Abstract: A barrier-wall structure having a retaining wall with a back support surface supported by backfill adjacent thereto, wherein the backfill is municipal solid waste processed into fill-material in the form of a multiplicity of biologically-inert compacted pieces.

Abstract: Provided herein is a method for constructing a pumping-injection well of a groundwater reservoir in a dump of an open-pit mine. The pumping-injection well includes a bottom pipe, intermediate pipes, and a top pipe in sequence from bottom to top connected from bottom to top. The method includes: arranging a rubble barrier around the pumping-injection well, and installing the bottom pipe of the pumping-injection well at a designed position of the pumping-injection well as a center of circle; continuing to install an intermediate pipe on the bottom pipe, and pile up a rubble pile; continuing to stack multiple intermediate pipes, and starting the construction of the groundwater reservoir; discarding discarded materials from the open-pit mine to form a dump; continuing to stack intermediate pipes to build an inverted trapezoidal surface sump around the pumping-injection well; and installing the top pipe and a well cover to form a complete pumping-injection well.

Abstract: A storage pod for containing a body and decomposition material for decomposing the body in the storage pod includes an elongate housing having opposite ends. The housing contains the body and the decomposition material. The housing defines an interior configured to receive the body and decomposition material, at least one air vent in fluid communication with the interior so that air can enter the interior through the at least one air vent when the housing is closed, and a product inlet in fluid communication with the interior so that decomposition material can enter the interior through the product inlet when the housing is closed.

Abstract: An underground ventilated system for storing nuclear waste materials. The system includes a storage module having an outer shell defining an internal cavity and an inner shell. A majority of the height of the outer shell may be disposed below grade. The outer shell may include a hermetically sealed bottom. First and second canisters are positioned in lower and upper portions within the cavity respectively in vertically stacked relationship. A centering and spacing ring assembly is interspersed between the first and second canisters to transfer the weight of the upper second canister to the lower first canister. The assembly may include centering lugs which laterally restrain the first and second canisters in case of a seismic event. A natural convection driven ventilated air system cools the canisters to remove residual decay heat to the atmosphere. In one non-limiting embodiment, the shells are made of steel.

Abstract: A system for encapsulating and storing disused radiological sources in sealed capsules is provided, the system having a basket to removably position capsules relative to each other, the capsules containing the radiological sources; a containment vessel for receiving the basket; and a cask reversibly encapsulating or otherwise housing the containment vessel. Also provided is a method for packaging, transporting and storing disused radiological sources, the method having the steps of transporting sealed capsules containing radiological sources from water pools to baskets; placing the basket in a containment vessel and sealing the vessel with helium backfill; placing the vessel in a cask and reversibly capping the cask; surrounding the cask with personnel a shield and crumple zones to create a construct; and transporting and storing the construct until its final disposal at a geological repository or a deep borehole, all without repackaging of the disused radiological sealed capsules.

Abstract: A container is designed to safely store radioactive debris from, for example, a nuclear reactor meltdown, in water or air. The container, with preferably although not necessarily all metal parts, has an overpack having an elongated cylindrical body extending between a top end and a bottom end, a planar bottom part at the bottom end, an open top at the top end, and a circular planar lid mounted over the open top. A basket is situated inside of the overpack. The basket has a plurality of elongated cylindrical canisters that are in parallel along their lengths. Each of the canisters has an elongated cylindrical body extending between a top end and a bottom end, a planar bottom part at the bottom end, an open top at the top end, and a circular planar lid mounted over the open top.

Abstract: A method for encapsulating a fuel rod or a fuel rod section in a container includes inserting the fuel rod or fuel rod section into the container. One of the ends of the container is connected to a purging-gas line. The container is dehydrated and purged by use of a purging gas. The ends of the container are connected to a bypass line in such a way that a closed gas circuit is produced and a hot gas is circulated in the gas circuit until the absolute moisture content reaches an end value at which the absolute moisture content no longer rises. The container is disconnected from the gas circuit and subsequently the container is closed in a fluid-tight manner at both ends.

