2010
DOI: 10.1016/j.anucene.2010.04.006
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High-burn up 10×10 100%MOX ABWR core physics analysis with APOLLO2.8 and TRIPOLI-4.5 codes

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Cited by 5 publications
(2 citation statements)
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“…Design of assemblies with UO 2 fuel consists of 9 × 9 lattice configuration with 2 large water channels and 74 fuel rods of varying 235 U enrichment. Initial enrichment varies from Science and Technology of Nuclear Installations 3 3 wt% to 6.3 wt% for fuel mixtures (marked by numbers [1][2][3][4]. 16 fuel rods contain UO 2 -Gd 2 O 3 mixture (marked as G).…”
Section: Designs Of Fuelmentioning
confidence: 99%
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“…Design of assemblies with UO 2 fuel consists of 9 × 9 lattice configuration with 2 large water channels and 74 fuel rods of varying 235 U enrichment. Initial enrichment varies from Science and Technology of Nuclear Installations 3 3 wt% to 6.3 wt% for fuel mixtures (marked by numbers [1][2][3][4]. 16 fuel rods contain UO 2 -Gd 2 O 3 mixture (marked as G).…”
Section: Designs Of Fuelmentioning
confidence: 99%
“…Void reactivity coefficient for BWR fuel has been studied for typical void fraction values of 0%, 40%, and 70% [2][3][4]. 0% and 70% void fractions were chosen in these studies, since they correspond to moderation conditions at the bottom and the top of the BWR fuel assembly during normal operation, respectively.…”
Section: Introductionmentioning
confidence: 99%