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Galkin, A.; Tkachenko, V.
Abstracts of 2.Eurasian Conference on Nuclear Science and its Application2002
Abstracts of 2.Eurasian Conference on Nuclear Science and its Application2002
AbstractAbstract
[en] Pursuant of modern concept on radioactive waste management applied in IAEA Member States all radioactive wastes produced during the BN-350 operation and decommissioning are subject to processing in order to be transformed to a form suitable for long-term storage and final disposal. The first two priority objectives for BN-350 reactor are as follows: cesium cleaning from sodium followed by sodium drain, and processing; processing of liquid and solid radioactive waste accumulated during BN-350 operation. Cesium cleaning from sodium and sodium processing to NaOH will be implemented under USA engineering and financial support. However the outputted product might be only subject to temporary storage under special conditions. Currently the problem is being solved on selection of technology for sodium hydroxide conversion to final product incorporated into cement-like matrix ready for disposal pursuant to existing regulatory requirements. Industrial installation is being designed for liquid radioactive waste processing followed by incorporation to cement matrix subject to further disposal. The next general objective is management of radioactive waste expected from BN-350 decommissioning procedure. Complex of engineering-radiation investigation that is being conducted at BN-350 site will provide estimation of solid and liquid radioactive waste that will be produced during the course of the BN-350 decommission. Radioactive wastes that will be produced may be shared for primary (metal structures of both reactor and reactor plant main and auxiliary systems equipment as well as construction wastes of dismantled biological protection, buildings and structures) and secondary (deactivation solutions, tools, materials, cloth, special accessory, etc.). Processing of produced radioactive wastes (including high activity waste) requires the use of special industrial facilities and construction of special buildings and structures for arrangement of facilities mentioned as well as for storage of packed wastes. Currently the preliminary feasibility study is completed that concerns to construction in Mangystau region (close to BN-350 reactor plant) of special processing plant and disposal facility. Construction of radioactive waste processing plant and disposal facility should become the timely measure for solution of many problems on radioactive waste management. The number of other objectives are also being solved: Criteria development for radioactive waste classification; Substantiation of criteria limiting values for exemption from radiation account for material produced during decommissioning; Development of principles and methods for control of equipment, materials and wastes for reuse; Development of scenarios for reuse of materials, which would not induce the socially unacceptable exposure dose for population
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Source
Ministry of Energy and Mineral Resources of the Republic of Kazakhstan, Astana (Kazakhstan); Atomic Energy Committee of the Republic of Kazakhstan, Almaty (Kazakhstan); Inst. of Nuclear Physics, Almaty (Kazakhstan); Nuclear Society of the Republic of Kazakhstan, Almaty (Kazakhstan); Engineering Academy of the Republic of Kazakhstan, Almaty (Kazakhstan); 482 p; ISBN 9185-2-X;
; 2002; p. 30-31; 2. Eurasian Conference on Nuclear Science and its Application; 2.Eurasian Conference on Nuclear Science and its Application; Almaty (Kazakhstan); 16-19 Oct 2002

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Book
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Conference
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BREEDER REACTORS, DECOMMISSIONING, DESALINATION REACTORS, EPITHERMAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, INDUSTRIAL PLANTS, LIQUID METAL COOLED REACTORS, LMFBR TYPE REACTORS, MANAGEMENT, NUCLEAR FACILITIES, POWER REACTORS, RADIOACTIVE WASTE MANAGEMENT, REACTORS, SODIUM COOLED REACTORS, WASTE DISPOSAL, WASTE MANAGEMENT
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