Other

Pedro B Macedo

Theodore Aaron Litovitz

Joseph H Simmons

Robert K Mohr

Catherine J Simmons

Nicholas Lagakos

Aaron Barkatt

Danh C Tran

Mrinmay Samanta

Herbert G Sutter

Hamid Hojaji

Robert J Meister

Prabhat K Gupta

Marek Brandys

Deepak Varshneya

Ian L Pegg

Shigeo Murai

Hamid Hojaj

In this invention radioactive or hazardous containing materials are vitrified in a melter having two or more chambers. Glass feed materials are added to the primary chamber of the melter and they are heated to a molten glass which is then transported to one or more secondary chambers where hazardous and/or radioactive containing materials are added and are encapsulated and/or melted. In addition, the non-plutonium part of a glass feed can be melted in a non-radioactive environment which permits contact operations and maintenance; no radioactive shielding; and a conventional off gas system-similar to commercial vitrification plants. The hot molten 'clean' glass is directed into a radioactive containment such as a 'glove box'; shielded 'glove box'; or hot cell, or a combination of these. By delivering hot 'clean' glass from a melter including non-radioactive materials, 90% of the off gases will be non-radioactive. Thereby only minimum heating is needed in the radioactive containment resulting in very significant reductions in size of the maintenance requirements for the radioactive portion of the process. In the radioactive portion, the glove box will include means for adding plutonium feed. The glass melt will be homogenized with the plutonium feed, optionally by additional stirring. Once the plutonium glass is sufficiently homogeneous, it can be cooled in the container in the glove box or the container becomes a disposal container for the glass. If the melt chamber is different than the container, the melt is discharged to a separate container, all within the glove box, for subsequent disposal.

Method and apparatus for eliminating volatiles or airborne entrainments

An off-gas quencher and solid recovery scrubber unit includes a wet flue gas scrubber which has the dual responsibilities of lowering the temperature of the inlet hot gas entering through the scrubber and trapping contaminants from the gas stream into the liquid stream. The hot exhaust gases are first cooled by evaporating the liquid scrubber solution. The contaminants of the exhaust gas are neutralized by a suitable reagent such as sodium hydroxide and the product is collected in the scrubbing solution. Since the solution is continuously recycled, the concentration of the scrubbing agent will be diminished as the scrubbing proceeds, while the concentration of the scrubbing product in the solution will rise to the solubility limit of the product. The scrubbing products start to precipitate and are collected at the bottom of the scrubber and are withdrawn. The scrubbing reagents are continuously replenished to the scrubber. The secondary scrubber is another wet scrubber which uses reagents/water from spray nozzles to scrub off any contaminants that might have escaped the solid recovery scrubber. In addition, the exhaust gas entering the secondary scrubber is cooled below its dew point which results in condensation of water in the scrubber.

Off-gas scrubber system

Material, such as, for example, sealed double bags of asbestos containing waste or ash from infectious waste or toxic material or radioactive waste, is transferred into a glass melt of a furnace. Gas bubbles released into the melt form a gas curtain which causes enhanced mixing of the material to accelerate the dissolution of the components of the added material. The presence of the gas bubbles reduces the cross-section of the molten glass through which current passes, which in turn increases the electrical resistance of the glass melt and therefore increases power generation of the melt or power density at constant current. A highly oxidizing hot region is produced under the location where the material is introduced into the furnace. Drawn off glass is shaped and quenched into at least two sizes of approximate spheres. The spheres are cooled sufficiently fast to be thermally tempered and have a surface compressive strength level above 5000 psi.

