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R. Mollerach
R. Mollerach
Engineering
Coolant
Nuclear engineering
Nuclear power plant
Control rod
3
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3
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0
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Thermalhydraulics studies examining the feasibility for introducing slightly enriched uranium fuel into the Embalse CANDU reactor
2007
Nuclear Engineering and Design
L.K.H. Leung
P. Serrano
M. Schivo
A. Parrondo
Y. Guo
O. Mazzantini
D. Oh
M. Higa
F. Khatchikian
R. Mollerach
J. Fink
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Validation of updated neutronic calculation models proposed for Atucha-II PHWR. Part II: Benchmark comparisons of PUMA core parameters with MCNP5 and improvements due to a simple cell heterogeneity correction
2006
C. Grant
R. Mollerach
F. Leszczynski
O. Serra
J. Marconi
J. Fink
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Validation of Updated Neutronic Calculation Models Proposed for Atucha-II PHWR. Part I: Benchmark Comparisons of WIMS-D5 and DRAGON Cell and Control Rod Parameters with MCNP5
2006
R. Mollerach
F. Leszczynski
J. Fink
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