Abstract: Plasma reactors and methods are provided for reducing the volume of radioactive nuclear wastes or toxic wastes where the surface contamination is the main source of radioactivity or toxicity. The radioactive or toxic wastes are prepared in the form of small particles and fed into a pulsed plasma reactor operating in fluidized bed configuration. The repetitively pulsed radio-frequency (rf) powered plasma reactor generates high power plasma for pulse duration between 10 ?s-10 ms. During the pulse, the plasma deliver a short burst of intense heat flux to the surface of waste feed particles. Due to the short pulse duration, the heat flux is concentrated on the surface without propagating much to the core of the particles. The localized heat flux preferentially removes the surface contaminants via vaporization. The removed waste in the vapor phase will be transferred out of the reactor where it may undergo additional treatments or disposed accordingly in a reduced volume.

Abstract: The present invention provides a spent nuclear fuel assembly storage including a metal cask which stores a spent nuclear fuel assembly and a container body which stores the metal cask and has a substantially hexagonal tubular shape, and an assembly of the spent nuclear fuel assembly storage containers, and a method of assembling the spent nuclear fuel assembly storage container.

Abstract: Embodiments of this disclosure relate to tissue digestion and, more particularly, to methods and apparatuses for varying the number, size, and/or location of one or more tissue compartments within a digestive fluid vessel. Some examples include partitions that may be selectively positioned within a vessel (and may be selectively removable from the vessel) to create one or more tissue compartments. The partitions may be positioned, repositioned and rearranged within the vessel to form one or more tissue compartments. The partitions may be solid or include apertures, and may be oriented in horizontally and/or vertically. Alternate embodiments include one or more selectively closeable apertures that permit digestive fluid to circulate along alternate pathways, which can permit tissue digestion with reduced digestive fluid levels. Still further embodiments include baskets that are selectively positionable within the tissue digester.

Abstract: A circulation pipe of a chemical decontamination apparatus including a malonic acid injection apparatus and an oxalic acid injection apparatus is connected to a purification system pipe, which is made of carbon steel, of a boiling water nuclear power plant. A malonic acid aqueous solution is injected from the malonic acid injection apparatus into the circulation pipe. An oxalic acid aqueous solution is injected from the oxalic acid injection apparatus into the circulation pipe. A reduction decontaminating solution including a malonic acid of 5200 ppm and an oxalic acid within a range of 50 to 400 ppm is supplied into the purification system pipe through the circulation pipe. Reduction decontamination for an inner surface of the purification system pipe is executed. After the reduction decontamination for the purification system pipe finishes, the malonic acid and oxalic acid included in the solution are decomposed and furthermore, the solution is purified.

Abstract: The invention relates to a hardenable dental composition comprising component (A) comprising a cationically hardenable compound, component (B) comprising an initiator being able to initiate the hardening reaction of the cationically hardenable compound, and component (C) comprising a filler, wherein the filler comprises a filler body and a filler surface, the filler surface comprising side groups with polar moieties. The invention also relates to a process of producing the dental composition, to the use of the dental composition as dental impression material and to a method of taking an impression of dental tissue.

Abstract: The present invention provides an oxidative decontamination reagent for removal of the dense radioactive oxide layer on a metal surface, which comprises an oxidizing agent, a metal ion, and an inorganic acid. The oxidative decontamination reagent of the present invention is characteristically prepared by adding a metal ion to the conventional oxidative decontamination reagent containing an oxidizing agent and an inorganic acid. When the oxidative decontamination reagent of the present invention is used, electric potential of the metal parts of the primary system of the nuclear power plant can be regulated as passive potential owing to the added metal ion during the oxidative decontamination of the primary metal part of the nuclear power plant. Therefore, by maintaining electric potential of the metal part as passive potential, local corrosion can be inhibited and at the same time secondary waste can be significantly reduced.

Abstract: A system for storing high level radioactive waste. In one embodiment, the invention can be a system comprising an overpack body extending along a vertical axis and having a cavity for storing high level radioactive waste, the cavity having an open top end and a floor; an overpack lid positioned atop the overpack body to enclose the open top end of the cavity; an air inlet vent for introducing cool air into the cavity, the air inlet vent comprising an annular air inlet plenum and an annular air inlet passageway, the annular air inlet plenum extending radially inward from an outer surface of the overpack body to the annular air inlet passageway, the annular air inlet passageway extending upward from the annular air inlet plenum to an opening in the floor, and an air outlet vent in the overpack lid for removing warmed air from the cavity.

