Tests on CANDU fuel elements sheath samples
Creators
- 1. Institute for Nuclear Research Pitesti, (Romania)
- 2. University POLITEHNICA of Bucharest, (Romania)
Description
This work is a study of the behavior of CANDU fuel elements after irradiation. The tests are made on ring samples taken from fuel cladding in INR Pitesti. This paper presents the results of examinations performed in the Post Irradiation Examination Laboratory. By metallographic and ceramographic examination we determinate that the hydride precipitates are orientated parallel to the cladding surface. A content of hydrogen of about 120 ppm was estimated. After the preliminary tests, ring samples were cut from the fuel rod, and were subject of tensile test on an INSTRON 5569 model machine in order to evaluate the changes of their mechanical properties as consequence of irradiation. Scanning electron microscopy was performed on a microscope model TESCAN MIRA II LMU CS with Schottky FE emitter and variable pressure. The analysis shows that the central zone has deeper dimples, whereas on the outer zone, the dimples are tilted and smaller. (authors)
Files
48103677.pdf
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Additional details
Publishing Information
- Publisher
- Institute for Nuclear Research - Pitesti
- Imprint Place
- Pitesti (Romania)
- Imprint Title
- Proceedings of NUCLEAR 2016 the 9th annual international conference on sustainable development through nuclear research and education. Part 1/3
- Imprint Pagination
- 332 p.
- Journal Page Range
- p. 166-173
- ISSN
- 2066-2955
- Report number
- INIS-RO--0009
Conference
- Title
- 9. annual international conference on sustainable development through nuclear research and education
- Acronym
- NUCLEAR 2016
- Dates
- 18-20 May 2016
- Place
- Pitesti (Romania)
INIS
- Country of Publication
- Romania
- Country of Input or Organization
- Romania
- INIS RN
- 48103677
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CANDU TYPE REACTORS; CLADDING; FUEL ASSEMBLIES; POST-IRRADIATION EXAMINATION
- Descriptors DEC
- DEPOSITION; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; SURFACE COATING; THERMAL REACTORS
Optional Information
- Notes
- 9 refs., 13 figs.