2007 International RERTR Meeting
Abstracts and Available Papers Presented at the Meeting
Microstructure of 50 Year Old SCK●CEN BR1 Research Reactor Fuel
A. Leenaers and S. Van
den Berghe
Nuclear Materials Science Institute
SCK.CEN, Boeretang 200, 2400 Mol, Belgium.
ABSTRACT
The BR1 research reactor at SCK.CEN, Mol (Belgium) has a graphite core matrix loaded with fuel rods consisting of a natural uranium slug in an aluminum cladding. Fabrication reports show the application of a so-called AlSi bonding layer and an U(Al,Si)3 anti-diffusion layer on the natural uranium fuel slug to limit the interaction between the uranium fuel and aluminum cladding. The BR1 reactor is in operation since 1956 and still contains its original fuel rods. After more than 50 years irradiation at low temperature, the integrity of some of the fuel rods is investigated. The microstructure of the fuel, bonding and anti-diffusion layer and cladding is analyzed using optical microscopy (OM), scanning electron microscopy (SEM) and electron microprobe analysis (EPMA).
Full paper in PDF format
- Microstructure
of 50 Year Old SCK●CEN BR1 Research Reactor Fuel,
A. Leenaers et al.
[PDF, 4.5MB, 10 pages]
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Contact:
Dr. Jordi Roglans-Ribas
Technical Director, RERTR Department
Nuclear Engineering Division – 362
Argonne National Laboratory
9700 South Cass Avenue
Argonne, IL 60439
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