Process for vitrifying asbestos containing waste, infectious waste,

The present invention comprises a process for separating rare earth ions or actinide ions or mixtures thereof in solution by passing the solution through an ion exchange material to separate the rare earths or actinides or mixtures thereof. The ion exchange material has a surface area of about 5-1500 m.sup.2 /g. The ion exchange material is impregnated with a liquid containing alkali metal cations, Group Ib metal cations, ammonium cations, organic amines or mixtures thereof, at a pH range above about 9. A plurality of fractions of the solution is collected as the solution passes through the ion exchange material, preferably in a column. This process is particularly preferred for separating rare earth ions and especially lanthanum and neodymium. It is particularly preferred to purify lanthanum to contain less than 0.1 ppm, preferably less than 0.01 ppm, of neodymium. In another embodiment, the present invention comprises a method of producing a porous silicate glass containing at least one transition metal oxide additive selected from a group consisting of the bottom two rows of Group VIII of the Periodic Table. This method comprises preparing a base glass from a melt which contains 40-80 mol percent of silica and up to 10 mol percent of one or more transition metal oxide additives selected from said group or of precursors of said oxide additives, separating said base glass by heat treatment into at least a soluble phase and an insoluble phase, leaching out the soluble phase. In yet another embodiment, the present invention comprises an ion exchange material consisting of a porous glass or silica gel including at least about 0.2 mol percent of a transition metal oxide or hydrous metal oxide and containing at least 0.3 mol percent of alkali metal cation, Group Ib metal cation, ammonium, organic amines, or mixtures thereof.

Ion exchange compositions

A liquid containing radioactive ions is purified (decontaminated) by contacting the same with an inorganic ion exchange composition having ion exchange sites which can be occupied by the radioactive ions from the liquid. The ion exchange composition is a mixture of an ion exchange medium and an additive which is relatively inert to the ion exchange process and which is a sintering aid for the ion exchange medium designed to lower the sintering temperature of the ion exchange composition. The ion exchange composition may be disposed within a suitable container (e.g., cannister), e.g., made of 304L stainless steel or Inconel 601 and the ion exchange process may be carried out in such container. Alternatively, the ion exchange medium can be employed without being previously admixed with the additive. The additive, if desired, can be admixed at a later stage with the contaminated medium. Thereafter, the mixture may be sintered and disposed of in any desirable manner as by underground burial of the spent mixture within the container. Also, the container may be placed within a suitably designed furnace for carrying out the ion exchange process, sintering of the ion exchange composition and its safe disposal. Methods are also described for making a homogeneous mixture of the ion exchange medium and the additive which, for example, have a certain defined density and particle size relationship.

Purification of contaminated liquid

A method for separating and purifying cations by ion exchange with regenerable porous glass. More specifically, the method is for decontaminating toxic waste streams such as a radioactive waste streams and concentrating the radioactive cations contained therein which comprises passage of the waste stream through an ion exchange medium of porous silicate glass or silica gel. In one embodiment, a liquid nuclear waste stream is passed through an ion exchange column containing porous silicate glass or silica gel having a plurality of .tbd.Si--O--Z groups wherein Z represents a non-radioactive cation (hydrogen, alkali metals, Group Ib metals and ammonium cations, and mixtures thereof) to displace the non-radioactive cations of the silicate glass or silica gel by the radioactive cations of the waste stream. Thereafter, the ion exchange medium is contacted with an aqueous solution of an acid to strip the radioactive cations therefrom and the stripped ion exchange medium is regenerated. The stripped ion exchange medium can be regenerated by contacting it with an aqueous basic solution of an alkali metal or ammonium ion. Additional liquid radioactive waste is contacted with the regenerated ion exchange medium to decontaminate an additional volume of liquid waste.

Method of separating and purifying cations by ion exchange with

A composition comprising a support such as a porous silicate glass or silica gel or charcoal having interconnected pores and containing heavy metal cations of mercury, thallium, silver, platinum, palladium, lead or copper capable of forming a stable complex with an anion bonded to the support. The preferred heavy metal cation is a mercury cation. The composition is especially useful for removing radioactive iodine from liquid and gaseous waste streams.

Fixation of anionic materials with a complexing agent

A process for removing metal species from solution comprising passing the liquid over a composition comprising a support such as a porous silicate glass or silica gel or charcoal having interconnected pores and containing water soluble amine complexing agents absorbed on the support capable of forming a stable complex with the metal species. The preferred amine complexing agent is triethylenetetramine. The process is especially useful for removing radioactive cobalt from liquid waste streams.

Fixation of dissolved metal species with a complexing agent

A process for removing heavy alkali metal cations from solution comprising passing a liquid over a composition including a support such as charcoal having interconnected pores containing a tetra-aryl boron moiety associated with an ion exchangeable cation absorbed on the support capable of forming a stable compound with a heavy alkali metal cation.

