Patent classifications
G21F9/125
SYSTEM FOR DECONTAMINATING SOIL AND THE LIKE
An object to be decontaminated contaminated with radioactive material, e.g., contaminated soil or water, is introduced into eluting solvent and dissolved, and the radioactive material is separated from the object to be contaminated by elution of the radioactive material into the eluting solvent. The eluting solvent containing the radioactive materials dissolved therein and the object to be decontaminated are separated into solid and liquid. The soil after solid-liquid separation and from which the radioactive material is removed is collected, and the eluting solvent after solid-liquid separation and a separated liquid containing contaminated water are introduced into an electrolysis tank and electrolyzed. Metal ions such as those of the radioactive materials are deposited on the cathode in the electrolysis tank. Hydrogen containing tritium generated in electrolysis is collected in the electrolysis tank. The hydrogen is moved to the outside of the electrolysis tank and trapped.
Method and System for Removing Radioactive Nuclides from Water
The present invention concerns a method for the removal of radionuclides from water, wherein at least one absorption additive that has an absorptive effect on the nuclides and at least one filter device that is impermeable to the adsorption additive and the nuclides absorbed thereon are used. An improved removal rate is achieved with reduced equipment expenditure when an adsorption layer is formed from the adsorption additive on an inflow-side surface of the respective filter device.
METAL-ORGANIC CAGES, METHODS OF MAKING, AND METHODS OF USE THEREOF
The disclosure relates to metal-organic cages which are a class of supramolecular structures comprising organic linkers and transition metal nodes. In an aspect an aluminum-based metal-organic cage (AI-pdc-AA) is disclosed. The cage formation was achieved via solvothermal self-assembly of an aluminum cluster and pyridine-dicarboxylic linker in the presence of acetic acid as a capping agent. The obtained supramolecular structure was characterized by single-crystal X-ray diffraction (SCXRD), thermbgravimetric analysis, and NMR spectroscopies. Based on the single crystal structure and computational analysis, the cage has a 3.7 A diameter electrophilic cavity suitable for the binding of cations, such as cesium (ionic radius 1.81 A). The host-guest interactions were probed with 1 H and 133Cs NM spectroscopies in DMSO, where at low concentrations Cs+ binds to AI-pdc-AA in a 1:1 ratio.
Method for concentrating liquid radioactive waste
The present disclosure relates to nuclear chemical, particularly radiochemical, technologies at different stages of the nuclear fuel cycle, such as the production of purified nuclear materials (uranium, zirconium) or the reprocessing of spent nuclear fuel from nuclear power stations, in which extraction processes and operations for purifying nuclear materials are used. An example method, which includes the partial decomposition of nitric acid during continuous evaporation while a solution containing a reducing agent is fed into the bottom part of an evaporator having a circulating bottoms solution, consists in that the process is carried out such that the solution is kept in the bottom part of the evaporator for more than 2 hours under the addition of an aqueous solution of formaldehyde and formic acid (hereinafter the mixture) or a solution of formic acid after the process has been started using the mixture.
Method for the removal of radionuclides from aqueous radioactive waste
The present invention discloses a method for the separation of radionuclides from an aqueous radioactive waste solution, the method comprising: receiving of an aqueous radioactive waste solution, adding at least one zirconium salt to the aqueous radioactive waste solution, changing the pH of the radioactive waste solution to obtain a precipitate P, and separating the precipitate P from the radioactive waste solution. The present invention also discloses the use of zirconium salts, preferably zirconium oxychloride, zirconium nitrate or a zirconium oxynitrate or any mixture thereof, for the treatment of aqueous radioactive waste solution, preferably acidic or alkaline intermediate or low level radioactive waste solution, preferably an acidic intermediate and/or low level radioactive waste solution.