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...

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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
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Beschreibung
Zusammenfassung:	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 properties and behavior under irradiation of alloyed metal fuel can be helpful in designing a fuel element that is serviceable to burnup ≥20% h.a.
ISSN:	1063-4258 1573-8205
DOI:	10.1007/s10512-013-9630-1