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The methodology of spent fuel containers nuclear safety proving by simulation.
Last modified: 2009-09-14
Abstract
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A description of an actual status of documentation of nuclear safety for burned down fuel transport containers C-30 is given in this article. An alternative frame for this documentation is given at the same time, too. The new alternative consists of mathematical modeling of container and after that in physical-thermal computation of container nuclear safety from measured data. The main phases of the methodology, as well as the model building, the verification of the obtained model, measuring parameters estimation, measuring systems realization, first results and next steps are described in the article. The methodology can be used for all types of containers for burned-down fuel transport.
The proposed methodology has resulted from Nuclear Regulatory of Slovak Republic requirements. The organization requires the duplicate proving of all reliability and safety parameters of systems used in nuclear power engineering. The suggested method is a topic of an APVV-0308-07 project, solved in co-operation of Faculty of Materials Science and Technology (represented by Institute of Applied Informatics, Automation and Mathematics) and Research Institute of Power Plants (VUJE ), joint stock company Trnava. The methodology is new and it brings significant theoretical and practical benefits.
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