Uranium-chelating polypeptides comprising at least one helix-loop-helix calcium-binding (EF-hand) motif which comprises a deletion of at least two amino acid in the 12-amino-acid calcium-binding loop sequence, and their use for uranium biodetection and biodecontamination.

The invention relates to an encapsulation composition for the storage or the confinement of waste which is toxic to health and/or the environment, comprising a resin composition containing at least one epoxy resin, and a hardening composition containing at least one polyamidoamine and at least one aromatic polyamine, said encapsulation composition having an aromaticity rate which is equal to, or higher than, 35%. The invention also relates to the use of said composition for encapsulating said waste.

A method for dismantling a steam generator or heat exchanger, such as found in nuclear power plants, which steam generator or heat exchanger includes a plurality of primary circuit tubes with a contaminated inner surface and wherein one or more tubes are sealed with a plug at both end is provided, the method comprising a) opening one or both ends of each sealed tube by creating an opening in or removing, the plug (13); b) introducing a viscous polymer to cure inside the tube wherein the polymer fills the tube across the full tube cross-section at least at the tube ends, immobilizing contaminations in the filled portion inside the tube (11); c) curing the polymer, then detaching the tubes with cured polymer the detached tubes being sealed by the polymer d) sorting out the detached tubes with polymer.

A composite panel for a toxic material encapsulation system, comprising a reinforcing structure extending within and integrally formed with a non-biodegradable thermoplastic polymer.

A composition and method for spray-applying a two-part, self-setting composition containing a dopant that provides a hazard shielding component and is particularly adapted for delivering the components of the composition at a temperature that promotes their spray application as well as a self-setting reaction. The method includes selecting a self-setting compound that is adapted for curing in place once applied, the self-setting compound including at least one dopant material; and applying the compound to a hazard to be encapsulated such as a radiological, lead, asbestos, or PCB. Alternately, a self-curing compound includes a multi-part compound which, upon a mixing of the parts, chemically reacts and cures, and at least one dopant material dispersed into at least one of the parts, wherein the dopant material is selected for providing radiation shielding upon application of the compound.

A composition and method for spray-applying a two-part, self-setting composition containing a dopant that provides a hazard shielding component and is particularly adapted for delivering the components of the composition at a temperature that promotes their spray application as well as a self-setting reaction. The method includes selecting a self-setting compound that is adapted for curing in place once applied, the self-setting compound including at least one dopant material; and applying the compound to a hazard to be encapsulated such as a radiological, lead, asbestos, or PCB. Alternately, a self-curing compound includes a multi-part compound which, upon a mixing of the parts, chemically reacts and cures, and at least one dopant material dispersed into at least one of the parts, wherein the dopant material is selected for providing radiation shielding upon application of the compound.

A method for dismantling a steam generator or heat exchanger, such as found in nuclear power plants, which steam generator or heat exchanger includes a plurality of primary circuit tubes with a contaminated inner surface and wherein one or more tubes are sealed with a plug at both end is provided, the method comprising a) opening one or both ends of each sealed tube by creating an opening in or removing, the plug (13); b) introducing a viscous polymer to cure inside the tube wherein the polymer fills the tube across the full tube cross-section at least at the tube ends, immobilizing contaminations in the filled portion inside the tube (11); c) curing the polymer, then detaching the tubes with cured polymer the detached tubes being sealed by the polymer d) sorting out the detached tubes with polymer.

Implementations are described herein that include producing waste forms that include an amount of radioactive waste material encapsulated in an amount of polymeric material. The waste form can be produced by heating a mixture that includes the polymeric material and the radioactive waste material. The heated or molten mixture is then subject to a process that applies an amount of pressure to the heated mixture and produces the waste form.

A process for the recovery of a radioisotope from a waste resin of a nuclear power plant comprises the steps of: a) treating a waste resin loaded with at least one radioisotope with an organic acid or alkaline compound to release the at least one radioisotope and to obtain a process solution containing the at least one radioisotope; b) separating the at least one radioisotope from the process solution through a reaction specific to the radioisotope so as to obtain a treated process solution depleted of the at least one radioisotope, wherein said depleted process solution comprises the organic acid or alkaline compound and optionally a non-reacted radioisotope; c) reacting the organic acid or alkaline compound in the depleted process solution from step b) by thermal and/or photochemical oxidation to form gaseous reaction products; and d) reloading the waste resin with the reacted process solution from step c) to bind the non-reacted radioisotope on the waste resin. Further, an apparatus is provided to carry out the above method.

A process for the recovery of a radioisotope from a waste resin of a nuclear power plant comprises the steps of: a) treating a waste resin loaded with at least one radioisotope with an organic acid or alkaline compound to release the at least one radioisotope and to obtain a process solution containing the at least one radioisotope; b) separating the at least one radioisotope from the process solution through a reaction specific to the radioisotope so as to obtain a treated process solution depleted of the at least one radioisotope, wherein said depleted process solution comprises the organic acid or alkaline compound and optionally a non-reacted radioisotope; c) reacting the organic acid or alkaline compound in the depleted process solution from step b) by thermal and/or photochemical oxidation to form gaseous reaction products; and d) reloading the waste resin with the reacted process solution from step c) to bind the non-reacted radioisotope on the waste resin. Further, an apparatus is provided to carry out the above method.