Published March 2002
| Version v1
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Special techniques for tensile tests of irradiated zirconium claddings
- 1. State Scientific Center of Russian Federation, Research Institute of Atomic Reactors, Dimitrovgrad (Russian Federation)
Description
Irradiated zirconium alloy claddings possessing property anisotropy should be tested in transverse and longitudinal directions. Such mechanical tests can be performed in conditions of large variety of geometric peculiarities of specimens, supports or grips. The objective of the work is the development of the unified complex of updated special techniques that allow investigation of mechanical pre- and post-irradiation properties of VVER claddings including radiation effect of property anisotropy changes in the same way. (author)
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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. 195-202
- 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
- 33018366
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ELONGATION; EXPANSION; FUEL CANS; POST-IRRADIATION EXAMINATION; TEMPERATURE DEPENDENCE; TENSILE PROPERTIES; ZIRCONIUM ALLOYS
- Descriptors DEC
- ALLOYS; DEFORMATION; MECHANICAL PROPERTIES; TRANSITION ELEMENT ALLOYS
Optional Information
- Notes
- 2 refs, 11 figs