Argonne National Laboratory
Reduced Enrichment for Research and Test Reactors
Nuclear Science and Engineering Division at Argonne
U.S. Department of Energy

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Abstracts and Available Papers Presented at the
1997 International RERTR Meeting


A. V. Vatulyn, Y. A. Stetskyi. I. V. Dobrikova
VNIINM, 123060, Moscow. Russia


To the purpose of fuel elements unification the possibility of rod fuel assembly (FA) using in the cores of research reactors have been considered in this paper. The calculation results of geometric, hydraulic and thermotechnical parameters of rod assembly are submitted. Several designs of finned square fuel element and fuel assembly are proposed on base of analysis of rod FA characteristics in compare of tube ones. The fuel elements specimens and the model assembly are manufactured. The developed designs are the basis for further optimization after neutron-physical calculations of cores.

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Dr. A. V. Vatulyn
Rogova 5
PO Box 369
Moscow 123060, Russia
Tel.: 7-095-190-8166
Fax: 7-095-196-4075
E-mail: [email protected]

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Last modified on July 29, 2008 11:33 +0200