Published 2001 | Version v1
Miscellaneous Open

Probabilistic analysis of strength and thermal-physic WWER fuel rod characteristics using START-3 code

  • 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 form

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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.