Abstract: A canister for storing radioactive materials includes a base plate, side wall and a top plate. The top plate includes a top surface with a top edge having a bevel, and with a channel set in from the top edge. The top plate is sealed to the sidewall by a weld formed between the beveled top edge and the top of the side wall. The base plate is sealed to a bottom of the sidewall, so that a sealed vessel is formed.

Abstract: A method for preparing low level radioactive hazardous wastes (LLHZ) for disposal in a landfill. The method includes providing a softsided transportable container at a hazardous debris collection site, where the softsided container has at least three layers of materials, an outer, middle and an inner layer, where the middle layer is a water impervious material. Each layer has a closable opening located on the top of the softsided layer. Hardsided closed containers containing LLHZ located in the interior of the hard container are loaded into the interior of the softsided container. Each layer of the softsided container is then closed, and the package transported and shipped to a disposal site for burial.

Abstract: A method and apparatus for the stabilization and safe removal of buried waste that is tested and classified as being transuranic or not transuranic waste and disposed accordingly. The buried waste (usually in vertical pipe units) is enclosed in a casing and ground and mixed with the surrounding soil. This process allows for chemical reactions to occur that stabilizes the mixture. The entire process is contained within the casing to avoid contamination. In situ or external testing is done for radio isotopes to classify the waste. If it is classified as transuranic the waste is removed in a controlled way into a retrieval enclosure and disposed off in drums. If the waste is not transuranic then grout is introduced into the mixture, allowed to set and the resulting monolith is removed and buried in trenches.

Abstract: A container, a device, and a method encapsulate a fuel rod or a fuel rod portion in a gas-tight manner. The container has a hollow cylindrical container part which is closed at the free ends of the container part in a fluid-tight manner by a respective single-piece closure stopper. The closure stopper is provided with a channel that fluidically connects the flushing chamber of the container part to the exterior exclusively in an intermediate position, which is assumed prior to reaching an end position during the assembly process and in which the closure stopper additionally projects out of the container part by an axial length compared to the end position of the closure stopper.

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: Provided is a method for disposal of radioactive waste which can reduce the radiation level until the waste can be reused as landfill or the like and which prevents the leakage of radiation nuclides in the ground. The method includes the following: a primary treatment step of turning the radioactive waste into a radioactive waste (primary treated waste) which has a radiation level equal to or less than a reference value via a radiation shielding agent composed of or predominantly composed of a Ca-based inorganic compound; and a secondary treatment step of heating to melt the primary treated waste and thereafter cooling the same to glass granules, and then sealing radioactive nuclides in the glass body.

Abstract: The present invention provides systems, methods and devices for storing and/or disposing of hazardous waste material. In some embodiments, the waste material includes nuclear waste such as calcined material. In certain embodiments, the device includes a container having a container body, a filling port configured to couple with a filling nozzle and a filling plug, and an evacuation port having a filter. The evacuation port is configured to couple with an evacuation nozzle and an evacuation plug. In certain embodiments, the method includes (a) adding hazardous waste material via a filling nozzle coupled to a filling port of a container, the container including an evacuation port, (b) evacuating the container during adding of the hazardous waste material via an evacuation nozzle coupled to an evacuation port of the container, (c) sealing the filling port, (d) heating the container, and (e) sealing the evacuation port.

Abstract: A waste form for and a method of rendering hazardous materials less dangerous is disclosed that includes fixing the hazardous material in nanopores of a nanoporous material, reacting the trapped hazardous material to render it less volatile/soluble, and vitrifying the nanoporous material containing the less volatile/soluble hazardous material.

Abstract: The invention includes a radioactive waste containment system for containing a radioactive waste material. The radioactive waste containment system includes a radioactive waste containment system outermost exterior containment layer comprised of an exterior containment layer glass material having an exterior containment layer property. The radioactive waste containment system includes a radioactive waste containment system adjacent interior containment layer, the adjacent interior containment layer comprised of an adjacent interior containment layer glass material having an adjacent interior containment layer property, the radioactive waste containment system adjacent interior containment layer is fused with the radioactive waste containment system outermost exterior containment layer with the properties not equal wherein the fused adjacent interior containment layer and the radioactive waste containment system outermost exterior containment layer are in compression.

