 to 13500C.
The invention will now be further described in a number of non-limitative Examples (in which parts and percentages are by weight) and with reference to the accompanying drawing, in which
Figure 1 shows a capsule containing a mixture of high-level waste and resistant material, and
Figure 2 is a schematic, partly sectioned, side view of a high-pressure furnace in which the pressing and the sintering of the said mixture are performed.
Example 1
25 parts of high-level waste from a plant for reprocessing waste from a nuclear reactor, which has been converted into oxides in conventional manner and which has a particle size of less than 80 mesh (on the ASTM scale), is mixed with 75 parts of quartz powder having a particle size of less than
100 mesh (on the ASTM scale). Prior to this the quartz has been treated in vacuum to remove dissolved gases. The mixture 10 is placed in accordance with Figure 1 in a capsule 11 of "Vycor" (RTM) glass which, to the extent of 96 per cent, consists of quartz and which is considered to fall under the concept of quartz glass as used in this specification. When the mixture is introduced into the capsule the latter has no indentation. The capsule is then degassed at room temperature at a pressure of 1 bar with a vacuum pump connected to the opening 12.The capsule is then sealed at this pressure by fusing the capsule at 13.
In Figure 2, the numeral 22 designates a displaceable press stand. It is supported by wheels 23 running on rails 24 on a floor. The press stand is of the type which consists of an upper yoke 26, a lower yoke 27 and a pair of spacers 28 which are held together by a prestressed strip sheath 29. The press stand is movable between the position shown in
Figure 2 and a position where the stand surrounds a high-pressure chamber 42. The high-pressure chamber 42 is supported by a column 49 and contains a high-pressure cylinder which is built up from an inner tube 50, a surrounding prestressed strip sheath 51 and end rings 52 which axially hold together the strip sheath and constitute a suspension device by which the high-pressure chamber is attached to the column 49. The chamber 42 has a lower end closure 53 projecting into the tube 50 of the high-pressure cylinder.In the end closure there isa slot in which there are arranged a sealing ring 54, a channel 55 for the supply of pressure medium, suitably argon or helium, and a channel 56 for cables for feeding heating elements 57 for the heating of the furnace. The elements 57 are supported by a cylinder 58 resting on an insulating bottom 59, which protrudes into an insulating sheath 60. The upper end closure comprises an annular portion 61 with a sealing ring 62 which seals against the tube 50. The sheath 60 is suspended from portion 61 and is connected in a gas-tight manner thereto. The end closure also comprises a lid 63 for closing the opening in portion 61, which is usually permanently mounted in the high-pressure cylinder.The lid is provided with a sealing ring 64 sealing against the inner surface of portion 61 and with an insulating lid 65 which, when the high-pressure chamber is closed, projects into cylinder 60 and constitutes part of the insulating shell which surrounds the furnance space 66. The lid 63 is fastened to a bracket 67 which is carried by a raisable, lowerable and rotatable operating rod 68.
Yokes 26 and 27 take up the compressive forces acting on end closure 53 and lid 63 when pressure is applied to the furnace space. the
When the capsule 11 has been placed in the furnace space 66, the lid 63 first having been lifted up and then lowered for closing the furnace space, the pressure and the temperature are successively increased to around 2000 bar and about 1200"C, respec tively, and are maintained at these values for about two hours, when the desired density and sintering have been obtained.
The capsule with the enclosed material is then allowed to cool, whereafter the pressure is reduced to atmospheric pressure and the capsule is removed from the furnace.
The capsule is allowed to remain as reinforcement. The capsule may be transported for permanent storage possible enclosed in a steel container.
Example 2
A waste solution from a plant for reprocessing of high level waste from a nuclear reactor consists of a 2-molar nitric acid solution and contains in the form of radioactive substances 7.0 g/l of Zr, 6.9 g/l of Mo, 8.0 g/l of Nd, 4.5 g/l of Ru, 5.4 g/l of Cs, 4.8 g/l of Ce, 3.8 g/l of Fe, 3.1 g/l of Pd, 3.3 g/l of Ba, 1.5 g/l of Sr, 2.5 g/l of La, 2.3 g/l of Pr, 2.3 g/l of Am, 12.6 g/l of U, 23.8 g/l of Gd and a plurality of other radioactive substances in lower contents. The pH of the solution is adjusted to around 1 by adding amonia. It is then conducted through a cylindrical column of titanium containing an ion exchanger consisting of NaTi2OsH in the form of particles having a size of from 0.1 to 1 mm.The ion exchanger is mixed up with the same quantity by weight of particles of
TiO2 having a size of from 0.1 to 0.5 mm.