Ion exchanger to separate heavy alkali metal ions

Silica-based chromatographic and reactive materials are disclosed with surfaces modified to contain or to be coated with oxides, hydrous oxides, hydroxides, carbonates or silicates of aluminum, iron, or other suitable metals such as zirconium or titanium. The materials exhibit good resistance to dissolution and resulting loss of activity or clogging. This good resistance is particularly evident even in the high pH region (above 8-9) and in the high temperature region (above 35.degree. C.) where the dissolution rates and solubilities of aluminosilicates and of trivalent iron oxides are much smaller than those of silica.

Process of using improved silica-based chromatographic supports

The present invention is directed to a method and apparatus for forming shaped foamed-glass articles. Glass particles are introduced to a pressure vessel in the presence of water. A pressure is applied to the pressure vessel sufficient to permit entrapment of water during sintering and sufficient to prevent foaming at processing temperatures. The temperature of the glass is increased to cause the glass to sinter and entrap water. The temperature of the glass is then increased to its fining temperature (T.sub.F) for a sufficient time to fine the glass. The temperature of the glass is reduced to its pressure release temperature (T.sub.PR). The pressure on the glass containing water is then reduced such as by extrusion to cause controlled foaming of the glass to occur. The glass is then cooled preferably by annealing to form the shaped foamed-glass article, typically pipe insulation.

Method of producing shaped foamed-glass articles

This invention relates to the immobilization of toxic, e.g., radioactive materials, internally in a silicate glass or silica gel matrix for extremely long periods of time. Toxic materials, such as radioactive wastes containing radioactive anions, and in some cases cations, which may be in the form of liquids, or solids dissolved or dispersed in liquids or gases, are internally incorporated into a glass matrix, having hydrous organofunctionalsiloxy groups, e.g., hydrous aminoalkylsiloxy or carboxyorganosiloxy, bonded to silicon atoms of said glass and/or hydrous polyvalent metals bonded to silicon atoms of said glass through divalent oxygen linkages or otherwise immobilized therein, by a process which involves the ion exchange of said toxic, radioactive anions with hydroxyl groups attached to said organofunctionalsiloxy groups or with hydroxyl groups attached to the hydrous polyvalent metal. Thereafter, the resulting glass now characterized by a distribution of internally bonded or immobilized, toxic, radioactive anions can be packaged in suitable containers, and disposed of as by burial, and/or they can be sintered to collapse the pores thereof to disposal or for producing useful radiation sources. The porous glass or a porous silica gel having said silicon-bonded organofunctionalsiloxy groups and/or said hydrous polyvalent metal oxy groups, the pores of said glass or silica gel remaining open and uncollapsed, can be used advantageously as a backfill for an underground radioactive waste burial site and as overpack in the waste disposal container. Also included is a novel method for bonding the polyvalent metal to the porous silica glass or gel by substituting the protons of the silicon-bonded hydroxyl groups thereof with an alkali metal or ammonium cation followed by displacement of said cation with the non-radioactive polyvalent metal cation.

Fixation by anion exchange of toxic materials in a glass matrix

This invention relates to the immobilization of toxic materials, e.g., radioactive materials, in glass for extremely long periods of time. Toxic materials, such as radioactive wastes, which may be in the form of liquids, or solids dissolved or dispersed in liquids or gases, are deposited in a glass container which is heated to evaporate off non-radioactive volatile materials, if present; to decompose salts, such as nitrates, if any, and to drive off volatile non-radioactive decomposition products, and then to collapse the walls of said container on said radwaste and seal the container and immobilize the contained radwaste, and then burying the resulting product underground or at sea. In another embodiment, the glass container also contains glass particles, e.g., spheres or granules, on which the radwaste solids are deposited. In other embodiments, the glass container can be made of porous glass or non-porous glass, and/or the contained glass particles can be made of porous or non-porous glass or mixtures of porous or non-porous glass, and/or the glass container can be open at one end and closed at the other or open at both ends, and/or the glass container can be closed at one end with a porous or non-porous closure and open at the other end or closed at the other end with a porous closure. When a porous glass container and/or porous glass particles are used, the radwaste deposits within the pores of the glass which are closed during the subsequent heating step after non-radioactive volatiles have been driven off and prior to sealing the container. There results a substantially impervious glass article in which the radwaste is entrapped and which is highly resistant to leaching action. The products resulting from the use of porous glass, as the container, contents, or both, can be used as sources of radioactivity for a variety of applications in medicine, sterilization, food preservation and any other application where radiation can be beneficially employed.

Growing community of inventors

Bethesda, MD, United States of America

Pedro B Macedo