Abstracts and Available Papers Presented at the
2002 International RERTR Meeting
STUDY OF APPLICATION AND TESTING OF THE EXPERIMENTAL FUEL ASSEMBLY WITH 36 %, 19.8% ENRICHMENT
B. S. Yuldashev, U. S. Salikhbaev, Kh. Karabaev., S. Baytelesov
Institute Nuclear Physics
Study of application and testing of the experimental fuel assembly with 36% enrichment in U-235, the fuel developed by Russian Federation at the WWR-SM research reactor of INP -- Institute of Nuclear Physics (the Republic of Uzbekistan).
The WWR-SM reactor of INP currently uses FA of the IRT-3M type containing uranium with an enrichment of 36% in U-235. The density of uranium in the fuel meat is 2.5 g/cm3. The reactor has a high operating efficiency (6400 hours per year) at a maximum power of 10 МW.
For research reactors in countries of the Former Soviet Union (FSU), nuclear fuel assemblies (FA) containing low-enriched uranium (LEU), which meet the international requirements, have not yet been developed. Scientists at Institute «Kurchatov» together with scientists at the INP are currently developing the fuel elements with an enrichment of 36%, (19.8% IRT-4M type) in U-235 that meets the requirements of IAEA.
The Institute of Nuclear Physics of the Academy of Sciences of the Republic of Uzbekistan has all necessary conditions, equipment and expertise at its WWR-SM research reactor for application research and testing of the fuel assemblies with PTFE. During 1987-1989, irradiation testing of two 6-tube FA and one 8-tube FA of the IRT-3M type with 36% enrichment in U-235 was successfully carried out. During November 2000 and 20 March 2002 irradiation testing of four IRT-4M type FA with an enrichment of 19.75% in U -235 successfully carried out.
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Mr. Sapar Baytelesov
Institute of Nuclear Physics
Uzbekistan Academy of Science,
Scientific Researcher 65, Sirgal Street,
Kibray, Tashkent region 702150 Uzbekistan
Phone: (99 87 12) 60 61 34
Fax: (99 87 12) 64 25 90