The solution is then conducted through a second cylindrical column of titanium containing an ion exchanger consisting of a zeolite of the formula Na8Al8Si40096- 24H2O. This ion exchanger also consists of particles of a size of from 0.1 to 1 mm.
The two columns are then relieved of their contents of water by being heated to around 900"C under vacuum. The ion exchangers are then at least partially decomposed. This leads to the formation of titanate containing radioactive substances and titanium dioxide in the first column.
Each column with its contents is then placed in a cylindrical capsule made of steel of low carbon content and provided with a bottom, and is then embedded in titanium dioxide powder having a particle size of less than 0.2 mm, so that the spaces between the capsule and the column around the envelope surface of the column as well as above its top and below its bottom are filled up with the titanium dioxide powder. Titanium dioxide powder will also fill up any spaces in the column which are accessible to the powder. Each capsule is then provided with a tightly fitting lid having an evacuation opening. After evacuation of each capsule at a pressure of 1 bar and subsequent closing of the evacuation opening, the capsule with its contents is placed in a high-pressure furnace according to Figure 2.When the capsule has been placed in the furnace space and the furnace space has been sealed, the pressure and the temperature in the furnace space are increased to around 1000 bar and about 1300"C, respectively, and are maintained at these values for about two hours, when the desired density and sintering of the formed body is obtained. The capsule with the enclosed material is then allowed to cool, whereafter the pressure is reduced to atmospheric pressure and the capsule is removed from the furnace. Each capsule is allowed to remain as reinforcement of the body.
Example 3
A 0.9 molar nitric acid solution contains in the form of radioactive substances 1.17 g/l of (NH4)6Mo7024 4H2O 3.75 g/l of Nd(NO3)3.6H2O, 0.59 g/l of CsNO3, 1.23 gll of Ce(NO3)3.6H2O,2.80 g/l of Fe (NO3)3.9H2O, 0.57 g/l of UO2(NO3)2.6H2O, and 0.63 g/l of Ni (NO3)2. The pH of the solution is adjusted to 1.3 by the addition of NaOH. It is then conducted through a cylindrical column containing an ion exchanger consisting of Na Ti2O5H in the form of particles having a size of from 0.1 to 1 mm. The ion exchanger is mixed up with the same amount of mixture of TiO2,
SiO2 and Al203 having a grain size of from 0.05 to 0.5 mm.The capacity of the ion exchanger corresponds approximately to 2.5 per cent of adsorbed waste calculated as oxide on dried ion exchanger. The ion exchanger is thereafter heated in air at 600"C and ground into a fine powder. The powder mixture is then packed in a capsule of iron, which is provided with a tightlyfitting lid having an evacuation opening.
After evacuation during 24 hours at a pressure of 1 bar at the pump and under heating to 7500C, the capsule with the pump connected is sealed. After the capsule has been placed in a high-pressure furnace according to Figure 2 and the furnace space has been closed, the pressure is raised to 1500 bar and the temperature to 1300"C, and these conditions are maintained for two hours. The capsule with the enclosed material is then allowed to cool, whereafter the pressure is reduced to atmospheric pressure and the capsule is removed from the furnace. The contents of the casule constitute a dense body without pores and voids and contain different crystalline phases, among other things TiO2, NaTiO3 and Al2TiOs where the radioactive substances are fixed in water-insoluble state.
Example 4
A waste solution from a plant for reprocessing high-level waste from a nuclear reactor consists of a 2-molar nitric acid solution and contains in the form of radioactive substances, among other things, 60.5 g/l of Nd, 5.9 g/l of [Po43-], 10.6 g/l of Cs, 11.5 g/l of Mo, 10.5 g/l of Sr, 10.9 g/l of Zr, 5.1 gIl of Fe and 0.3 g/l of Ni. 7.2 g/l of Ca and 2.2 g/l of Al in the form of nitrates as well as 65 of finely-divided SiO2 (grain size 100 Angström) are added to said solution. The solution is evaporated and calcined in air for one hour at 500"C. Thereafter, 60 parts by weight of calcine are mixed with 40 parts by weight of a-Al203 by grinding in a ball mill.