Abstract: A system and method for processing of carbon-based radioactive waste, comprise at least: a) soaking in an acid solution, and b) a heat treatment, of a thermal shock type, said acid solution recovering radioactive material resulting from said waste at least after the implementation of step b).

Abstract: By fibrillated cellulose fibrillated in fiber form and humidified as a water permeable polymeric substance of botanical origin and a radioactive-substance-absorbent obtained by mixing with zeolite as a granulated inorganic porous crystal, radioactive substances released and spilled in a accident etc. in a nuclear facility etc. may be efficiently and easily collected and removed at a low cost.

Abstract: A method of stabilizing a fuel containing a reactive sodium metal may include puncturing a cladding of a fuel pin enclosing the fuel containing the reactive sodium metal to form an injection passage and an extraction passage. A reaction gas may be injected into the fuel pin through the injection passage to react with the reactive sodium metal to form a stable sodium compound. A ratio of a product gas and a remaining quantity of the reaction gas exiting the fuel pin through the extraction passage is subsequently measured, wherein the product gas is a reaction product of the reaction gas and the reactive sodium metal within the fuel pin. Once the measured ratio indicates that a reaction between the reaction gas and the reactive sodium metal is complete, the injection passage and the extraction passage are sealed so as to confine the stable sodium compound within the fuel pin.

Abstract: An aspect of the present disclosure relates to a method for collecting volatile radioactive substances. The method includes irradiating a volatile radioactive substance on or under a contaminated material surface using microwave radiation and vaporizing the volatile radioactive substance, wherein the volatile radioactive substance comprises at least one of cesium and iodine. The method further includes recovering the vaporized volatile radioactive substance from the contaminated material. The method may be accomplished with and/or without physically collecting or isolating the contaminated material.

Abstract: A radioactive waste acid is recycled. The waste acid is a fluoboric waste acid. The waste acid contains a lot of oxides and radioactive nuclei. The waste fluoboric acid is processed to obtain a purified fluoboric acid. The amount of radioactive nuclei is greatly reduced. Thus, the present invention has a simple procedure with low cost and reduced power consumption.

Abstract: The present disclosure describes solid waste forms and methods of processing waste. In one particular implementation, the invention provides a method of processing waste that may be particularly suitable for processing hazardous waste. In this method, a waste component is combined with an aluminum oxide and an acidic phosphate component in a slurry. A molar ratio of aluminum to phosphorus in the slurry is greater than one. Water in the slurry may be evaporated while mixing the slurry at a temperature of about 140-200° C. The mixed slurry may be allowed to cure into a solid waste form. This solid waste form includes an anhydrous aluminum phosphate with at least a residual portion of the waste component bound therein.

Abstract: An apparatus and method for inter-unit transfer of spent nuclear fuel. In one aspect, the invention is a method of transferring high level radioactive waste comprising: a) loading high level radioactive waste into a water-filled cavity of a canister body having an open top end at a first location; b) coupling a lid to the canister body to enclose the open top end; c) removing a volume of water from the cavity so that a water level of the water within the cavity is above a top end of the high level radioactive waste and a space exists between the water level and a bottom surface of the lid; d) hermetically sealing the cavity; and e) transferring the canister to a second location, the water level remaining above the top end of the high level radioactive waste during the transfer.

Abstract: A system and method for storing multiple canisters containing high level waste below grade that afford adequate ventilation of the spent fuel storage cavity. In one aspect, the invention is a ventilated system for storing high level waste emitting heat, the system comprising: an air-intake shell forming an air-intake cavity; a plurality of storage shells, each storage shell forming a storage cavity; a lid positioned atop each of the storage shells; an outlet vent forming a passageway between an ambient environment and a top portion of each of the storage cavities; and a network of pipes forming hermetically sealed passageways between a bottom portion of the air-intake cavity and at least two different openings at a bottom portion of each of the storage cavities such that blockage of a first one of the openings does not prohibit air from flowing from the air-intake cavity into the storage cavity via a second one of the openings.

