Patent Application
20090012343
The present invention relates to the treatment and storage of waste materials by encapsulation. More specifically, it is concerned with the encapsulation of nuclear waste materials and the use of said waste materials in the production of stable monolithic materials.
Encapsulation has proved to be an especially favoured method for the disposal of certain hazardous materials; specifically it provides a suitable means for the conversion of these materials into a stable and safe form, which allows for long-term storage and/or ultimate disposal. The technique finds particular application in the nuclear industry, where the highly toxic and radioactive nature of the materials involved, and the extended timescales over which the toxicity is maintained, are the principal considerations when devising safe disposal methods.
In WO-A-03/056571, the present applicant has disclosed the use of cementitious grouting materials for the encapsulation of fine particulate sized wastes and provided details of a method for the encapsulation of fine particulate materials which comprises treating these materials with at least one microfine hydraulic inorganic filler.
The use of cement based injection grouting in the construction industry is well known from the prior art. Thus, EP-A-412913 teaches the use of a Portland Cement based grout in the consolidation of concrete structures affected by fine cracks, providing a cost-effective means of infilling both superficial and deeper fissures and cavities in such structures, including such as buildings, bridges and dams. Similarly, ZA-A-9209810 is concerned with a pumpable, spreadable grouting composition incorporating a cementitious and/or pozzolanic or equivalent material, and its application in sealing fissures and cracks, back-filling, providing mass fills in civil and mining works, or lining tunnels.
Also disclosed in the prior art are hydraulic setting compositions comprising particles of Portland Cement together with fine particles of silica fume containing amorphous silica, which are the subject of EP-A-534385 and are used in the production of concrete, mortar or grout having improved fluidity, whilst GB-A-2187727 describes a rapid gelling, hydraulic cement composition which comprises an acrylic gelling agent, a fine filler and Portland Cement, this composition being thixotropic and finding particular application in the formation of bulk infills for underground mining, and in the filling of voids and cavities in construction or civil engineering. A composition which also is useful in general building and construction work, and as an insulating material comprises a particulate filler, cellulose fibres and a cementitious binder, and is disclosed in GB-A-2117753.
Whilst the majority of these compositions of the prior art have a requirement for the addition of water, EP-A-801124 is concerned with a dry mixture, used for fine soil injection grout preparation, the mixture comprising fillers which do not react with water, cement and deflocculant; on addition of water, an agglomerate-free fine grout is formed, and this is easily injected into fine soil.
Thus, the use of such grouting materials in—primarily—civil engineering is well known, and its use in treating fine particulate sized wastes in the nuclear industry is the subject of WO-A-03/056571. Subsequently, in WO-A-04/06268, it is disclosed that cured cementitious materials may advantageously be employed for the long term encapsulation of uranium and Magnox fuel elements, as well as fuel element debris and other nuclear fuels, thereby providing a product which remains stable and monolithic for many hundreds of years. Hence, there is provided a treatment method which affords much greater efficiency, convenience and safety in handling, and has a consequent beneficial effect both in terms of environmental considerations and cost, thereby satisfying a long felt need in the nuclear industry wherein the waste management of materials is receiving ever greater attention in the global drive to ensure ever higher safety standards.
However, whilst the method of WO-A-04/06268 is generally satisfactory for dealing with materials of the type described, difficulties are often encountered when uranium metal is encapsulated in cementitious materials due to corrosion of the metal, which occurs at a very rapid rate in standard cementitious materials. This, in British Patent Application No. 0408113.9, there is disclosed a method for the encapsulation of uranium metal which comprises treating the metal with an encapsulant which comprises a cementitious material and curing the cementitious material, the process additionally comprising the provision of means for the minimisation of the corrosion of the metal. Typically the provision of means for the minimisation of corrosion comprises the provision of a source of oxygen within the cement matrix, or the minimisation of the water content of the matrix.
U.S. Pat. No. 4,859,367 discloses a method for the disposal of mine tailings, which frequently comprise significant quantities of salt residues, the method comprising adding the waste material to an alkali activated aluminosilicate mineral binder, such that the resulting mixture is bound together with a geopolymeric matrix and, on setting, forms a hard, monolithic solid.
All the methods of the prior art, however, rely on the provision of a cementitious material which is used in the production of a monolith in which the waste material is encapsulated. Thus, the waste material is physically constrained within the matrix provided by the cementitious material and, whilst the monoliths produced generally show excellent stability, the extent to which the waste material is securely bound within the matrix is constrained by the degree of physical restraint which is provided by the cementitious matrix.
Clearly, the stability of a monolith, and its ability to retain waste materials over a long period of time, and to prevent their leakage into the environment, could be enhanced in the event that the forces which caused the retention of these materials were to be chemical, rather than purely physical, forces. Thus, the present invention seeks to provided a means for the encapsulation of waste materials wherein the waste materials are more securely held within monoliths by virtue of chemical bonds which ensure that the waste materials are integral with, and form part of, the monoliths.
Thus, according to a first aspect of the present invention, there is provided a method for the production of a stable monolith, said method comprising the encapsulation of waste materials in said monolith by means of chemical bond formation within the monolith.
The method of the invention thereby provided a monolith wherein the waste material is integral with the encapsulation medium of the monolith, thus ensuring that the waste material is firmly bound within the material of the monolith and the chances of escape of the waste material occurring over time are significantly less than in cases wherein this material is retained within the monolith only by means of physical forces. Preferably, the monolith which is formed comprises a geopolymer monolith.
Thus, a second aspect of the invention provides a method for the disposal and storage of waste materials, said method comprising the production of a stable monolith in accordance with the first aspect of the invention.
Waste materials which are particularly suited to treatment in this way include those materials which may be used in the formation of cementitious monoliths. In this context, particular mention may be made of various geopolymer precursors, most particularly ion exchange materials, more specifically aluminosilicate materials. An especially preferred example of such a material is clinoptilolite.
