タグ「liquid」
Author: V.N. Epimakhov, M.C. Oleinik, S.V. Glushkov, T.V. Epimakhov
Reference: Patent, 05.05.2004, Sosnovyi Bor patent holder: State enterprise scientific-research centre of technology named after A.P. Aleksandrov
Keywords: liquid waste, neutralization, filter, ion exchange
Abstract: The invention relates to treatment of liquid radioactive wastes. For the current neutralizing method mechanical filter and ultrafilter is utilized. Subsequently conducted desalination through reverse osmosis filter, with advanced treatment on ion-exchange filters, with reagent treatment of spent ion-exchange resins, potassium ferrocyanide and cobalt salts. Then, the treated resin is used as sorption prefilter, in which waste treatment is conducted, before inputting it into the ion-exchange filter.
URL: http://www.findpatent.ru/patent/226/2267176.html
Author: V.I. Tikhonov, V.K. Kapustin, P.N. Moskalev
Reference: Patent, 27.08.2008, Gatchina patent holder: B.P. Konstantinov Institute of nuclear physics, St. Petersburg RAS
Keywords: liquid waste, fixation
Abstract: The invention relates to treatment of liquid radioactive waste. Long-lived radionuclides are emitted from nitric acid solution of spent nuclear fuel to a solid phase, in form of acetates, oxides or other compounds, which do not contain strongly activated neutron elements. Then, the radionuclides are imputed and fixed into carbon matrix.
URL: http://www.findpatent.ru/patent/234/2343575.html
Author: A.K. Andrianov, B.A. Gusev, V.V Krivobokov
Reference: Patent, 29.01.2007, Sosnovyi Bor patent holder: State enterprise scientific-research centre of technology named after A.P. Aleksandrov
Keywords: liquid waste, solidification, phosphor
Abstract: The invention relates to treatment of liquid radioactive waste, namely to methods of concentrating the waste by evaporation (thermal distillation) and solidifying of radioactive concentrates. During the treatment, salt solution is evaporated at a given temperature and pH of the solution. After gaining salt concentrate in the evaporated solution, close to saturation, the evaporation is conducted in phosphoric acid medium, at 150~1870g/l of concentration of phosphoric acid and temperature of 105~130℃. The concentrated salt is solidified by phosphate binders.
URL: http://www.findpatent.ru/patent/233/2336584.html
Author: E.P. Larin, V.N. Chvatov, A.G. Petrov, A.V. Soldatkin, S.V. Gribanenkov
Reference: Patent, 27.01.1999, Sosnovyi Bor patent holder: State enterprise Leningrad Nuclear Power Plant named after V.I. Lenin
Keywords: liquid waste, treatment, potassium cobalt ferrocyanide
Abstract: The present invention relates to the field of disposal of radioactive waste from nuclear plants, in particular to radioactive waste liquid. The method consists of heating the oil, of alkaline potassium permanganate, and ferrocyanide collector to 80oC, in volume ratio of the two being 0.5:5:0 (collector:oil), with formation of coagulant and subsequent separation of radioactive sludge. As ferrocyanide collector, 1. potassium cobalt ferrocyanide or 2. mixture of potassium nickel ferrocyanide and potassium cobalt ferrocyanide can be used.
URL: http://www.findpatent.ru/patent/212/2125745.html
Author: O.M. Slyunchev, D.E. Rezchikov
Reference: Patent, 27.10.2004, Ozersk patent holder: Mayak Production Association
Keywords: liquid waste, treatment, evaporation
Abstract: The invention relate to treatment of liquid radioactive wastes. The method consists of preliminary evaporation of the solution with obtainment of regenerated nitric acid and distillation residue. Then, neutralization of the distillation residue to pH1~2, and partial reduction of ferric iron, using sodium sulfite, to mixed valence state of Fe3+:Fe2+=2:1, are conducted.