Abstract: A fuel basket spacer, and system and method for storing high level radioactive waste. In one aspect, the invention is an apparatus for transporting and/or storing radioactive materials comprising: a body having a cavity for receiving radioactive materials; a basket positioned in the cavity comprising a plurality of cells; and a structure having an outer surface and an inner surface forming a central passageway; the structure positioned in the cavity so that the basket extends through the central passageway of the structure; and wherein the internal perimeter of the structure corresponds to the external perimeter of the basket in size and shape and the external perimeter of the structure corresponds to the perimeter of the cavity in size and shape. Circumferential clearances are provided between structure and the basket and the structure and the body that are eliminated when exposed to a residual heat load of the radioactive waste.

Abstract: A method of stabilizing a fuel containing a reactive sodium metal may include puncturing a cladding of a fuel pin enclosing the fuel containing the reactive sodium metal to form an injection passage and an extraction passage. A reaction gas may be injected into the fuel pin through the injection passage to react with the reactive sodium metal to form a stable sodium compound. A ratio of a product gas and a remaining quantity of the reaction gas exiting the fuel pin through the extraction passage is subsequently measured, wherein the product gas is a reaction product of the reaction gas and the reactive sodium metal within the fuel pin. Once the measured ratio indicates that a reaction between the reaction gas and the reactive sodium metal is complete, the injection passage and the extraction passage are sealed so as to confine the stable sodium compound within the fuel pin.

Abstract: Process for the destruction of toxic residues via oxidation in the presence of water and oxygen developed in homogenous phase at temperatures over 374° C. and pressure of at least 220 atmospheres and a continuous mobile unit easily transferred to treat effluents or contaminated media. This mobile unit is composed of a reactor, which includes pressurization, reaction, cooling, depressurization and sampling zones for the destruction of toxic residues like polychloride biphenyls (PCBs), pyridines, and other hazardous compounds.

Abstract: A decontamination method of solid-state material contaminated by radiocesium comprising bringing the solid-state material containing radiocesium in contact with a first processing solution and preferably eluting cesium ion from the solid-state material to the liquid phase under the presence of potassium ion or ammonium ion.

Abstract: Methods for partially decontaminating radioactive waste wherein the waste is first mixed, or brought in contact, with at least one corrosive medium. Activation energy is then supplied to the corrosive medium, so that at least a portion of the radionuclide present in the waste is converted into at least one gaseous reaction product, or is dissolved, by hydrogen or hydrogen ions, oxygen or oxygen ions, and/or halogen (for example chlorine) or halogen ions from the corrosive medium. The aim is that of decontaminating a 12C/13C-containing porous solid waste, which is contaminated with the 14C radionuclide. For this purpose, CO2 and/or hydrogen are applied as corrosive media to the waste, so that at least a portion of the waste is reacted to form at least one gaseous reaction product, wherein the process temperature is selected so that the 14C radionuclide is enriched in the reaction product over 12C/13C.

Abstract: A method for treating a radioactive liquid waste containing a sodium salt, which includes: feeding a radioactive liquid waste containing at least one of sodium hydroxide, sodium hydrogencarbonate and sodium carbonate to an anode chamber in an electrolytic cell provided with an anode and a cathode on both sides of a permeable membrane, which is selectively permeable to sodium ions, and electrodialyzing the radioactive liquid waste; separating sodium ions permeated through the permeable membrane as sodium hydroxide from the radioactive liquid waste in a cathode chamber; separating a radioactive substance remaining in the anode chamber as a concentrated radioactive liquid waste; and recovering the separated sodium hydroxide and concentrated radioactive liquid waste, respectively.

Abstract: A chemical decontamination apparatus of the present invention chemically dissolves radioactive substance-containing oxide films formed or adhering on the surface of a decontamination object by using ozone water to conduct decontamination. The chemical decontamination apparatus includes an ozone generating unit for generating ozone gas, an ozone supplying device for supplying the generated ozone gas to an ozone supplying unit in water, and a sintered metal element 37 which is disposed in the ozone supplying unit and to which ozone gas is supplied from the ozone supplying device. The ozone gas supplied to a sintered metal element interior from the ozone supplying device is allowed to flow out of the element into water so as to generate ozone water.

Abstract: Biowaste sterilizers are described. In one implementation an exemplary system has waste transport vessels that can be intermittently heated and pressurized, for example, with steam, and are interconnected to provide multiple sterilization pathways for waste as the waste is transported. Selected sterilization pathways may depend on attributes of the waste. Sterilization factors, such as mechanical shredding, application of steam, application of pressure, maintenance of temperature, separation of liquid, etc., are integrated into the waste transport features of the system, which can be made compact to save space while processing relatively large bulk amounts of materials, such as medical wastes. The system maintains safe isolation of bio-hazardous components in the waste from the external environment. A system controller provides parameters management, smart sterilization cycle control, quality assurance, safety management, diagnostics, and reporting over a network.

