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...

Ausführliche Beschreibung

Gespeichert in:

Bibliographische Detailangaben
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
Online-Zugang:	Volltext
Tags:	Tag hinzufügen Keine Tags, Fügen Sie den ersten Tag hinzu!

Schreiben Sie den ersten Kommentar!