State of metal alloy fuel after irradiation in a fast reactor

The main domestic and foreign results obtained in the course of reactor tests and post-reactor studies of alloyed fuel are reviewed. The regularities of its radiation swelling and mechanical and chemical interaction with fuel-element cladding are determined. The knowledge accumulated about the prope...

Ausführliche Beschreibung

Gespeichert in:

Bibliographische Detailangaben
Veröffentlicht in:	Atomic energy (New York, N.Y.) N.Y.), 2013-02, Vol.113 (4), p.276-282
Hauptverfasser:	Kryukov, F. N., Syuzyov, V. N., Nikitin, O. N., Kuzmin, S. V., Maltseva, E. B., Belyaeva, A. V., Gilmutdinov, I. F., Grin, P. I., Zhemkov, I. Yu
Format:	Artikel
Sprache:	eng
Schlagworte:	Alloying elements Alloys Analysis Building materials Domestic Experiments Fuels Fusion Hadrons Heat conductivity Heavy Ions Irradiation Metal fuels Nuclear Chemistry Nuclear Energy Nuclear fuels Nuclear Physics Nuclear radiation Nuclear reactors Physics Physics and Astronomy Radiation Reactors Regularity Specialty metals industry Studies Swelling Uranium
Online-Zugang:	Volltext
Tags:	Tag hinzufügen Keine Tags, Fügen Sie den ersten Tag hinzu!

Schreiben Sie den ersten Kommentar!