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The development of a three-dimensional transient CFD model for predicting cooling ability of spent fuel poolsHUNG, Tzu-Chen; DHIR, Vijay K; PEI, Bau-Shei et al.Applied thermal engineering. 2013, Vol 50, Num 1, pp 496-504, issn 1359-4311, 9 p.Article

Le cycle et les scénarios (Paris, 16 janvier 2001)Le cycle et les scénarios. Journée. 2001, 240 p.Conference Proceedings

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Oxidation of UO₂ by radiolytic oxidantsEKEROTH, Ella; JONSSON, Mats.Journal of nuclear materials. 2003, Vol 322, Num 2-3, pp 242-248, issn 0022-3115, 7 p.Article

The kinetics of dissolution of Th_1-xU_xO₂ solid solutions in nitric mediaHEISBOURG, G; HUBERT, S; DACHEUX, N et al.Journal of nuclear materials. 2003, Vol 321, Num 2-3, pp 141-151, issn 0022-3115, 11 p.Article

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