Techniques for storing nuclear waste hazardous material include identifying a storage area of a directional wellbore formed from a terranean surface and extending into a subterranean formation; circulating a slurry that includes a hardenable material and one or more portions of nuclear waste hazardous material into the storage area; forming a seal in the directional wellbore that isolates the storage area of the directional wellbore from an entry of the directional wellbore; monitoring at least one variable associated with the one or more portions of nuclear waste hazardous material from a sensor positioned proximate the storage area; recording the monitored variable at the terranean surface; and based on the monitored variable exceeding a threshold value, removing the seal from the wellbore and retrieving at least a portion of the slurry from the storage area to the terranean surface.

Systems and methods for long-term disposal of radioactive or nuclear waste materials, in liquid, solid, and/or other physical forms, into human-made caverns, within deep geologic rock formations, derived from a wellbore, are manufactured by use of drilling and reaming technologies. The radioactive waste may be preprocessed from original surface storage site(s), transported, temporarily surface stored, and then finally further processed at a selected well site before injection into the subterranean deep human-made caverns within the host rock (deep geologic rock formations).

A continuous bubbling fluid bed process converts biomass feedstocks into energy/heat, engineered biochar particles (including nanoparticles) and a vapor stream of organic compounds. The products have a multitude of applications determined by the specific conditions at which the process was operated, specifically controlling: temperature, catalysts, residence time, element and compound concentrations, and withdraw of products from various points in the system. The introduction of air, steam, and various gases into the vessel at selected locations and at controlled rates enables the economic, dependable and consistent production of these products.

A cement solidification device for waste includes a slurrying vessel 14 that dissolves and slurries waste 11 containing harmful substances and deliquescent compounds in solvent water 12 to obtain slurried material 13; an iron-based additive supply unit 16 that adds an iron-based additive 15 to the slurrying vessel 14; a cement kneading vessel 20 that adds a cement solidifying agent 17 from a cement-solidifying agent supply unit 18 to the slurried material 13 in which the iron-based additive 15 is mixed to obtain a cement kneaded product 19; and a cement solidification unit 22 that cures the cement kneaded product 19 to form a cement solidified product 21.

Systems and methods for long-term disposal of radioactive or nuclear waste materials, in liquid, solid, and/or other physical forms, into human-made caverns, within deep geologic rock formations, derived from a wellbore, are manufactured by use of drilling and reaming technologies. The radioactive waste may be preprocessed from original surface storage site(s), transported, temporarily surface stored, and then finally further processed at a selected well site before injection into the subterranean deep human-made caverns within the host rock (deep geologic rock formations).

Mineralogical method and apparatus for removal of cesium ion in aqueous solution are provided. In particular, a mineralogical method for removal of cesium ion in aqueous solution including controlling a temperature of radioactive wastewater containing cesium from 25 to 45 C., controlling an initial pH of the radioactive wastewater from 6.0 to 8.5, and adding iron(II) and sulfide(II) containing sulfur in the 2 oxidation state to the radioactive wastewater, to convert the cesium ion in aqueous solution into a cesium mineral, and a mineralogical apparatus for removal of cesium ion in aqueous solution, capable of being applied to such a method, are provided.

A process for immobilizing hazardous waste includes mixing the hazardous waste with a non-swelling clay, a cementitious binder and, optionally, water, and allowing the resulting mixture to set to an immobilized waste material. The process can also include dispersing the hazardous waste in the non-swelling clay to form a dry mixture, mixing the cementitious binder and, optionally, water with the dry mixture to produce a plastic mixture, and allowing the plastic mixture to set to the immobilized waste material.

A hazardous material storage bank includes a wellbore extending into the Earth and including an entry at least proximate a terranean surface, the wellbore including a substantially vertical portion, a transition portion, and a substantially horizontal portion; a storage area coupled to the substantially horizontal portion of the well bore, the storage area within or below a shale formation, the storage area vertically isolated, by the shale formation, from a subterranean zone that includes mobile water; a storage container positioned in the storage area, the storage container sized to fit from the wellbore entry through the substantially vertical, the transition, and the substantially horizontal portions of the wellbore, and into the storage area, the storage container including an inner cavity sized enclose hazardous material; and a seal positioned in the wellbore, the seal isolating the storage portion of the wellbore from the entry of the wellbore.

The invention relates to means for protecting the environment from the consequences of fires complicated by a radiation factor. A composition for dust suppression and containment of radioactive products of combustion after a fire with a radiation factor has been extinguished comprises, as a surfactant, a mixture of an anionic, a non-ionic and an amphoteric surfactant, and has the following ratio of components: 3.0-7.0% by weight of an aqueous solution of polyvinyl alcohol (in terms of a mass fraction of dry product); 0.1-0.3% by weight of plasticizer; 11.0-29.0% by weight of surfactant; with water making up the remainder. The invention makes it possible to carry out dust suppression and containment of radioactive products of combustion which are formed on surfaces, including at elevated temperatures, after a fire has been extinguished.

Provided are a silicotitanate molded body having high strength and reduced generation of fine powder, a production method thereof, an adsorbent comprising the silicotitanate molded body, and a decontamination method of radioactive cesium and/or radioactive strontium by using the adsorbent. The silicotitanate molded body comprises: crystalline silicotitanate particles that have a particle size distribution in which 90% or more, on volume basis, of the particles have a particle size within a range of 1 m or more and 10 m or less and that are represented by a general formula of A.sub.2Ti.sub.2O.sub.3(SiO.sub.4).nH.sub.2O wherein A represents one or two alkali metal elements selected from Na and K, and n represents a number of 0 to 2; and an oxide of one or more elements selected from the group consisting of aluminum, zirconium, iron, and cerium.