The mixture is then heated in air for two hours at 9000C, remainders of nitrates and water then being driven off. Thereafter, the mixture is packed in a cylindrical capsule of iron which is provided with a tightly-fitting lid having an evacuation opening. The capsule is evacuated for 24 hours at a pressure of 1 bar at the pump and under heating to 7500C and is thereafter sealed with the pump connected. When the capsule has been placed in a high pressure furnace according to Figure 2 and the furnace space has been sealed, the pressure is raised to 1500 bar and the temperature to 1300"C, and these conditions are maintained for seven hours. The capsule and the enclosed material are then allowed to cool, whereafter the pressure is reduced to atmospheric pressure and the capsule is removed from the furnace.The contents of the capsule constitute a dense body without pores and voids and with a density of 4.82 g/cm3 and it contains different crystalline phases, among other things a phase of corundum type (ale)203, a phase of fluorite type, (Zr Ca
Nd)O2, a phase of pollucite type CsAlSi206, a phase of scheelite type, (Sr Ca)MoO4, and a phase of apatite type (Ca Nd)10(SiO4 PO4AlO4)602, in which the radioactive substances are fixed. A SEM-analysis of elements Cs, Sr and Nd shows that these elements are very evenly distributed in the body obtained during the compression.
Example 5
The waste solution described in Example 4 is treated with formic acid at a temperature of 90"C, whereby the nitrates are decomposed in accordance with the formula 2 NO3- + 4HCOOHo N2O + 4CO2 + 3H2O + 20H-, and whereby metal oxides and metal hydroxides are precipitated. After drying, the precipitated substances are mixed with Al2O3 and are then placed in a capsule and subjected to isostatic pressing in the manner described in the preceding example.
The method according to the invention may, of course, be utilised for the treatment of radioactive material other than high-level waste from the reprocessing of nuclear reactor fuel. It is also possible for example, to use the method for the treatment of high-level waste in connection with fuel reprocessing in the manufacture of plutonium for nuclear weapons.
WHAT WE CLAIM IS:
1. A method of anchoring radioactive waste from nuclear fuel in a body resistant to leaching by water, characterised in that a mass containing radioactive constituents and constituents which are resistant to' leaching by water or which, when heated, form constituents resistant to leaching by water, is subjected to isostatic pressing enclosed in a casing at a pressure and temperature necessary for the formation of a coherent dense body of the mass.
2. A method according to claim 1, in which particles of the radioactive material are mixed with particles of a material resistant to leaching by water to form said mass
3. A method according to claim 2, in which the material resistant to leaching consists of a material containing one or more oxides.
4. A method according to claim 2 and 3, in which the material resistant to leaching consists of aluminium oxide.
5. A method according to claim 2 or 3, in which the material resistant to leaching consists of quartz.
6. A method according to claim 2 or 3, in which the material resistant to leaching consists of titanium dioxide.
7. A method according to claim 2 or 3, in which the material resistant to leaching consists of rock existing in nature.
8. A method according to claim 1, in which said mass is a particle mass containing a material resistant to leaching by water, in which the radioactive material is fixed or a material in which the radioactive material is fixed and which, when heated, forms a material resistant to leaching by water.
9. A method according to claim 8, in which the particle mass contains compounds of radioactive substances which are resistant to leaching by water.
10. A method according to claim 8, in which the particle mass contains a material
obtained by heating an ion exchanger, in
which the radioactive substances are fixed.
11. A method according to claim 10, in
which the ion exchanger consists of a
zeolite.
12. A method according to claim 10, in
which the ion exchanger consists of a
titanate.
13. A method according to any of claims
8 to 12, in which the particle mass contains
material resistant to leaching by water in
addition to that in which radioactive mate
rial is fixed, or that which has been formed
by heating the material, in which radioactive
material is fixed.
14. A method according to claim 13, in
which the further material resistant to
**WARNING** end of DESC field may overlap start of CLMS **.
Claims (20)
1. A method of anchoring radioactive waste from nuclear fuel in a body resistant to leaching by water, characterised in that a mass containing radioactive constituents and constituents which are resistant to' leaching by water or which, when heated, form constituents resistant to leaching by water, is subjected to isostatic pressing enclosed in a casing at a pressure and temperature necessary for the formation of a coherent dense body of the mass.
2. A method according to claim 1, in which particles of the radioactive material are mixed with particles of a material resistant to leaching by water to form said mass
3. A method according to claim 2, in which the material resistant to leaching consists of a material containing one or more oxides.
4. A method according to claim 2 and 3, in which the material resistant to leaching consists of aluminium oxide.
5. A method according to claim 2 or 3, in which the material resistant to leaching consists of quartz.
6. A method according to claim 2 or 3, in which the material resistant to leaching consists of titanium dioxide.
7. A method according to claim 2 or 3, in which the material resistant to leaching consists of rock existing in nature.
8. A method according to claim 1, in which said mass is a particle mass containing a material resistant to leaching by water, in which the radioactive material is fixed or a material in which the radioactive material is fixed and which, when heated, forms a material resistant to leaching by water.