Abstract: The present invention relates to a process for the manufacture of a glass frit for the containment by vitrification of a material comprising at least one oxidizable or reducible chemical species, and also to a process for the containment of said material by vitrification. The process for the manufacture of the glass frit comprises a step of incorporating into a raw glass frit at least one redox couple, the nature and the amount of which make it possible to maintain said at least one chemical species in its oxidized or reduced state. The containment process comprises mixing and hot melting the resulting glass frit and the material to be contained. The present invention makes it possible to optimize the containment of pollutants such as radionucleides, metals and metalloids. The material may be nuclear waste or a material derived from the incineration of household refuse.

Abstract: Bio-waste sterilizers are described. In one implementation an exemplary system has waste transport vessels that can be intermittently heated and pressurized, for example, with steam, and are interconnected to provide multiple sterilization pathways for waste as the waste is transported. Selected sterilization pathways may depend on attributes of the waste. Sterilization factors, such as mechanical shredding, application of steam, application of pressure, maintenance of temperature, separation of liquid, etc., are integrated into the waste transport features of the system, which can be made compact to save space while processing relatively large bulk amounts of materials, such as medical wastes. The system maintains safe isolation of bio-hazardous components in the waste from the external environment. A system controller provides parameters management, smart sterilization cycle control, quality assurance, safety management, diagnostics, and reporting over a network.

Abstract: The present invention provides an apparatus useful for the separation of hazardous and non-hazardous organic and inorganic constituents from various matrices. A method of separating such constituents is also provided.

Abstract: An apparatus and system for separating remaining powder of hulls includes a first remaining powder separating unit to be supplied with hulls of a spent nuclear fuel subjected to a high-temperature oxidation, and to include a first brush for separating remaining powder of the hulls; a hull alignment unit to be supplied with the hulls from the first remaining powder separating unit, and to align the hulls; a second remaining powder separating unit to be supplied with the aligned hulls from the hull alignment unit, and to include a second brush for separating remaining powder adhered on an inner peripheral surface of the hulls; and a third remaining powder separating unit to be supplied with the hulls from the second remaining powder separating unit, and to separate the remaining powder remaining on the inner/outer peripheral surface of the hulls by using air.

Abstract: The disclosed invention relates to a portable decontamination unit. The invention also relates to a decontamination process. The decontamination unit may be ruggedized for use in hostile environments such as those that may be anticipated for military applications.

Abstract: A radioactive containment composition may be created for containing radionuclides from a radioactive material by mixing a clay mineral with water. This mixture may form an aqueous clay suspension, which in turn can be refined by filtering to remove coarse material. The aqueous clay suspension may be applied to a radioactive material, allowing the radionuclides to be exchanged with cations in the aqueous clay suspension. The resulting aqueous slurry may be collected, heated and analyzed.

Abstract: Methods for removing nuclear waste from a component are provided. In one embodiment, the method includes the steps of supplying oxalic acid to the nuclear waste on the component to form an oxalic acid/waste solution, feeding the oxalic acid/waste solution from the component, feeding an oxidant to the oxalic acid/waste solution to form carbon-dioxide, water and a precipitate, and separating the precipitate from the water. A system for removing nuclear waste is also provided.

Abstract: A process for selectively removing contaminant ions from a solution includes: a) contacting the solution with magnetic particles coupled to selectively chelating ion exchange functionality containing moieties prepared by: i) activating carboxyl groups on the selectively chelating ion exchange functionality containing moieties by the formation of an acyl fluoride, and ii) reacting the acyl fluoride with the magnetic particles, the magnetic particles having a particle size of less than 10 microns; b) allowing the chelating functionality coupled magnetic particles to selectively bind one or more of the contaminant ions; and, c) extracting the chelating functionality coupled magnetic particles and contaminant ions from the solution by magnetic filtration.