Abstract: Provided is a method for disposal of radioactive waste which can reduce the radiation level until the waste can be reused as landfill or the like and which prevents the leakage of radiation nuclides in the ground. The method includes the following: a primary treatment step of turning the radioactive waste into a radioactive waste (primary treated waste) which has a radiation level equal to or less than a reference value via a radiation shielding agent composed of or predominantly composed of a Ca-based inorganic compound; and a secondary treatment step of heating to melt the primary treated waste and thereafter cooling the same to glass granules, and then sealing radioactive nuclides in the glass body.

Abstract: A concrete pit containing radioactive waste is surrounded by a low diffusion layer of cement-based material, which in turn, is surrounded by a low water permeability layer of sodium-type bentonite and the leaching out of calcium ions from the low water permeability layer is inhibited by mixing sodium bicarbonate or sodium carbonate with the sodium-type bentonite/sand mixture of the low water-permeability layer so that leached calcium ions form a barrier layer having calcium carbonate as the main component in the vicinity of the interface between the layers.

Abstract: In one embodiment, a system and method for dry storage comprises removing spent fuel rods from their fuel rod assemblies and placing the freed fuel rods in a storage cell of a dry storage canister with a high packing density and without a neutron absorber material present.

Abstract: A container for confining nuclear waste, including a sleeve of longitudinal axis closed at a first longitudinal end by a base and a second longitudinal free end via which the container is designed to be loaded, a plug configured to close the second longitudinal free end tightly, a flange fixed on the inner face of the sleeve to the side of the second longitudinal free end, the plug having at least one external diameter substantially equal to at least one internal diameter of the flange, the plug configured to be welded on the flange such that the welding zone is offset radially towards an interior of the container, relative to an inner face of the sleeve.

Abstract: The present invention provides processes to immobilize high alkaline radioactive and/or hazardous waste in a silicate-based glass, the waste containing one or more of radionuclides, hazardous elements, hazardous compounds, and/or other compounds. The invention also provides silicate-based glass compositions for use in immobilizing radioactive and/or hazardous waste.

Abstract: Systems for treating contaminated soil are described herein. One system includes a soil chamber that includes one or more walls and at least one floor; at least one heater attached to or inside of at least one of the walls; and at least one heater coupled to or in the floor. Two or more of the walls enclose an interior of the soil chamber. At least one of the walls is configured to move between a closed position during heating of the soil chamber, and an open position that allows a soil moving vehicle to access an interior of the soil chamber to provide or remove soil to and from the soil chamber. At least one wall heater and at least one floor heater provide heat that transfers from the heaters to the contaminated soil in the soil chamber.

Abstract: The invention relates to a long-term storage device (1) intended to receive a containment case (3) containing radioactive materials, where this device includes a main body (2) having an inner surface delimiting a housing (7). According to the invention, in an unloaded configuration, in which the containment case containing radioactive materials is absent from the storage device, the latter includes a storage case (9) delimiting a cavity (4) to receive the containment case, where the storage device also includes ventilation means allowing air to circulate between the exterior of the storage device and a space delimited between the inner surface of the main body and the storage case (9).

Abstract: The invention relates to methods and products enabling decontamination of chemical warfare agents and/or toxic industrial chemicals. More particularly, the invention pertains to improvements of surface decontamination processes using novel sorbents such as nanotubular titania.

Abstract: Systems and methods for containing a hazardous fluid are described, in which first and second precast concrete segments are coupled together to form wall elements having a plurality of void spaces. A precast concrete floor segment can be coupled to the wall elements to form a cavity, and a metal liner can be disposed within the cavity to form a container capable of storing a hazardous fluid. An external barrier configured to be impervious to the hazardous fluid can be coupled to an exterior portion of at least one of the first and second segments.

