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Pochman, K.; Ruscak, M.; Brumovsky, M.
Proceedings of international topical meeting on VVER technical innovations for next century2000
Proceedings of international topical meeting on VVER technical innovations for next century2000
AbstractAbstract
[en] The program of lifetime management at NPP Dukovany is oriented towards an effective usage of facilities while keeping their safety parameters, mainly concerning nuclear safety. The goal is to achieve maximum usage of the design lifetime under the condition of fulfilling above mentioned requirements. Evaluation procedures have been prepared for selected components. These are subsequently discussed and approved by the State Office of Nuclear Safety. The databases of original data are built up regarding the evaluated components. The input data are completed as well according to the approved procedures. Generally valid approaches based on the evaluation of all possible degradation mechanisms are modified regarding the original status of particular component. The procedures are oriented towards a quantification of residual lifetime. They employ knowledge of initiation and kinetics of degradation mechanisms. They also define mechanisms, which should be quantified. For irreplaceable components or components whose replacement is difficult, the program is focused to the control of operation conditions and inspection of facilities. However, they are again based on the knowledge of degradation kinetics. If at least some parts of the facility could be replaced, better material selection regarding the operation conditions is an option. Systems included into the ageing management system will be specified in the paper. Also, the measures will be identified which serve as a check of implementation of all possible stressors and degradation mechanisms into the first screening. The examples of lifetime evaluation of some systems and components will be given in the paper: reactor pressure vessel, reactor internals, steam generator tubes and feedwater piping. Specific approaches will be shown fro different original status of components and different operation conditions. (author)
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European Nuclear Society, Bern (Switzerland); Czech Nuclear Society, Prague (Czech Republic); Slovak Nuclear Society, Bratislava (Slovakia); Czech Society for Science and Technology, Prague (Czech Republic); 435 p; 2000; p. 267-277; International topical meeting on 'VVER technical innovations for next century'; Prague (Czech Republic); 17-20 Apr 2000; 4 figs.
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Miscellaneous
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Conference
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BOILERS, CONTAINERS, ENRICHED URANIUM REACTORS, HYDROGEN COMPOUNDS, LIFETIME, NUCLEAR FACILITIES, OXYGEN COMPOUNDS, POWER PLANTS, POWER REACTORS, PWR TYPE REACTORS, REACTORS, SAFETY, THERMAL POWER PLANTS, THERMAL REACTORS, TUBES, VAPOR GENERATORS, WATER, WATER COOLED REACTORS, WATER MODERATED REACTORS, WWER TYPE REACTORS
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