Abstract: A system, apparatus and method of processing and/or removing radioactive materials from a body of water that utilizes the buoyancy of the water itself to minimize the load experienced by a crane and/or other lifting equipment. In one aspect, the invention is a method comprising: a) submerging a container having a top, a bottom, and a cavity in a body of water having a surface level, the cavity filling with water; b) positioning radioactive material within the cavity of the submerged container; c) raising the submerged container until the top of the containment apparatus is above the surface level of the body of water while a major portion of the container remains below the surface level of the body of water; and d) removing bulk water from the cavity while the top of the container remains above the surface level of the body of water and a portion of the container remains submerged.

Abstract: The invention relates to a process for separating, in an aqueous medium, at least one actinide element from one or more lanthanide elements by using at least one molecule which sequesters the said actinide element to be separated and membrane filtration, the said process successively comprising: a) a step of bringing at least one molecule which sequesters the said actinide element in contact with the aqueous medium, the said molecule not being retained in the non-complexed state by the said membrane and being capable of forming a complex with the actinide element to be separated, comprising the said element and at least two of the said sequestering molecules, which complex is capable of being retained by the membrane; b) a step of passing the aqueous medium over the membrane in order to form a permeate on one side, comprising an aqueous effluent depleted of the said actinide element, and a retentate comprising the said complex.

Abstract: Methods and devices for removing inflammable gases produced by radiolysis in a closed chamber containing radioactive matters comprising organic compounds and possibly water, or radioactive matters in the presence of organic compounds and possibly water. Inside the chamber there may be placed a catalyst of at least one reaction for oxidizing the inflammable gases by oxygen contained in the chamber atmosphere, supported by an inert solid support; a catalyst of at least the reaction for oxidizing CO to CO2; possibly an oxygen source; and possibly a hygroscopic microporous inert solid support. Also, chambers for radioactive matters containing such devices.

Abstract: A system, method and apparatus for transporting and/or storing radioactive materials, such as spent nuclear fuel. In one aspect, the invention is a jacket apparatus that is filled with a neutron absorbing fluid and adapted to facilitate a cyclical thermosiphon flow of the neutron absorbing fluid within the jacket when the neutron absorbing fluid is subjected to heat emanating from the cavity. In other aspects, the invention can be a method and container incorporating and/or using the same.

Abstract: The present invention relates to the use of lithium salts and/or magnesium salts for the precipitation of aluminum oxides present in aqueous media.

Abstract: The present invention relates to the use of lithium salts and/or magnesium salts for the precipitation of aluminum oxides present in aqueous media.

Abstract: The present invention provides methods and compositions for detecting, identifying and measuring the abundance of chemical nerve agents. Methods and compositions of the present invention are capable of providing selective detection of phosphorous based nerve agents, such as nerve agents that are esters of methyl phosphonic acid derivatives incorporating a moderately good leaving group at the phosphorus. Selectivity in the present invention is provided by a sensor composition having an alpha (?) effect nucleophile group that undergoes specific nucleophilic substitution and rearrangement reactions with phosphorus based nerve agents having a tetrahederal phosphorous bound to oxygen. The present invention includes embodiments employing a sensor composition further comprising a reporter group covalently linked to the alpha effect nucleophile group allowing rapid optical readout of nerve agent detection events, including direct visual readout and optical readout via spectroscopic analysis.

Abstract: Method of treating sodium contained in the interconnected open pores of a structure placed in a cladding, the pores furthermore containing a radioactive substance. The method comprises the following successive steps: a) at least two slits are made over the entire length of the cladding; b) the sodium is converted to sodium carbonate by a carbonation reaction by bringing the structure into contact, via the slits, with a reactive gas mixture comprising steam, carbon dioxide and a gas inert with respect to sodium, in such a way that the expansion of the carbonate causes the cladding and the structure to open starting from the slits and results in the carbonation reaction propagating into the structure.

Abstract: A system and method for storing high level waste. In one aspect, the invention is a system comprising: an outer shell having an open top end and a hermetically closed bottom end; an inner shell forming a cavity, the inner shell positioned inside the outer shell so as to form a space between the inner shell and the outer shell; at least one passageway connecting the space and a bottom portion of the cavity; at least one passageway connecting an ambient atmosphere and a top portion of the space; a lid positioned atop the inner shell, the lid having at least one passageway connecting the cavity and the ambient atmosphere; and a seal between the lid and the inner shell so at form a hermetic lid-to-inner shell interface.

