A container for the consolidation of waste materials including radioactive containing waste, and a method of consolidating such materials. The container comprises an outer cylinder and an inner cylinder comprising internal compression plates that are designed to resist collapse during consolidation, and therefore control the size of the consolidated container to a predictable shape and dimension. The container is sufficient to hold a variety of materials, including hazardous, toxic, or radioactive waste, and the container is configured to hold such waste without releasing it to the environment.

A container for the consolidation of waste materials including radioactive containing waste, and a method of consolidating such materials. The container comprises an outer cylinder and an inner cylinder comprising internal compression plates that are designed to resist collapse during consolidation, and therefore control the size of the consolidated container to a predictable shape and dimension. The container is sufficient to hold a variety of materials, including hazardous, toxic, or radioactive waste, and the container is configured to hold such waste without releasing it to the environment.

A method of checking the storage and the radioactive activity of a radioactive gas adsorbed by a porous material having scintillation properties, which comprises: (a) putting the porous material in place in an enclosure, (b) performing circulation of the radioactive gas in the enclosure, (c) monitoring the adsorption of the radioactive gas by monitoring the scintillation of the porous material, up to an adsorption level, (d) interrupting the radioactive gas circulation in the enclosure when the adsorption level is attained, (e) placing the enclosure under a vacuum, and (f) monitoring the radioactive activity of the radioactive gas adsorbed by the porous material at the end of step (c) by monitoring the scintillation of the porous material. The porous material comprises metal organic frameworks formed of inorganic sub-units constituted by Zn.sub.4O and an organic ligand.

As an organic iodine remover that removes organic iodine in a containment vessel of a nuclear reactor, an organic agent (for example, an ionic liquid, an interfacial active agent, a quaternary salt, or a phase transfer catalyst) having a function of dissolving and decomposing the organic iodine and retaining iodine is used. The organic iodine remover is a substance composed of a cation and an anion. The organic iodine remover is, in particular, an organic iodine remover in which, in a structure of the cation of the organic agent, carbon or oxygen is bonded to, via a single bond, to a phosphorus element, a sulfur element or a nitrogen element, the number of carbon chains is 2 or more, and an anionic structure is configured with a substance with high nucleophilicity. By using such an organic agent, the organic iodine is removed with an efficiency of 99% or more.

As an organic iodine remover that removes organic iodine in a containment vessel of a nuclear reactor, an organic agent (for example, an ionic liquid, an interfacial active agent, a quaternary salt, or a phase transfer catalyst) having a function of dissolving and decomposing the organic iodine and retaining iodine is used. The organic iodine remover is a substance composed of a cation and an anion. The organic iodine remover is, in particular, an organic iodine remover in which, in a structure of the cation of the organic agent, carbon or oxygen is bonded to, via a single bond, to a phosphorus element, a sulfur element or a nitrogen element, the number of carbon chains is 2 or more, and an anionic structure is configured with a substance with high nucleophilicity. By using such an organic agent, the organic iodine is removed with an efficiency of 99% or more.

To provide an iodine trapping apparatus capable of trapping organic iodine in a wide temperature range with high efficiency. The iodine trapping apparatus includes a first trapping agent 2 capable of trapping organic iodine in a gas in a nuclear power structure main body. The first trapping agent 2 contains a generating and trapping component which generates an iodide ion (I.sup.−) from organic iodine (RI) and traps the generated iodide ion, and a generating component which is different from the generating and trapping component, generates an iodide ion from the organic iodine at least at 100° C. to 130° C., and traps the generated iodide ion in the generating and trapping component.

To provide an iodine trapping apparatus capable of trapping organic iodine in a wide temperature range with high efficiency. The iodine trapping apparatus includes a first trapping agent 2 capable of trapping organic iodine in a gas in a nuclear power structure main body. The first trapping agent 2 contains a generating and trapping component which generates an iodide ion (I.sup.−) from organic iodine (RI) and traps the generated iodide ion, and a generating component which is different from the generating and trapping component, generates an iodide ion from the organic iodine at least at 100° C. to 130° C., and traps the generated iodide ion in the generating and trapping component.

An inorganic material in a form of open-porosity particles, each of the particles comprising a lead vanadate or phosphovanadate of formula Pb.sub.3-xX.sub.x(VO.sub.4)2.sub.-2y(PO.sub.4)2.sub.y,wherein x = 0 or x > 0 but ≤ 0.33; y = 0 or y > 0 but < 1;X = Ba.sup.2+, Ca.sup.2+, Sr.sup.2+ or Cd.sup.2+; and metallic lead or a lead salt. A method for preparing the material, a method for capturing iodine present in a gaseous effluent as well as a method for conditioning iodine present in a gaseous effluent in a form of an iodoapatite.

An inorganic material in a form of open-porosity particles, each of the particles comprising a lead vanadate or phosphovanadate of formula Pb.sub.3-xX.sub.x(VO.sub.4)2.sub.-2y(PO.sub.4)2.sub.y,wherein x = 0 or x > 0 but ≤ 0.33; y = 0 or y > 0 but < 1;X = Ba.sup.2+, Ca.sup.2+, Sr.sup.2+ or Cd.sup.2+; and metallic lead or a lead salt. A method for preparing the material, a method for capturing iodine present in a gaseous effluent as well as a method for conditioning iodine present in a gaseous effluent in a form of an iodoapatite.

Systems and methods that facilitate the transmutation of long-lived radioactive transuranic waste into short-live radioactive nuclides or stable nuclides using pre-pulse lasers to irradiate carbon nanotubes (CNTs) saturated with tritium into ionized gas of carbon and tritium and a laser-driven particle beam to fuse with the tritium and generate neutrons.