9. A method according to claim 8, in which the particle mass contains compounds of radioactive substances which are resistant to leaching by water.
10. A method according to claim 8, in which the particle mass contains a material
obtained by heating an ion exchanger, in
which the radioactive substances are fixed.
11. A method according to claim 10, in
which the ion exchanger consists of a
zeolite.
12. A method according to claim 10, in
which the ion exchanger consists of a
titanate.
13. A method according to any of claims
8 to 12, in which the particle mass contains
material resistant to leaching by water in
addition to that in which radioactive mate
rial is fixed, or that which has been formed
by heating the material, in which radioactive
material is fixed.
14. A method according to claim 13, in
which the further material resistant to
leaching consists of a material containing one or more oxides.
15. A method according to any one of claims 1 to 14, in which the casing consists of metallic material.
16. A method according to any of claims 1 to 14, in which the casing consists of quartz glass.
17. A method at cording to any of claims 1 to 14, in which the casing consists of boron silicate glass.
18. A method according to any of claims 1 to 17, in which the pressure during the isostatic pressing amount to at least 100 bar.
19. A method according to any of claims 1 to 18, in which the temperature during the isostatic pressing amounts to at least 700"C.
20. A method of anchoring radioactive material in a body resistant to leaching by water, substantially as described in any of the foregoing Examples and with reference to the accompanying drawing.
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| SE7612146A SE404736B (en) | 1976-11-02 | 1976-11-02 | WAY TO INCLUDE HIGH-ACTIVE NUCLEAR FUEL WASTE IN A LOT OF A RESISTANT MATERIAL |
| SE7701278A SE407640B (en) | 1977-02-07 | 1977-02-07 | WAY TO ANCHOR A RADIOACTIVE MATERIAL IN A RESISTANT BODY RESISTANCE TO WATER |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| GB1588350A true GB1588350A (en) | 1981-04-23 |
Family
ID=26656753
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB4537977A Expired GB1588350A (en) | 1976-11-02 | 1977-11-01 | Method of anchoring radioactive waste from nuclear fuel in a body resistant to leaching by water |
Country Status (5)
| Country | Link |
|---|---|
| JP (1) | JPS5357400A (en) |
| BR (1) | BR7707273A (en) |
| DE (1) | DE2747951A1 (en) |
| FR (1) | FR2369659A1 (en) |
| GB (1) | GB1588350A (en) |
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2525381A1 (en) * | 1982-04-17 | 1983-10-21 | Kernforschungsz Karlsruhe | PROCESS FOR IMPROVING THE PROPERTIES NECESSARY FOR LONG-TERM STORAGE OF SOLIDIFIED RADIOACTIVE WASTE |
| WO1983003919A1 (en) * | 1982-04-30 | 1983-11-10 | Jukka Kalevi Lehto | Procedure for ceramizing radioactive wastes |
| GB2139407A (en) * | 1981-02-07 | 1984-11-07 | Wiederaufarbeitung Von Kernbre | Device for closing a storage container for radioactive materials |
| WO2003015106A2 (en) * | 2001-08-03 | 2003-02-20 | British Nuclear Fuels Plc | Encapsulation of waste |
| WO2013184648A1 (en) * | 2012-06-04 | 2013-12-12 | American Isostatic Presses, Inc. | Methods of consolidating radioactive containing materials by hot isostatic pressing |
Families Citing this family (14)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2375695A1 (en) * | 1976-12-21 | 1978-07-21 | Asea Ab | PROCESS FOR THE TREATMENT OF RADIOACTIVE WASTE |
| ZA786514B (en) * | 1978-11-09 | 1980-07-30 | Litovitz T | Immobilization of radwastes in glass containers and products formed thereby |
| DE2945006A1 (en) * | 1979-11-08 | 1981-05-21 | Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe | METHOD FOR PRODUCING HIGH-RADIOACTIVE WASTE MATERIALS CONTAINING |
| DE3175445D1 (en) * | 1980-07-15 | 1986-11-13 | Atomic Energy Of Australia | Arrangements for containing waste material |
