摘要:
When making moisture content adjustment by adding liquid such as water to a raw material such as pulverulent material including bentonite, uniform mixing of the liquid such as water with the raw material is given with relatively simple facilities, moisture content adjustment of a large quantity of raw materials is attainable, and besides, a material having satisfactory performances such as impermeability is obtainable through uniform moisture content adjustment. Within a mixing tank (1) configured with a normal powder mixer kept at low temperatures, pulverulent bentonite (A) and fine granular ice (B) are stirred and mixed. Stirring and mixing of the fellow pulverulent materials are adapted to uniformly mix the pulverulent bentonite (A) and the fine granular ice (B), enabling uniformly moisture content-adjusted bentonite to be obtained. A liquid-nitrogen gas bomb (21), for instance, is connected to the mixing tank (1), causing the inside of the mixing tank to be kept at low temperatures with nitrogen gas supplied from the bomb, before putting the prepared fine granular ice (B) through an inlet port (20).
摘要:
A ceramic waste immobilizing material for the encapsulation of high level radioactive waste (HLW), e.g. resulting from the reprocessing of irradiated nuclear fuel. The ceramic waste immobilising material enables waste ions from at least fission products in irradiated nuclear fuel to be dissolved in substantially solid solution form. The ceramic waste immobilising medium has a matrix comprising phases of hollandite, perovskite and zirconolite in which the waste ions are dissolved. The invention also includes a method of immobilizing HLW from reprocessed nuclear fuel assemblies comprising the steps of mixing a liquor containing the HLW with a precursor material comprising oxides or oxide precursors of at least titanium, calcium and barium to form a slurry, drying the slurry, and calcining the dried slurry under a reducing atmosphere to form a powder comprising 30–65 weight % waste.
摘要:
The present invention utilizes one or more processes to immobilize a waste that contains one or more of radionuclides, hazardous elements, hazardous compounds, and/or other compounds present in the waste. Each of the processes create a barrier against leaching and diffusion of the wastes. The first barrier is created by integrating the waste with an immobilizing mineral. The second barrier is a layer of non-radioactive or non-hazardous material that covers the first barrier. The second barrier may be created using an overgrowth procedure or by sintering. The third barrier is created by a rock or glass matrix that surrounds the first and/or second barriers. The fourth barrier is created by ensuring that the rock or glass has the same or similar composition as the indigenous rock at the disposal site. The resultant rock or glass matrix is in equilibrium with the groundwater or local hydrothermal solutions that are saturated with components of the indigenous rock of the disposal area.
摘要:
A phosphosilicate apatite useful as a confinement matrix for radioactive waste, and having the formula: MtCaxLnyHfwPuz−w(PO4)6−u(SiO4)uF2 (I) wherein: M represents an alkaline metal, Ln represents at least one cation selected from lanthanides, and t, x, y, z, w and u are such that: 0≦t≦1, 8≦x≦10, 0≦y≦1, 0
摘要翻译:可用作放射性废物的约束基质的磷硅酸盐磷灰石,并具有下式:其中:M表示碱金属,Ln表示选自镧系元素,和,x,y,z,w和u中的至少一种阳离子,使得: 0 <= t <= 1,8 <= x <= 10,0 <= y <= 1,0
摘要:
This invention relates to a method for conditioning a waste constituted of an aqueous solution of sodium hydroxide NaOH of 3 to 10 M, possibly radioactive. The method is as follows: a) a metakaolin powder is added to the aqueous solution such that a suspension is obtained capable of solidifying and forming a crystalline phase of the zeolite A type; b) the suspension is introduced into a mould; c) the suspension is left to solidify in the mould in order to obtain a moulded solid product based on zeolite A; d) the moulded product is dried; and e) the zeolite A phase is converted into a nepheline type phase by heat treatment at a temperature of 1000null C. to 1500null C.
摘要:
The present invention utilizes one or more processes to immobilize a waste that contains one or more of radionuclides, hazardous elements, hazardous compounds, and/or other compounds present in the waste. Each of the processes create a barrier against leaching and diffusion of the wastes. The first barrier is created by integrating the waste with an immobilizing mineral. The second barrier is a layer of non-radioactive or non-hazardous material that covers the first barrier. The second barrier may be created using an overgrowth procedure or by sintering. The third barrier is created by a rock or glass matrix that surrounds the first and/or second barriers. The fourth barrier is created by ensuring that the rock or glass has the same or similar composition as the indigenous rock at the disposal site. The resultant rock or glass matrix is in equilibrium with the groundwater or local hydrothermal solutions that are saturated with components of the indigenous rock of the disposal area.
摘要:
The invention relates to novel thorium phosphates, their preparation process and their use for the storage of radioactive products.These novel thorium phosphates comply with the formulas Th.sub.4 P.sub.6 O.sub.23 (I) or Th.sub.4-x M.sub.4x/v P.sub.6 O.sub.23 (III) in which:M is a monovalent, divalent, trivalent or tetravalent cation,v represents the valency state of the cation and is equal to 1, 2, 3 or 4, andx is such that:0
摘要:
An improved method of disposing of radioactive or hazardous liquid aqueous waste compositions having a substantial amount of dissolved solids comprises mixing the liquid under a high mechanical shear with a clay selected from the group consisting of attapulgite, sepiolite, and mixtures thereof. Water soluble or miscible organic liquids as well as liquid hydrocarbon mixtures thereof may also be solidified by utilizing the aforesaid clays together with an organic ammonium montmorillonite having at least 10 carbon atoms, the amount of montmorillonite used being proportional to the amount of liquid hydrocarbon present.
摘要:
An improved method of disposing of radioactive or hazardous liquids comprises placing the liquids in a container and adding a sodium montmorillonite over intervals until the composition is substantially solid in the container.
摘要:
The invention relates to a process for the preparation of a borosilicate glass containing nuclear waste.In this process, an inactive borosilicate matrix is prepared in an aqueous medium by mixing the following:a silica-based gel precursor,a concentrated aqueous solution of a boron compound, anda concentrated aqeuous solution of the vitrification adjuvant,in proportions corresponding to the composition of the final glass minus the waste, with stirring at a high rate of shear, at a temperature of between 20.degree. C. and 80.degree. C., preferably at 65.degree.-70.degree. C., at an acid pH, preferably a pH of between 2.5 and 3.5, so as to form a gelled solution, and the said matrix is heat-treated and the nuclear waste is added at any stage during the said treatment to form, by melting, the final borosilicate glass containing the said waste.The process according to the invention is applied to the treatment of nuclear waste, especially to solutions of fission products.