Abstract: Clay-based compositions capable of absorbing contaminants from surfaces or objects having surface faces may be applied to a surface and later removed, the removed clay-based compositions absorbing at least a portion of the contaminant from the surface or object to which it was applied.

Abstract: The present invention provides an apparatus useful for the separation of hazardous and non-hazardous organic and inorganic constituents from various matrices. A method of separating such constituents is also provided.

Abstract: A rotary-drum mechanical surface decontamination method for radioactively contaminated metal first places a feed chute fully loaded with radioactively contaminated metal on a hydraulic lift platform of a dual-chain roller conveyor and then moves the feed chute to a hydraulic cover-opening machine for positioning, and then uses a hydraulic cover-opening machine to open the cover of the feed chute, while non-covered feed chute will advance further to the post on a feed hopper of a drum spray washer, and then drop the workpieces into a conical drum for rotary multi-angular spray washing. The decontaminated metal waste is transferred by a vibrating discharger onto a conveyor and then into a discharge tank, and to the hydraulic cover-opening machine by a dual-chain roller conveyor, and to the hydraulic lift platform to complete the decontamination process.

Abstract: Systems and methods are provided for reducing the storage time of spent nuclear fuel. In one embodiment, a method is provided that includes providing a sample of spent nuclear fuel and irradiating the spent nuclear fuel with substantially collimated gamma ray photons having energy levels of about 10 MeV to about 15 MeV for a predetermined time period to initiate a photofission reaction in the remaining fertile fissile material in the spent nuclear fuel.

Abstract: The present invention provides a method of online analysis of mineral waste content of a slurry in a mineral separation process, said method including the steps of: measuring the density of said slurry (10); measuring the concentration of solids in said slurry (12); calculating the density of solids in said slurry from said slurry density and said solids concentration (20); and calculating said mineral waste content from said solids density (22). The present invention also provides an online analyzer for mineral waste content of a slurry in a mineral separation process.

Abstract: The current methods of removing the surface-deposited layer contaminated by radioisotopes has the disadvantage of rigorous applicability conditions in such terms as the substance to be treated, the area and the shape, so the scope of their applicability is quite limited; in addition, 100% decontamination is not guaranteed and in spite of more than 50% that can be decontaminated, a greater part of the deposited radioisotopes remain unremoved, limiting the decontamination performance of the methods. Parts, structural components, etc. that have their surfaces contaminated by radioisotopes in the accelerators, nuclear reactors, RI product manufacturing factories, nuclear fuel factories, nuclear fuel reprocessing factories, etc.

Abstract: A chemical decontamination apparatus of the present invention chemically dissolves radioactive substance-containing oxide films formed or adhering on the surface of a decontamination object by using ozone water to conduct decontamination. The chemical decontamination apparatus includes an ozone generating unit for generating ozone gas, an ozone supplying device for supplying the generated ozone gas to an ozone supplying unit in water, and a sintered metal element 37 which is disposed in the ozone supplying unit and to which ozone gas is supplied from the ozone supplying device. The ozone gas supplied to a sintered metal element interior from the ozone supplying device is allowed to flow out of the element into water so as to generate ozone water.

Abstract: Methods of treating radioactive materials are disclosed. In one aspect, a method may include mixing a radioactive isotope diluted in a filler material with a radioactive material treatment composition to form a resulting material. The radioactive material treatment composition may include mostly salt, and from 0.5 to 15 wt % sorbent. The method may further include mixing the resulting material with one or more inorganic binding agents. Other methods of treating radioactive materials are also disclosed, as well as compositions for treating radioactive materials.

Abstract: A method of decontaminating porous surfaces contaminated with water soluble radionuclides by contacting the contaminated porous surfaces with an ionic solution capable of solubilizing radionuclides present in the porous surfaces followed by contacting the solubilized radionuclides with a gel containing a radionuclide chelator to bind the radionuclides to the gel, and physically removing the gel from the porous surfaces. A dry mix is also disclosed of a cross-linked ionic polymer salt, a linear ionic polymer salt, a radionuclide chelator, and a gel formation controller present in the range of from 0% to about 40% by weight of the dry mix, wherein the ionic polymer salts are granular and the non cross-linked ionic polymer salt is present as a minor constituent.

Abstract: Disclosed herein is provided an evaporator/calciner in which hazardous materials, such as radioactive liquids, are converted into chemically stable, solid forms by evaporating, drying and calcination within a single vessel, that can then be sealed and used for long term storage.