To the problem of the statistical basis of evaluation of the mechanical safety factor
Description
The methodology applied for the safety factor assessment of the WWER fuel cycles uses methods and terms of statistics. Value of the factor is calculated on the basis of estimation of probability to meet predefined limits. Such approach demands the special attention to the statistical properties of parameters of interest. Considering the mechanical constituents of the engineering factor it is assumed uncertainty factors of safety parameters are stochastic values. It characterized by probabilistic distributions that can be unknown. Traditionally in the safety factor assessment process the unknown parameters are estimated from the conservative points of view. This paper analyses how the refinement of the factors distribution parameters is important for the assessment of the mechanical safety factor. For the analysis the statistical approach is applied for modelling of different type of factor probabilistic distributions. It is shown the significant influence of the shape and parameters of distributions for some factors on the value of mechanical safety factor. (Authors)
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Additional details
Publishing Information
- Publisher
- Kiadja and KFKI Atomenergia Kutatointezet
- Imprint Place
- Budapest (Hungary)
- ISBN
- 963-372-640-2
- Imprint Title
- Proceedings of the nineteenth symposium of atomic energy research on WWER reactor physics and reactor safety
- Imprint Pagination
- [533 p.]
- Journal Page Range
- p. 1-8
- Report number
- INIS-SK--2009-114
Conference
- Title
- 19. atomic energy research symposium on WWER reactor physics and reactor safety
- Dates
- 21-25 Sep 2009
- Place
- Varna (Bulgaria)
INIS
- Country of Publication
- Hungary
- Country of Input or Organization
- Slovakia
- INIS RN
- 40108140
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- DATA COVARIANCES; FUEL ASSEMBLIES; FUEL CYCLE; NUMERICAL DATA; RADIATION PROTECTION; RISK ASSESSMENT; SAFETY ANALYSIS; STATISTICAL MODELS; WWER TYPE REACTORS
- Descriptors DEC
- DATA; ENRICHED URANIUM REACTORS; INFORMATION; MATHEMATICAL MODELS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 4 figs.; 1 tab.; 4 refs. Imprint:ISBN(13): 978-963-372-640-2; Next corporations organizations: Budapest University of Technology and Economics, Institute of Nuclear Techniques, Budapest (Hungary); Forschungszentrum Dresden - Rossendorf, Institute of Safety Research, Dresden (Germany); Slovak University of Technology, Faculty of Electrical Engineering and Information Technology, Department of Nuclear Physics and Technology, Bratislava (Slovakia); GRS mbH (Germany); INRNE-BAS, Sofia (Bulgaria); VTT, Espoo (Finland); BME NTI (Hungary), State Scientific and Technical Centre on Nuclear and Radiation Safety, Kyiv (Ukraine); Nuclear Regulatory Authority of the Slovak Republic (Slovakia); Dukovany NPP (Czech Republic); Studsvik Scandpower GmbH (Germany)