Abstract: The present disclosure relates to a method of consolidating a calcine comprising radioactive material, the method comprising mixing 60-80% (by weight) of a radionuclide containing calcine with at least one non-radioactive additive, such as an oxide, and hot isostatic pressing the mixture to form a stable monolith of glass/ceramic. In one embodiment, the ratio of radionuclide containing calcine to additives is about 80:20 by weight, wherein the non-radioactive additive comprises oxides such as BaO, CaO, Al2O3, TiO2, SiO2 and others, that combine with the waste elements and compounds to form a ceramic mineral or glass/ceramic material, after hot isostatic pressing. Non-limiting examples of mineral phases that may be formed are: hollandite (BaAl2Ti6O16), zirconolite (CaZrThO7), and perovskite (CaTiO3).

Abstract: The present invention relates to a system, method and apparatus for providing additional radiation shielding to a container holding radioactive materials. In one aspect, the invention is an apparatus that includes a tubular shell constructed of a gamma radiation absorbing material and having an inner surface that forms a cavity having an axis, the cavity having an open top end and an open bottom end; a plurality of spacers extending from the inner surface of the shell toward the axis of the cavity, the spacers extending a first height from the inner surface of the tubular shell; and one or more flange members located at or near the open top end of the cavity extending from the tubular shell toward the axis of the cavity, the flange member extending a second height from the inner surface of the shell, the second height being greater than the first height.

Abstract: A nuclear chemistry laboratory adopts In-site Cutting Technique to remove the large-scale glove box contaminated by transuranium compounds. During removal operation, to prevent further spreading of contamination, it is necessary to build an alpha airtight quarantine tent around the glove box that is ready to be cut. Each section of the quarantine tent maintains a stable airflow and sufficient air exchange to meet negative pressure requirements and effectively prevent leak of ? contamination. It is necessary to install a negative pressure ventilation system to assure the operation of the quarantine tent that has a pressure gradient and allows airflow from low contamination area to high contamination area to effectively prevent spreading of ? contamination and also increase the safety for the transuranium contaminated glove box that is not in service.

Abstract: Materials and methods of synthesizing mixed-layered bismuth oxy-iodine materials, which can be synthesized in the presence of aqueous radioactive iodine species found in caustic solutions (e.g. NaOH or KOH). This technology provides a one-step process for both iodine sequestration and storage from nuclear fuel cycles. It results in materials that will be durable for repository conditions much like those found in Waste Isolation Pilot Plant (WIPP) and estimated for Yucca Mountain (YMP). By controlled reactant concentrations, optimized compositions of these mixed-layered bismuth oxy-iodine inorganic materials are produced that have both a high iodine weight percentage and a low solubility in groundwater environments.

Abstract: A package for storing radioactive waste, which is suitable for safe, ultra-long ultimate disposal having a moisture-impermeable, corrosion-resistant graphite matrix and metal-encased waste products, which are embedded into the matrix. A method for producing such packages is also part of the invention.

Abstract: Provided is a method for treating contaminated soil. The method includes providing contaminated soil in a soil chamber that has at least one wall, and at least one floor, at least one heater coupled to or inside of at least one of the walls and at least one substantially elongated floor heater coupled to or in the floor. At least one of the walls at least partially includes a thermally conductive material configured to transfer heat from at least one of the heaters to an interior of the soil chamber. At least one of the walls at least partially encloses an interior of the soil chamber. At least one of the walls can move between a closed position during heating of the soil chamber, and an open position that allows a soil moving vehicle to access an interior of the soil chamber to provide or remove soil to and from the soil chamber unencumbered by piping located within the soil volume.

Abstract: The invention provides a storage device adapted for use for the storage of waste materials in a glovebox, the device comprising support means incorporating engaging means, the support means comprising a substantially hollow body and the engaging means being adapted to restrain an object therein. It is a particular advantage of the device that the support means defines a hollow interior section in the device, thereby facilitating the storage of additional waste materials integrally within the device in a safe and orderly manner. The device finds particular application in a method for the removal of waste materials located in a glovebox, wherein the waste materials comprise hazardous biological or radioactive materials.