URL: http://www.findpatent.ru/patent/225/2257626.html
Author: A.G. Anshits, T.A. Vereshagina, E.N. Voskresenskaya, E.M. Kostin, V.F. Pavlov, Yu.A. Revenko, A.A. Tretyakov, O.M. Sharonova, A.S. Aloi, N.V. Sapozhnikova, D.A. Knecht, T.D. Trenter, E. Macheret
Reference: Patent, 10.10.2002, Krasnoyarsk patent holder: Institute of chemistry and chemical technology (RAS), Mining and chemical combine, V.G. Khlopin Radium Institute
Keywords: liquid waste, solidification
Abstract: Summary of invention: for solidification of liquid radioactive wastes, porous glass-ceramic blocks are applied, which is formed from hollow glass-ceramic microsphere, extracted from the fly ash from combustion of fossil fuels. The block operates as a sponge and is characterized by a high value of open porosity of uniform pore structure.
URL: http://www.findpatent.ru/patent/219/2190890.html
Author: G.V. Beklemyshev, V.M. Kondakov, V.G. Balakhonov, V.S. Zagumennov, S.G. Sulima, G.G. Shadrin, S.A. Zhitkov
Reference: Patent, 13.09.2004, Seversk patent holder: Siberian chemical combine
Keywords: liquid waste, deactivation
Abstract: The invention relates to deactivation of liquid radioactive waste. It consists of alkaline deposition, in the presence of calcium and / or magnesium and phosphate ion, and the separation of the precipitate. The process is conducted in sequential deposition in two stages at a constant pH level of: 4-5 in the first stage and 7-9 in the second. Advantages of the invention are the increase of degree of purification and the reduce of reagent consumption.
URL: http://www.findpatent.ru/patent/227/2276415.html
Author: V.N. Epimakhov, M.S. Oleinik, T.V. Epimakhov, V.V. Trofimov
Reference: Patent, 01.12.2009 patent holder: State enterprise scientific-research centre of technology named after A.P. Aleksandrov
Keywords: liquid waste, cementing
Abstract: The invention relates to treatment of liquid radioactive waste. In a container, with non-radioactive cement compound, which plays the role of radiation shield, a filter with selective sorbent is installed. After establishing the resource of the filter, which is not aimed to be regenerated, with protection (filter-container) on disposal through the filter with selective sorbents, a thin Portland-cement slurry, with water cement ration not less than 10 percent, is pumped for cementing the monolith of the exhausted sorbent.
URL: http://www.findpatent.ru/patent/241/2410779.html
Author: V.A. Avramenko, E.V. Kaplun, T.A. Sokolnitskaya, V.V. Zhelezov, A.A. Yukhkam, S.Yu. Bratskaya
Reference: Patent, 20.07.2002, Vladivostok patent holder: State institution- Institute of Chemistry, Far Eastern Branch of Russian Academy of Sciences
Keywords: strontium, aqueous solution, removal
Abstract: The invention relates to methods of cleaning solutions using sorption of radioactive strontium, and can be used for extraction of radionuclides strontium from solutions with high content of hardness salts and liquid radioactive wastes with complex chemical composition. The method consists of a joint process of sorption and coprecipitation of strontium on sorption-reagent materials.
URL: http://www.findpatent.ru/patent/218/2185671.html
Author: S.A. Dmitriev, D.A. Fyodorov, A.E. Savkin, Yu.V. Karlin
Reference: Patent, 19.03.2007, Moscow, patent holder: Moscow State Enterprise – Joint Environmental-Technological Research Center for the disposal of radioactive waste and the protection of the environment (SIA “Radon”)
Keywords: liquid waste, process, filtration
Abstract: The invention relates to environmental protection, in detail, to process of liquid radioactive wastes. The original flow of the liquid waste is subjected to be defended by the formation of supernatant liquid and sludge. The supernatant fluid is clarified with a mechanical filter to form a filtrate; the filtrate is subjected to ion-selective sorption after deep desalting in two stages.
URL: http://www.findpatent.ru/patent/234/2342720.html