The use of ion exchange materials for the treatment of radioactive materials has previously been reported in the literature. Thus, for example, EP-B-456382 discloses a method for the removal of radioisotope cations from an aqueous environment which includes the step of contacting the aqueous environment containing the radioisotope cations with an ion exchange material comprising a modified clinoptilolite. The present invention is now able to provide a means for the safe storage and disposal of the clinoptilolite following the contacting step with the aqueous environment containing radioisotope cations.
Thus, a preferred application of the method of the second aspect of the invention is in the treatment of radioactive waste materials. Specifically, there is envisaged a method for the encapsulation of radioactive waste materials, said method comprising the production of a stable monolith by means of chemical bond formation within the monolith.
Preferably said radioactive waste material is comprised in an ion exchange material. More preferably, said ion exchange material comprises an aluminosilicate material. Most preferably, said ion exchange material comprises clinoptilolite.
Typically, the radioactive waste material is originally comprised in a liquid medium and is removed from said liquid medium by treatment of said liquid medium with said ion exchange material. Generally said liquid medium comprises an aqueous environment. Thus a particularly preferred embodiment of the present invention envisages a method for the removal of radioactive waste materials from a liquid medium, said method comprising performing, in order, the steps of:
The present invention thereby provides improved methods for the disposal and long term storage of radioactive waste materials.
In the most preferred embodiment of the present invention, the waste material encapsulated in a monolith comprises a geopolymer precursor, particularly an ion exchange material, most preferably an aluminosilicate ion exchange material. In such cases, a monolithic cementitious binder material is most conveniently produced by treatment of the geopolymer precursor with a suitable curing initiator which, in the case of an ion exchange material precursor, typically comprises a silicate, preferably an alkali metal silicate such as sodium silicate. Preferably, in such situations, the ion exchange material is treated with an alkaline solution of said silicate. Most preferably, the ion exchange material is contacted with an aqueous solution of sodium silicate and sodium hydroxide. The use of a curing initiator in the method envisaged by the first aspect of the present invention promotes chemical bond formation within the monolith, thereby increasing the efficiency of the encapsulation process.
Following treatment of the ion exchange material with a silicate, the resulting mixture is allowed to cure to form a monolithic product. Typically, curing is allowed to proceed for 12-48 hours, with satisfactory results generally being obtained within 24 hours. Although not necessary to obtain satisfactory curing, it is preferred that the mixture is heated during the curing process, as this provides a faster rate of curing. Although temperatures anywhere between the ambient and several hundred degrees Celsius (e.g. 800° C.) are suitable for this purpose, temperatures of up to 100° C. are typically employed, with optimum results being achieved at temperatures in the region of 80° C.
The processes of the invention, when applied to the treatment of aluminosilicate ion exchange materials, result in the formation of three-dimensional amorphous aluminosilicate geopolymer networks, thereby providing monolithic products with excellent long term stability and high waste loading.
The processes of the invention find potential application to a wide range of waste treatment requirements. Most particularly, spent ion exchange beds may be treated by injection of an inorganic silicate solution in order to provide a stable monolithic product. The method of treatment thereby obviates the requirement for breaking open the cartridge or other container in which the ion exchange bed is located prior to the encapsulation treatment. The resulting product is inorganic and, therefore, more environmentally acceptable than most organic polymeric residues. Furthermore, the method of treatment overcomes the difficulties which are associated with the treatment of fine particulate wastes—such as many ion exchange materials—using cement grouts, which often segregate in such circumstances.
With specific reference to the treatment of drummed ion exchange materials, and particularly clinoptilolite, the method of the prior art requires that the material should be mixed with a mixture of Ordinary Portland Cement (OPC) and Blast Furnace Slag (BFS). However, as a consequence of the vortex which forms during mixing, and the volume of added grout, the waste bed volume in a drum is typically limited to about 70% of its capacity; thus, for example, a 500 litre drum is generally filled only to about 350 litres. By application of the methods of the present invention, however, an alkaline solution of a silicate salt may be pressure injected into the drum, thereby allowing the drum to be filled to close to its capacity, with the consequence that monoliths of much higher waste loading may be obtained by the application of the methods of the present invention.
The present invention also envisages the incorporation of geopolymer precursors, such as ion exchange materials, in a wide range of waste materials, and treatment of the resulting mixtures with solutions of curing initiators, such as silicates, in order to produce geopolymer monoliths of high stability and integrity.
The invention will now be illustrated, without limitation of its scope, by reference to the following specific examples:
A geopolymer monolith was obtained by treatment of an ion exchange material comprising clinoptilolite (50 g) with an aqueous solution containing sodium silicate (composition 8.9% sodium oxide, 27.3% silica and 63.8% water; 30 g), sodium hydroxide (7 g) and distilled water (10 ml). After addition of the solution to the material, the resulting mixture was allowed to cure for 19 hours at 80° C. to provide a hard, solid product of high integrity and stability.
A geopolymer monolith was obtained by treatment of an ion exchange material comprising clinoptilolite (50 g) with an aqueous solution containing sodium silicate (composition 8.9% sodium oxide, 27.3% silica and 63.8% water; 30 g), sodium hydroxide (10 g) and distilled water (10 ml). After addition of the solution to the material, the resulting mixture was allowed to cure for 19 hours at 80° C. to again provide a hard, solid product of high integrity and stability.
| Number | Date | Country | Kind |
|---|---|---|---|
| 0505330.1 | Mar 2005 | GB | national |
| Filing Document | Filing Date | Country | Kind | 371c Date |
|---|---|---|---|---|
| PCT/GB2006/000867 | 3/16/2006 | WO | 00 | 5/7/2008 |
