EDN: HQVFFV
Authors & Affiliations
Smykov V. B., Legkikh K.G., Trifanova E.M., Grushicheva E.A.
A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia
Smykov V.B. – Head of Direction, Cand. Sci. (Tech.)
Legkikh K.G. – Head of Laboratory. Contacts: 1, pl. Bondarenko, Obninsk, Kaluga region, Russia, 249033. Tel.: +7 (484) 399-70-00 (доб. 88-03); e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Trifanova E.M. – Leading Research Engineer.
Grushiueva E.A. – Leading Research Engineer.
Abstract
Decommissioning of any facility for the use of atomic energy (OUAE) is an integral part of its “life cycle” and makes a significant contribution to ensuring the radiation safety of this facility. The decommissioning of the plant in accordance with paragraph 7 of FZ-170 “On the use of nuclear energy” should be worked out at the stage of making a decision on the creation of an OUAE and presented as part of the design documentation and in the SJR.
The BR-10 research reactor is a testing ground for the development of technologies for decommissioning FS-type reactor installations. A method of solid-phase oxidation using copper-smelting slag has been developed for the processing of impaled silk liquid metal carrier. To date, the solid-phase oxidation method developed at BR-10 has converted more than 12 m3 of purified sodium into a fire-explosion-proof state. However, the final product of the application of the RW immobilization technology must meet the criteria of acceptability for burial. One of such criteria for shvak-like compounds is the rate of leaching. It is recommended to determine the rate of leaching of radionuclides from the form of radioactive waste taking into account GOST R 52126-2003. The article describes the problems of processing spent alkaline liquid metal (ALM) coolant in BN-type reactors and the methods of their solution. The methods of processing ALM coolant and its nondrainable residues, used in the BR-10 research reactor (IPPE JSC, Obninsk) are described in detail. The main parameters of solidified products are given, namely, their mechanical strength and caesium-137 leaching rate. A comparative analysis of the obtained data has been performed with the indicators of cement compounds in the alkaline solution obtained by dissolving radioactive sodium with 10 % alkali.
Keywords
solid-phase oxidation, (SPO), silk liquid metal carrier, research reactor BR-10, fast reactors with sodium coolant, 137Cs isotope leaching rate, SPO product porosity, SPO product mechanical strength
Article Text (PDF, in Russian)
References
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UDC 621.181.6
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2025, no. 1, 1:19
