タグ「radioactive waste disposal」
Title: Aspects of storage and disposal of nuclear materials (waste)
Author: Komleva, Elena Vladimirovna
Reference: Journal: Jurisprudence, Year: 2012 Issue: 1
Keywords: nuclear energy, hydrocarbons, nuclear waste, international depositories, nickel, the SAMPO image
Abstract: This paper presents further consideration of the following interrelation in the energy production sphere: oil and gas business and international projects on the long-term storage of nuclear materials. There are discussed some Russian versions of construction of nuclear depositories as well as corresponding geological assessments. In particular, for the North-West Russia.
URL:http://cyberleninka.ru/article/n/aspekty-hraneniya-i-zahoroneniya-yadernyh-materialov
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: A.I. Egorov, B.Ya. Galkin, R.I. Lyubets, V.Ya Mishin, V.K. Isupov, G.N. Popova
Reference: Patent, 10.07.2000, Gatchina patent holder: B.P. Konstantinov Institute of nuclear physics, St. Petersburg RAS, V.G. Khlopin Radium Institute
Keywords: zirconium, treatment, extraction, reactor
Abstract: The invention relates to retrieving of zirconium from shell of fuel elements and other parts, exposed to zirconium, of a nuclear reactor, providing also a method of treatment of zirconium before its reuse. The Method includes operations of dissolving alloy, zirconium extraction into an organic solvent, and re-extraction of the purified zirconium and its precipitation from aqueous phase. The operation is conducted under temperature of 100~130℃. The components of the solution are the following: HNO3: 300-800kg/m3, K2Zr (Hf) F6: 5-32 kg/m3, water.
URL: http://www.findpatent.ru/patent/215/2152651.html
Author: D.W. Awkers
Reference: U.S. Nuclear Regulatory commission, 2002
Keywords: decontamination, ion exchange resin, extraction
Abstract: As part of a study being performed for the Nuclear Regulatory Commission (NRC), small-scale waste specimens were collected following an AP/CAN-DEREM full-system decontamination of the reactor vessel of the Indian Point 2 reactor vessel in March 1995. CAN-DEREM is a modified version of a reduction process developed by Atomic Energy of Canada Ltd. for that country’s heavy-water CANDU reactors. The INEEL research was undertaken to support licensing needs for reviewing radiological and chemical data and information to address uncertainties associated with disposal of low-level radioactive decontamination waste in performance assessment modeling. This report presents information on radionuclide and chelate characteristics of decontamination radwaste on ion-exchange resins. The information is expected to reduce uncertainties associated with developing radionuclide inventories for the performance assessment.
URL: http://www.nrc.gov/reading-rm/doc-collections/nuregs/contract/cr6766/cr6766.pdf
Author: E.P. Emets, L.A. Mamaev, P.P. Poluetkov, A.B. Ozolin, V.P. Stelmachuk, S.L. Khrabrov
Reference: Patent, 10.09.2003, Moscow patent holder: All-Russian research institute of inorganic materials named after A.A. Bochvar
Keywords: metal, decontamination, monobath method, nitric acid
Abstract: The invention relates to nuclear technology, namely to decontamination of radioactively contaminated metals. The cleaning composition consists of: nitric acid (15.0~25.0%), sulfamic acid (0.1~4.0%), hydrofluoric acid (0.5~2.0%) and water (the rest). The method allows to implement monobath method of decontamination, in low temperature, which greatly simplifies the technical process, and it reduces the quantity of liquid waste by conducting effective decontamination.
URL: http://www.findpatent.ru/patent/221/2212073.html
Author: Yu.P. Kudryavsky, Yu.A. Ryaposov, O.V. Rakhimova I.N. Lipunov, A.S. Teplounov, S.A. Onorin, M.V. Zilberman, N.K. Zhulanov, I.Yu. Eremin, N.I. Polezhaev, A.I. Medvedev
Reference: Patent, 28.04.2003, Berezniki paten holder: Research-production environmental company “Eco-technology”
Keywords: radioactive waste, decontamination
Abstract: The invention relates to chemical technology, namely to technology of nonorganic materials. It can be used for deactivation and decontamination of radioactive waste, from industries, containing Th-232 and daughter products of its decay (Ra-228, Ra-224), as well as REM, Fe, Cr, Mn, Al, Ti, Zr, Nb, Ta, Ca, Mg, Na, K, etc. The method contains dissolving of the waste, process of solutions or slurry of barium chloride, with acid and lime milk, and separation of precipitate from the solution.
URL: http://www.findpatent.ru/patent/224/2246772.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: 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
