Probabilistic analysis of strength and thermal-physic WWER fuel rod characteristics using START-3 code
Creators
- 1. A. A. Bochvar Research Institute of Inorganic Materials, Moscow (Russian Federation)
- 2. International Atomic Energy Agency, Vienna (Australia)
Description
During the last years probabilistic methods for evaluation of the influence of the fuel geometry and technology parameters on fuel operational reliability are widely used. In the present work the START-3 procedure is used to calculate the thermal physics and strength characteristics of WWER fuel rods behavior. The procedure is based on the Monte-Carlo method with the application of Sobol quasi-random sequences. This technique allows to treat the fuel rod technological and operating parameters as well as its strength and thermal physics characteristics as random variables. The work deals with a series of WWER-1000 fuel rod statistical tests and verification based on the PIE results. Also preliminary calculations are implemented with the aim to determine the design schema parameters. This should ensure the accuracy of the assessment of the parameters of WWER fuel rod characteristics distribution. The probability characteristics of fuel rod strength and thermal physics are assessed via the statistical analysis of the results of probability calculations
Availability note (English)
Available from INIS in electronic formFiles
33070731.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 7 p.
- Report number
- INIS-BG--0481
Conference
- Title
- International conference on WWER fuel performance, modelling and experimental support
- Dates
- 1-5 Oct 2001
- Place
- Varna (Bulgaria)
INIS
- Country of Publication
- Bulgaria
- Country of Input or Organization
- Bulgaria
- INIS RN
- 33070731
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FUEL RODS; PROBABILITY; S CODES; STATISTICS; STRAINS; STRESSES; WWER TYPE REACTORS
- Descriptors DEC
- COMPUTER CODES; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; MATHEMATICS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 3 tabs, 8 figs., 11 refs.