AbstractAbstract
[en] Decomposition of organic compounds contained in the spent ion exchange resins is considered effective in reducing the waste volume. A system using the wet-oxidation process has been studied for the treatment of the spent resins stored at Trino Nuclear Power Plant owned by SOGIN. Compared with various processes for treating sludge and resin, the wet-oxidation system is rather simple and the process conditions are mild. Not contaminated ion exchange resin samples similar to those ones used in Trino NPP were processed by wet-oxidation and appropriate decomposition of the organic compounds was verified. After decomposition the residue can be solidified with cement for final disposal. When compared with direct solidification without decomposition, the number of waste packages can be significantly reduced. Additional measures for conditioning secondary waste products have also been studied, and their applicability to the Trino Nuclear Power Plant was verified. Some of conditions studied were specific to the Trino Nuclear Power Plant, but it is expected that the system will provide an effective solution for resin treatment at other Italian NPPs. (authors)
Primary Subject
Source
Stiopol, Mihaela (ed.) (Romanian Nuclear Energy Association, AREN, Str. Atomistilor 111, PO Box 53, RO-76900 Bucharest - Magurele (Romania); Societatea Nationala 'Nuclearelectrica' S.A., Str. Polona, nr. 65, RO-010494 Bucharest (Romania)), E-mail: mstiopol@nuclearelectrica.ro; Romanian Nuclear Energy Association, AREN, Str. Atomistilor 111, PO Box 53, RO-76900 Bucharest -Magurele (Romania); Romanian Atomic Forum, ROMATOM, 65, Polona street, PO Box 22-102, 010494 Bucharest, sector 1 (Romania). Funding organisation: Romanian Nuclear Energy Association, AREN, Str. Atomistilor 111, PO Box 53, RO-76900 Bucharest -Magurele (Romania); European Nuclear Society, ENS, Belpstrasse 23, PO Box 5032, CH 3001Bern (Switzerland); Romanian Atomic Forum, ROMATOM, 65, Polona street, PO Box 22-102, 010494 Bucharest, sector 1 (Romania); 532 p; 2009; p. S2.147-S2.151; SIEN 2009: international symposium on nuclear energy. Nuclear power - a new challenge; Bucuresti (Romania); 12-16 Oct 2009; Available from author(s) or as a CD-ROM issued by Romanian Nuclear Energy Association, AREN, Str. Atomistilor 111, PO Box 53, RO-76900 Bucharest - Magurele (RO); Available as a CD-ROM from Romanian Nuclear Energy Association, AREN, Str. Atomistilor 111, PO Box 53, RO-76900 Bucharest - Magurele (RO); 3 figs.
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Multimedia
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Conference
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BUILDING MATERIALS, CHEMICAL REACTIONS, ENERGY SOURCES, ENRICHED URANIUM REACTORS, FUELS, MANAGEMENT, MATERIALS, NUCLEAR FUELS, ORGANIC COMPOUNDS, ORGANIC POLYMERS, PETROCHEMICALS, PETROLEUM PRODUCTS, PHASE TRANSFORMATIONS, POLYMERS, POWER REACTORS, PROCESSING, PWR TYPE REACTORS, RADIOACTIVE WASTE MANAGEMENT, REACTOR MATERIALS, REACTORS, THERMAL REACTORS, WASTE MANAGEMENT, WASTE PROCESSING, WATER COOLED REACTORS, WATER MODERATED REACTORS
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Botta, E.; Frepoli, C.; Scarsi, G.; Secolo, F.
CNE'96: National Energy Conference 'Improving Energy Efficiency in a Transition Economy'. Proceedings of Section IV: Nuclear Power1996
CNE'96: National Energy Conference 'Improving Energy Efficiency in a Transition Economy'. Proceedings of Section IV: Nuclear Power1996
AbstractAbstract
[en] The object of the current study is a Main Feed Water Pump (MFWP) miniflow control valve installed on Unit 1 of Cernavoda NPP. During feedwater system commissioning unexpected and severe pipe vibration and noise problems were experienced leading to valve stem break, thought as being due to hydrodynamic vibration generated by cavitation phenomena taking place inside the valve itself. The complex turbulent flow occurring in the valve has been simulated through the Computational Fluid Dynamic (CFD) methodology. Such valves are characterized by high pressure drops achieved by the particular design of the valve internals which originate an high speed swirling turbulent flow. The FLOW3D computer code has been employed to solve the velocity and pressure field in such complex 3D domain. The valve internals (plug and blades) are fully modeled as well as a significant portion of the discharge line. A grid size of 50,000 nodes and the K-Epsilon turbulence (isotropic turbulence) model has been used in the calculation. (author). 12 figs., 9 refs
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Secondary Subject
Source
Petrescu, M.; Balan, Gh.; Zlatanovici, D. (Centrul de Cercetari Energetice, RENEL - Str. Energeticienilor Nr.8, Sector 3, R-79619 Bucharest (Romania)); 198 p; 1996; p. 100-118; RENEL - Romanian Electricity Authority; Neptun-Olimp (Romania); CNE'96: National Energy Conference 'Improving Energy Efficiency in a Transition Economy'; Neptun-Olimp (Romania); 1-5 Sep 1996; Available from authors by request; Available from publishers
Record Type
Miscellaneous
Literature Type
Conference
Country of publication
CANDU TYPE REACTORS, COMPUTER CODES, CONTROL EQUIPMENT, EQUIPMENT, FAILURES, FLOW REGULATORS, HEAVY WATER COOLED REACTORS, HEAVY WATER MODERATED REACTORS, HYDROGEN COMPOUNDS, NATURAL URANIUM REACTORS, OXYGEN COMPOUNDS, PHWR TYPE REACTORS, POWER REACTORS, PRESSURE TUBE REACTORS, PUMPS, REACTORS, THERMAL REACTORS, WATER
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Bitetti, B.; Mantero, G.; Orlandi, S.; Scarsi, G.; Brusa, L.; Ruggeri, G.; Dionisi, M.; Farina, A.; Grossi, G.
International conference on safe decommissioning for nuclear activities: Assuring the safe termination of practices involving radioactive materials. Contributed papers2002
International conference on safe decommissioning for nuclear activities: Assuring the safe termination of practices involving radioactive materials. Contributed papers2002
AbstractAbstract
[en] The main objective of this study, promoted by ANPA, the Italian Nuclear Regulatory Body, carried out with ANSALDO and in close co-operation with SOGIN, was to define a methodology for the evaluation of the inventory of the amount of radioactive waste produced during the NPPs decommissioning activities, in terms of both volume and radioactivity content, and estimate the solid materials suitable for release from the regulatory control. The simulation code RainMan, developed within this project, allows, according to a selected scenario, for the evaluation of the solid materials that could be cleared and the volumes of the L-MLW that should be sent to a disposal facility. (author)
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International Atomic Energy Agency, Vienna (Austria); Bundesamt fuer Strahlenschutz (BfS) (Germany); 408 p; 2002; p. 138-143; International conference on safe decommissioning for nuclear activities: Assuring the safe termination of practices involving radioactive materials; Berlin (Germany); 14-18 Oct 2002; CN--93[25]; 1 fig., 3 tabs
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Report
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Conference
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