Development of a FBR Fuel Bundle-duct Interaction Analysis Code-BAMBOO: Analysis Model and Verification by Phenix High Burn-up Fuel Subassemblies
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چکیده
منابع مشابه
a phonological contrastive analysis of kurdish and english
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متن کاملComparison of (Th-233U) O2 and (Th-235U) O2 fuel burn up into a thermal research reactor using MCNPX 2.6 code
Background: Decrease of economically accessible uranium resources motivates consideration of breeding of fertile elements such as thorium. Material and Method: Thorium oxide fuel burn up calculation of a simulated research reactor cooled heavy water has been proposed in the present work using MCNPX 2.6 code. Two 233U and 235U isotopes have been used as fissile element of thorium oxide fuel. 135...
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ژورنال
عنوان ژورنال: Journal of Nuclear Science and Technology
سال: 2005
ISSN: 0022-3131
DOI: 10.3327/jnst.42.608