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Study on velocity field in a deformed fuel bundle
Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan, 2006SATO, HIROYUKI +3 more
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An Improved Version of the Bacchus Code for the Analysis of Fuel Bundles
1990The present work describes an improved version of the computer code BACCHUS-T to analyse the thermohydraulic features of the coolant flow in the fuel bundle of a LMFBR.The improvement mainly consists in the development of a numerical algorithm, based on the finite element method, in order to predict the temperature distribution in the fuel, gap and ...
E. Lorenzini +5 more
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CFD investigation on thermal-hydraulic characteristics of a helical cruciform fuel bundle
Progress in Nuclear Energy, 2022Maolong Liu
exaly
Thermal-hydraulic analysis of a 7-pin sodium-cooled fast reactor wire-wrapped fuel bundle
International Journal of Heat and Mass Transfer, 2020Changhong Peng
exaly
Modeling Temperature Nonuniformities in a Fuel-Element Bundle of a VVER-1000 Fuel-Assembly
Atomic Energy, 2013S. I. Getya +4 more
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Numerical simulation of turbulent flow through a 37-element CANDU fuel bundle
Annals of Nuclear Energy, 2012S D Yu
exaly
Investigation of uranium monocarbide fuel elements in the fuel bundles of the Br-5 reactor
Soviet Atomic Energy, 1971Sh. Sh. Ibragimov +7 more
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CFD investigations of helical wire-wrap fuel pin bundle and its comparison with straight wire bundle
Progress in Nuclear Energy, 2016K Velusamy
exaly
Development of a FBR Fuel Bundle-duct Interaction Analysis Code-BAMBOO
Journal of Nuclear Science and Technology, 2005Tomoyuki Uwaba, Shigeharu Ukai
exaly