Abstract: Materials and methods of making low-sintering-temperature glass waste forms that sequester radioactive iodine in a strong and durable structure. First, the iodine is captured by an adsorbant, which forms an iodine-loaded material, e.g., AgI, AgI-zeolite, AgI-mordenite, Ag-silica aerogel, ZnI2, CuI, or Bi5O7I. Next, particles of the iodine-loaded material are mixed with powdered frits of low-sintering-temperature glasses (comprising various oxides of Si, B, Bi, Pb, and Zn), and then sintered at a relatively low temperature, ranging from 425° C. to 550° C. The sintering converts the mixed powders into a solid block of a glassy waste form, having low iodine leaching rates. The vitrified glassy waste form can contain as much as 60 wt % AgI. A preferred glass, having a sintering temperature of 500° C. (below the silver iodide sublimation temperature of 500° C.) was identified that contains oxides of boron, bismuth, and zinc, while containing essentially no lead or silicon.

Abstract: An apparatus and method for loading drums into a drum container, in which a function of gripping a lid of the drum container is added to a gripper used when a drum filled with radioactive waste is loaded into the drum container, thereby considerably reducing loading time of the drums, risk of dropping the drum, and preventing a radiation exposure risk. The apparatus includes a drum feeder transferring a drum, a drum container into which the drums transferred through the drum feeder are sequentially loaded, a support frame on which a lid of the drum container is placed when the drums are being loaded, and a crane having a gripper that selectively grips and transfers the drum or the drum container lid. The gripper includes radial gripper arms, an arm hydraulic unit reciprocating the gripper arms, jaws on inner sides of the gripper arms and gripping an outer surface of the drum, and latches for latching the drum container lid.

Abstract: A method, apparatus and system for the transferring a container for receiving high level radioactive waste into and/or out of a pool. The instant invention utilizes a specially designed container in order to make effective use of a stand placed within the pool.

Abstract: A method for underwater packaging of radioactive materials includes creating a vacuum in a cavity of a cleaning device to automatically cause a portion of the cleaning device to move upward to actuate the cleaning device from an open position to a closed position; mounting the cleaning device inside a safe containment area of a transportation and/or storage device; placing the transportation and/or storage device in a pool after filling the safe containment area with water; loading a radioactive material into the safe containment area; closing the transportation and/or storage device using at least one cover; extracting the transportation and/or storage device from the pool; draining the water inside the safe containment area; and creating a pressure differential in the safe containment area to dry the safe containment area, wherein the pressure differential causes the cleaning device to automatically actuate from the closed position to the open position.

Abstract: An apparatus and method for automatically loading drums into a drum container, in which, when the drums filled with radioactive waste are loaded into the drum container, the drums are fed to a designated position, and placed at a fixed position, reducing loading time and manpower as well as minimizing radiation exposure risk associated with radioactive waste treatment. The apparatus includes a drum feeder having conveyor modules transferring the drums and a turntable rotating a drum transferred to an orientation where the drum can be gripped, for sequentially loading the drums, a support frame on which a lid of the drum container is placed when the drums are being loaded, and a crane that grips and transfers the drum or the drum container lid.

Abstract: The present invention relates to a system, method and apparatus for providing additional radiation shielding to a container holding radioactive materials. In one aspect, the invention is an apparatus that includes a tubular shell constructed of a gamma radiation absorbing material and having an inner surface that forms a cavity having an axis, the cavity having an open top end and an open bottom end; a plurality of spacers extending from the inner surface of the shell toward the axis of the cavity, the spacers extending a first height from the inner surface of the tubular shell; and one or more flange members located at or near the open top end of the cavity extending from the tubular shell toward the axis of the cavity, the flange member extending a second height from the inner surface of the shell, the second height being greater than the first height.

Abstract: The present invention provides processes to immobilize high alkaline radioactive and/or hazardous waste in a silicate-based glass, the waste containing one or more of radionuclides, hazardous elements, hazardous compounds, and/or other compounds. The invention also provides silicate-based glass compositions for use in immobilizing radioactive and/or hazardous waste.

