Performance analysis of 233 U for fixed bed nuclear reactors

Abstract Criticality and burn up behavior of the Fixed Bed Nuclear Reactor (FBNR) are investigated for the mixed fuel 233 UO 2 /ThO 2 as an alternative to low enriched 235 UO 2 fuel. CERMET fuel with a zirconium matrix and cladding has been used throughout the study. The main results of the study ca...

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Bibliographic Details
Published inKerntechnik (1987) Vol. 75; no. 5; pp. 243 - 247
Main Authors Şahin, S., Acır, A., Şahin, H. M.
Format Journal Article
LanguageEnglish
Published 01.09.2010
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