Deformation of Experimental Fuel Pins with Improved Zirconium-Alloy Cladding in Reactor Tests

Deformation of Experimental Fuel Pins with Improved Zirconium-Alloy Cladding in Reactor Tests

A stand for inspecting experimental fuel pins in the cooling pool of the MIR.M1 reactor and methodological approaches to measuring the height and diameter of experimental fuel pins are described. The basic characteristics of the equipment used for performing measurements are described. The structura...

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Veröffentlicht in:Atomic energy (New York, N.Y.) N.Y.), 2020-07, Vol.128 (3), p.191-195
Hauptverfasser: Burukin, A. V., Dolgov, A. I., Izhutov, A. L., Il’in, P. A., Kalygin, V. V., Mokeichev, M. A., Ugryumov, A. V., Dolgov, Yu. N.
Format: Artikel
Sprache:eng
Schlagworte:
Alloys
Building materials
Cladding
Diameters
Energy industry
Fuels
Hadrons
Heavy Ions
In reactor tests
Nuclear Chemistry
Nuclear Energy
Nuclear fuels
Nuclear Physics
Nuclear power plants
Physics
Physics and Astronomy
Reactors
Specialty metals industry
Zirconium
Zirconium alloys
Zirconium base alloys
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Beschreibung
Zusammenfassung:A stand for inspecting experimental fuel pins in the cooling pool of the MIR.M1 reactor and methodological approaches to measuring the height and diameter of experimental fuel pins are described. The basic characteristics of the equipment used for performing measurements are described. The structural features of an experimental FA (EFA) and the test parameters of experimental fuel pins in an assembly in one of the loop facilities of the MIR reactor are presented. The results of a series of measurements of the diameter and height of irradiated fuel pins with cladding made from different zirconium alloys with different average fuel burnup over the EFA are shown.
ISSN:1063-4258
1573-8205
DOI:10.1007/s10512-020-00674-8