Radiation detectors and methods of using the radiation detectors that provide a route for surface decontamination during use are described. The detectors utilize light illumination of an internal surface during use. Light is in the longer UV to near-infrared spectra and desorbs contamination from internal surfaces of radiation detectors. The methods can be carried out while the detectors are in operation, preventing the appearance of the negative effects of radioactive and non-radioactive contamination during a detection regime and following a detection regime.

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 a method for decontaminating a radioactively contaminated metal surface, wherein the metal surface is brought in contact with a decontamination solution, which comprises a complexing agent and a transition metal. The invention further relates to such a decontamination solution and to the use thereof to decontaminate a metal surface.

According to the present invention, a method which dissolves hydrogen in a liquid that includes a radioactive substance is able to reduce the amount of radioactivity of the liquid. With respect to this method, the radioactive substance may include radioactive cesium, and hydrogen may be dissolved in the liquid by mixing a substance that contains a radioactive substance with a hydrogen water that contains 1.0 ppm or more of hydrogen.

A chemical decontamination method includes a dissolution step in which a radioactive insoluble substance containing a metal oxide, the radioactive insoluble substance being adhered to a decontamination object including carbon steel, is dissolved in a decontamination solution and a metal-ion removal step in which the decontamination solution containing the metal ion, the decontamination solution being produced in the dissolution step, is brought into contact with a cation-exchange resin in order to remove the metal ion, the dissolution step including a reductive dissolution step conducted using a decontamination solution containing formic acid, ascorbic acid and/or erythorbic acid, and a corrosion inhibitor.

This geopolymer molding production method comprises: a mixing step (S1) for mixing a first material containing aluminum and silicon with a hydrate of an alkali stimulant containing a hydrate of an alkaline hydroxide and/or a hydrate of an alkaline silicate; a compaction step (S2) for compacting the mixture obtained in the mixing step (S1) into a compacted mixture; and a curing step (S3) for curing the compacted mixture.

A nuclear fusion system comprises: a muon generation unit to generate negative muons including electron and positron accelerators for generating electron and positron beams; a gas supply unit to supply to circulate gaseous deuterium or gaseous deuterium-tritium mixture as raw material gas; a Laval nozzle to accelerate the raw material gas to supersonic velocity; and a shock wave cone connected to the Laval nozzle to introduce the raw material gas accelerated to supersonic velocity to generate an oblique shock wave, the raw material gas accelerated to supersonic velocity being introduced into the shock wave cone to generate the oblique shock wave, the oblique shock wave being decelerated to create a high-density gas target in an in-flight manner, the muons generated as a result of causing electrons and positrons to collide with each other being introduced into the high-density gas target thereby to cause a muon-catalyzed nuclear fusion reaction to occur.

Provided is a chemical decontamination method that shortens the decomposition time of a reduction decontamination agent. An oxidization decontamination, a decomposition of an oxidization decontamination agent, and reduction decontamination using an oxalic acid aqueous solution are performed on a target piping of a BWR plant. After that, the oxalic acid is decomposed (S7). That is, a part of the oxalic acid is decomposed by irradiating the oxalic acid aqueous solution with ultraviolet rays upstream of a decomposition device (S8), and Fe.sup.3+ in the aqueous solution is converted to Fe.sup.2+. Hydrogen peroxide is supplied to the decomposition device (S9). In the decomposition device, the oxalic acid is decomposed by a catalyst and hydrogen peroxide, Fe.sup.2+ and hydrogen peroxide react to produce Fe.sup.3+ and OH*, and the oxalic acid is decomposed by OH*. A corrosion potential of the aqueous solution flowing out from the decomposition device is measured (S11). A concentration ratio calculation device obtains Fe.sup.3+/Fe.sup.2+ (concentration ratio) based on the corrosion potential (S12), and A control device controls the supply amount of hydrogen peroxide to the decomposition device based on Fe.sup.3+/Fe.sup.2+ (S14 and S16).).

A waste liquid treatment facility according to an exemplary embodiment of the present invention includes: a filter connected to a system of a nuclear power plant; a demineralizer connected to the filter; a reactor connected to the demineralizer and including a first lamp and a second lamp of different wavelengths connected in succession; a buffer tank connected to the filter, demineralizer, and reactor; and a circulation pipe portion connecting the filter, demineralizer, reactor, and buffer tank to form a circulation structure of a solution together with the system, wherein the solution sequentially passes through the first lamp and the second lamp.

A single integrated system for recycling used nuclear fuel (UNF) emerging from a reactor has a decladding vessel separating fuel pellets from nuclear fuel rods via oxidation to produce U.sub.3O.sub.8. A fluorination vessel is coupled to the decladding vessel to remove hexafluorides from the U.sub.3O.sub.8 produced by the decladding vessel. An electrowinning vessel is coupled to the fluorination vessel removing plutonium and actinides via electrowinning.