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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Published in | Kerntechnik (1987) Vol. 75; no. 5; pp. 243 - 247 |
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Main Authors | , , |
Format | Journal Article |
Language | English |
Published |
01.09.2010
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Online Access | Get full text |
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