Composition, manufactures, and methods of making and using them, illustratively a process including the steps of: changing density of a composition including a neutron absorbent, the absorbent having a neutron absorption cross section greater than or equal to Boron comprising at least 19.7% of Boron-10 isotope, and a thermal conductor having a thermal conductivity of at least 10% of coolant thermal conductivity at 100 degrees C. at sea level, combined into the particles that have a density of at least 0.9982 g/mL and not more than 2.0 g/ml, the altering carried out in association with nuclear fuel or nuclear waste in a cask that is not located in a nuclear reactor containment vessel, the cask being a nuclear fuel cask or a spent nuclear fuel cask, the changing carried out by relocating the composition by at least one of the sub steps comprising: (A) operating a hollow conduit connected to a reservoir to relocate at least some of the particles from a reservoir into the cask, and/or (B) altering a close pack formation of the particles by effectuating a change from a static coefficient of friction of the particles to a dynamic coefficient of friction of the particles, thereby redistributing the particles within the cask into an altered close pack formation, and/or (C) removing at least some of the particles from the cask into the reservoir.

A method includes: a pre-treatment step of mixing radiocontaminated grains and a sodium phosphate-based dispersant; and a decontamination step of mixing the radiocontaminated grains processed by the pre-treatment step and paper sludge-derived sintered carbonized porous grains so as to incorporate radioactive .sup.134Cs and .sup.137Cs of the radiocontaminated grains in the sintered carbonized porous grains.

A container for storage of molten material from an industrial facility, and method of manufacture thereof, is provided to maximize internal volume of the container while providing structural stability. The container includes walls having rounded convex-shaped edges at each wall junction. A first head is connected to the walls at a first end of the container, and a second head closes the second end of the container. The second head is connected to the walls at a second end of the container. Corners are defined at the intersection of the walls with the first head and second head at the first end and the second end respectively. A first flange is connected to the first head to receive molten material, and the first head is shaped as a tapered shoulder to smoothly transition from the first flange to the junction of the walls.

The invention relates to the field of environmental protection, more specifically to the field of processing radioactive waste, and can he used for the safe and effective handling of a large quantity of liquid radioactive waste of various activity levels that has been formed as the result of decontaminating protective equipment of boxes and chambers, and makes it possible to decrease the volume of stored waste by solidifying same and incorporating same into a ceramic matrix. For this purpose, radioactive solutions after decontamination of surfaces of protective equipment are evaporated as alkaline and acidic solutions containing sodium hydroxide, potassium permanganate, oxalic acid, and nitric acid until a solid residue forms, and are calcined, and the calcinate is mixed with components of a fusion mixture containing oxides of titanium, calcium, iron (III), zirconium, and manganese (IV) and aluminum in a specified ratio, and fused.

According to one aspect of the invention, a method to create a ceramic waste form from used nuclear fuel. An active metal salt waste, a rare earth metal waste, and raw materials are received. The active metal salt waste is combined with the rare earth metal waste, forming a waste salt. The waste salt is then heated to approximately 500 C. The raw materials are also heated to approximately 500 C. The waste salt and raw materials are then blended to form a homogenous waste mixture. The homogenous waste mixture is heated to a first predetermined temperature for a predetermined amount of time, creating a ceramic waste form. The ceramic waste form is cooled to a second predetermined temperature.

According to one aspect of the invention, a method to create a ceramic waste form from used nuclear fuel. An active metal salt waste, a rare earth metal waste, and raw materials are received. The active metal salt waste is combined with the rare earth metal waste, forming a waste salt. The waste salt is then heated to approximately 500 C. The raw materials are also heated to approximately 500 C. The waste salt and raw materials are then blended to form a homogenous waste mixture. The homogenous waste mixture is heated to a first predetermined temperature for a predetermined amount of time, creating a ceramic waste form. The ceramic waste form is cooled to a second predetermined temperature.

The invention relates to the field of environmental protection, more specifically to the field of processing radioactive waste, and can he used for the safe and effective handling of a large quantity of liquid radioactive waste of various activity levels that has been formed as the result of decontaminating protective equipment of boxes and chambers, and makes it possible to decrease the volume of stored waste by solidifying same and incorporating same into a ceramic matrix. For this purpose, radioactive solutions after decontamination of surfaces of protective equipment are evaporated as alkaline and acidic solutions containing sodium hydroxide, potassium permanganate, oxalic acid, and nitric acid until a solid residue forms, and are calcined, and the calcinate is mixed with components of a fusion mixture containing oxides of titanium, calcium, iron (III), zirconium, and manganese (IV) and aluminum in a specified ratio, and fused.

The invention relates to a method for producing a solid nanocomposite material comprising nanoparticles of a metal coordination polymer with ligands CN, said nanoparticles satisfying the formula [Alk.sup.+.sub.x]M.sup.n+[M(CN).sub.m].sup.z? where Alk is an alkali metal, x is 1 or 2, M is a transition metal, n is 2 or 3, M is a transition metal, m is 6 or 8, and z is 3 or 4; said M.sup.n+ cations of the coordination polymer being bound by an organometallic bond or a coordination bond to an organic group R2 of an organic graft, and said organic graft furthermore being chemically attached, preferably by a covalent bond, to at least one surface of a solid support, by reaction of a group R1 of said graft with said surface.

Nuclear waste, such as, but not limited to, spent nuclear fuel (SNF) assemblies or portions thereof, are chipped and compacted into (waste) pucks that are placed within diecast molds, and then diecast injection molding occurs within the diecast molds and around the pucks that are emplaced within those diecast molds, with injected molten alloy(s), to form solid metal ingots upon sufficient cooling after the diecasting injection that contain within the ingots the emplaced pucks. The molten alloy(s) may contain a copper alloy. The molten alloy(s) may also contain neutron absorbers. The ingots may be placed into waste capsules. The ingots and/or the waste capsules may be landed in deeply located horizontal wellbores. The deeply located horizontal wellbores may be at least partially located within deeply located geologic formations.

Nuclear waste, such as, but not limited to, spent nuclear fuel (SNF) assemblies or portions thereof, are placed within diecast molds, and then diecast injection molding occurs within the diecast molds and around the SNF assemblies or portions thereof that are emplaced within those diecast molds, with injected molten alloy(s), to form solid metal ingots upon sufficient cooling after the injection that contain within the ingots the emplaced SNF assemblies or portions thereof. The molten alloy(s) may contain a copper alloy. The molten alloy(s) may also contain neutron absorbers. The ingots may be placed into waste capsules. The ingots and/or the waste capsules may be landed in deeply located horizontal wellbores. The deeply located horizontal wellbores may be at least partially located within deeply located geologic formations.