Abstract: Systems and methods for storing spent nuclear fuel below grade that afford adequate ventilation of the spent fuel storage cavity. In one aspect, the invention is a system comprising: a shell forming a cavity for receiving a canister of spent nuclear fuel, at least a portion of the shell positioned below grade; and at least one inlet ventilation duct extending from an above grade inlet to a below grade outlet at or near a bottom of the cavity; the inlet ventilation duct connected to the shell so that the cavity is hermetically sealed to ingress of below grade fluids.

Abstract: A radioactive material handling assembly (10) includes an outer housing (12) and an inner cell (14). The inner cell defines a radioactive material containment/handling chamber (16) and is removably mountable inside the outer housing. Handling means is operable from outside the inner cell to handle radioactive materials located in the containment/handling chamber. At least one of the outer housing and the inner cell is predominantly of a shielding material which is opaque to radioactivity.

Abstract: Methods of removing contaminant matter from porous materials include applying a polymer material to a contaminated surface, irradiating the contaminated surface to cause redistribution of contaminant matter, and removing at least a portion of the polymer material from the surface. Systems for decontaminating a contaminated structure comprising porous material include a radiation device configured to emit electromagnetic radiation toward a surface of a structure, and at least one spray device configured to apply a capture material onto the surface of the structure. Polymer materials that can be used in such methods and systems include polyphosphazine-based polymer materials having polyphosphazine backbone segments and side chain groups that include selected functional groups.

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: A method for storing high level radioactive waste in a passively cooled cavity. In one embodiment, the invention comprises: (a) providing a container 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 within the outer shell so as to form a space between the inner shell and the outer shell, and at least one opening in the inner shell that forms a passageway between the space and a bottom portion of the cavity; (b) lowering a hermetically sealed canister holding high level radioactive waste into the cavity via the open top end; and (c) positioning a lid having at least one inlet vent and at least one outlet vent atop the container such that the at least one inlet vent forms a passageway from an ambient atmosphere to the space and the at least one outlet vent forms a passageway from the cavity to the ambient atmosphere, the lid substantially enclosing the open top end.

Abstract: The invention relates to a canister (1) for final repository of spent fuel elements from a nuclear reactor, comprising an insert (2) that contains said spent fuel elements, an inner copper casing (4a, 4b, 4c) that encloses the insert (2), and at least one outer casing (5a, 5b, 5c) that encloses the copper casting and that consists of a passive-film-forming metal or metal alloy, the passive film on the casing being constituted by an essentially oxidic film that is rich in one or more of the metals in the group of metals that consist of the metals zirconium, chromium and titanium.

Abstract: Systems and processes for reducing the volume of radioactive waste materials through pyrolysis and vitrification carried out by microwave heating and, in some instances, a combination of microwave heating and inductive heating. In some embodiments, the microwave-enhanced vitrification system comprises a microwave system for treating waste material combined with a modular vitrification system that uses inductive heating to vitrify waste material. The final product of the microwave-enhanced vitrification system is a denser, compacted radioactive waste product.

Abstract: A storage element for the storage of cases (16) full of nuclear fuel in the horizontal position, said element comprising ventilation means (19, 32) arranged on the sides of the element, so that storage stacks according to this invention can be created. The storage elements may have a cross-section in the shape of regular hexagon to optimise the storage density.

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: A system, method and apparatus for providing additional radiation shielding to a ventilated cask for holding high level radioactive materials. The invention utilizes a tubular shell that is ancillary to the ventilated cask that circumscribes the ventilated cask to add radiation shielding protection while improving heat removal by natural convective air flow. Because the tubular shell and cask are non-unitary and slidably separable from one another, crane lifting capacity is not affected.

Abstract: The invention relates to a coating composition for the storage or containment of waste that is toxic to health and/or the environment, comprising a composition based on an epoxy resin and a curing composition free from an aromatic amine curing agent. The invention also relates to the use of this composition for the coating of said waste.