Specific features of the determination of the pellet-cladding gap of the fuel rods by non-destructive method
Creators
- 1. State Scientific Center of the Russian Federation, Research Institute of Atomic Reactors, Dimitrovgrad (Russian Federation)
Description
This report describes the specific features of determining the pellet-cladding gap of the irradiated WWER-1000 fuel rods by nondestructive method. The method is based on the elastic radial deformation of the cladding up to its contact with the fuel. The value of deformation of cladding till its contacting fuel when radial force changes from Fmax to 0 is proposed as a measuring parameter for determination of the diametrical gap. Because of the features of compression method, the obtained gap value is not analog of the gap measured on micrograph of the fuel rod cross-section. Results of metallography can provide only qualitative evaluation of its method efficiency. Comparison of the values determined by non-destructive method and metallography for WWER-1000 fuel rods with burnup from 25 to 55 MWd/kg U testified that the results of compression method can be used as a low estimate of the pellet-cladding gap value. (author)
Files
33018354.pdf
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Additional details
Publishing Information
- Imprint Title
- Advanced post-irradiation examination techniques for water reactor fuel. Proceedings of a technical committee meeting
- Imprint Pagination
- 228 p.
- Journal Page Range
- p. 73-79
- ISSN
- 1011-4289
- Report number
- IAEA-TECDOC--1277
Conference
- Title
- Technical committee meeting on advanced post-irradiation examination techniques for water reactor fuel
- Dates
- 14-18 May 2001
- Place
- Dimitrovgrad (Russian Federation)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 33018354
- Subject category
- S42: ENGINEERING; S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; COMPRESSION STRENGTH; DEFORMATION; FUEL CANS; FUEL PELLETS; FUEL RODS; FUEL-CLADDING INTERACTIONS; MECHANICAL TESTS; NONDESTRUCTIVE TESTING; POST-IRRADIATION EXAMINATION; STATIC LOADS; WWER-5 REACTOR
- Descriptors DEC
- ENRICHED URANIUM REACTORS; FUEL ELEMENTS; MATERIALS TESTING; MECHANICAL PROPERTIES; PELLETS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS
Optional Information
- Notes
- 3 refs, figs