Possibility of identifying the fuel elements and fuel assemblies of first-generation USA and USSR research reactors

The possibilities of identifying the fuel elements and fuel assemblies from the cores of first-generation research reactors in the USSR (F1, TVR, RFT, IGR, SM-2, and IVG.1) and USA (CR-1, X-10, BGRR, EBR I, MTR, ARE, and TREAT) are examined. The fuel elements and assemblies are described and the cro...

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Bibliographic Details
Published in:Atomic energy (New York, N.Y.) N.Y.), 2013-02, Vol.113 (4), p.271-275
Main Authors: Gorin, N. V., Churikov, Yu. I., Korneev, A. A., Voloshin, N. P., Arkhangelskiy, N. V., Prostakov, V. I., Dikarev, V. S., Pavshook, V. A., Abalin, S. S., Shvedov, O. V., Deryavko, I. I., Kolbaenkov, A. N.
Format: Article
Language:English
Subjects:
Aluminum
Analysis
Assemblies
Cross sections
Fuel elements
Fuels
Hadrons
Heavy Ions
Identification
Nuclear Chemistry
Nuclear Energy
Nuclear engineering
Nuclear fuel elements
Nuclear fuels
Nuclear Physics
Nuclear reactors
Physics
Physics and Astronomy
Radiation
Reactors
Studies
Uranium
USSR
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Summary:The possibilities of identifying the fuel elements and fuel assemblies from the cores of first-generation research reactors in the USSR (F1, TVR, RFT, IGR, SM-2, and IVG.1) and USA (CR-1, X-10, BGRR, EBR I, MTR, ARE, and TREAT) are examined. The fuel elements and assemblies are described and the cross section and characteristic dimensions are presented. It is shown that the fuel elements and fuel assemblies are different and that in order to identify them in most cases only the geometric dimensions need by examined and measured. However, if a reactor fuel element or assembly is completely destroyed, then the uranium enrichment and isotopic composition as well as the impurity composition must be measured.
ISSN:1063-4258
1573-8205
DOI:10.1007/s10512-013-9629-7