| US4851156A (en) * | 1980-09-10 | 1989-07-25 | The United States Of America As Represented By The United States Department Of Energy | Retention of radio-ruthenium in acid processing of nuclear waste |
| DE3110192A1 (en) * | 1981-03-17 | 1982-10-07 | Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe | METHOD FOR COATING RADIOACTIVELY CONTAMINATED OR RADIOACTIVE SOLIDS CONTAINING SOLUTIONS FROM NUCLEAR TECHNICAL PLANTS WITH A REPOSABLE MATRIX |
| IT1211145B (en) * | 1981-12-11 | 1989-09-29 | Agipnucleare S P A Comitato Na | PREPARATION PROCEDURE FOR INORGANIC ION EXCHANGERS ABASE OF TITANIUM COMPOUNDS AND THEIR USES. |
| US4645624A (en) * | 1982-08-30 | 1987-02-24 | Australian Atomic Energy Commission | Containment and densification of particulate material |
| US4591455A (en) * | 1982-11-24 | 1986-05-27 | Pedro B. Macedo | Purification of contaminated liquid |
| SE442562B (en) * | 1983-01-26 | 1986-01-13 | Asea Ab | WANT TO INCLUDE RADIOACTIVE OR OTHER DANGEROUS WASTE AND A RECIPE OF SUCH WASTE |
| JPS59167554U (en) * | 1983-04-22 | 1984-11-09 | 馬場 良雄 | balance training equipment |
| FR2563936B1 (en) * | 1984-05-04 | 1989-04-28 | Sgn Soc Gen Tech Nouvelle | PROCESS FOR COATING AND STORING DANGEROUS MATERIALS, PARTICULARLY RADIOACTIVE, IN A MONOLITHIC CONTAINER, DEVICE FOR IMPLEMENTING THE PROCESS AND PRODUCT OBTAINED |
| JPH0782115B2 (en) * | 1988-11-29 | 1995-09-06 | 動力炉・核燃料開発事業団 | HIP volume reduction method for radioactive waste |
| EP3565675A1 (en) * | 2017-01-06 | 2019-11-13 | Georoc International, Inc. | Integrated ion-exchange disposal and treatment system |
Family Cites Families (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3000072A (en) * | 1959-08-20 | 1961-09-19 | Ca Atomic Energy Ltd | Process of containing and fixing fission products |
| BE622903A (en) * | 1961-10-09 | |||
| NL7300552A (en) * | 1973-01-15 | 1974-07-17 |
-
1977
- 1977-10-26 DE DE19772747951 patent/DE2747951A1/en not_active Withdrawn
- 1977-10-26 FR FR7732219A patent/FR2369659A1/en active Granted
- 1977-10-31 BR BR7707273A patent/BR7707273A/en unknown
- 1977-11-01 JP JP13038877A patent/JPS5357400A/en active Pending
- 1977-11-01 GB GB4537977A patent/GB1588350A/en not_active Expired
Cited By (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB2139407A (en) * | 1981-02-07 | 1984-11-07 | Wiederaufarbeitung Von Kernbre | Device for closing a storage container for radioactive materials |
| US4638134A (en) * | 1981-02-07 | 1987-01-20 | Deutsche Gesellschaft | Device for evacuating, filling and closing final storage containers for radioactive materials |
| FR2525381A1 (en) * | 1982-04-17 | 1983-10-21 | Kernforschungsz Karlsruhe | PROCESS FOR IMPROVING THE PROPERTIES NECESSARY FOR LONG-TERM STORAGE OF SOLIDIFIED RADIOACTIVE WASTE |
| GB2121232A (en) * | 1982-04-17 | 1983-12-14 | Kernforschungsz Karlsruhe | Method for solidifying radioactive wastes |
| WO1983003919A1 (en) * | 1982-04-30 | 1983-11-10 | Jukka Kalevi Lehto | Procedure for ceramizing radioactive wastes |
| US4632778A (en) * | 1982-04-30 | 1986-12-30 | Imatran Voima Oy | Procedure for ceramizing radioactive wastes |
| WO2003015106A2 (en) * | 2001-08-03 | 2003-02-20 | British Nuclear Fuels Plc | Encapsulation of waste |
| WO2003015106A3 (en) * | 2001-08-03 | 2003-09-04 | British Nuclear Fuels Plc | Encapsulation of waste |
| US7241932B2 (en) | 2001-08-03 | 2007-07-10 | British Nuclear Fuels Plc | Encapsulation of radioactive waste using a sodium silicate based glass matrix |
| WO2013184648A1 (en) * | 2012-06-04 | 2013-12-12 | American Isostatic Presses, Inc. | Methods of consolidating radioactive containing materials by hot isostatic pressing |
Also Published As
| Publication number | Publication date |
|---|---|
| DE2747951A1 (en) | 1978-05-11 |
| FR2369659B1 (en) | 1984-05-11 |
| BR7707273A (en) | 1978-08-01 |
| JPS5357400A (en) | 1978-05-24 |
| FR2369659A1 (en) | 1978-05-26 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PS | Patent sealed | ||
| PCNP | Patent ceased through non-payment of renewal fee |