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E. Sikik
E. Sikik
Argonne National Laboratory
Nuclear engineering
Engineering
Nuclear reactor core
Thermal hydraulics
Nuclear chemistry
6
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4
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Thermal-Hydraulics and Neutronics Overview of the DISECT Experiment
2019
Walter J. Williams
C. Hale
E. Sikik
M Sprenger
G. Borghmans
Daniel M. Wachs
S. Van den Berghe
Maria A. Okuniewski
T. Maddock
B. Boer
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Supplemental Thermal-Hydraulic Transient Analyses of BR2 in Support of Conversion to LEU Fuel
2016
J. R. Licht
B. Dionne
E. Sikik
G. Van den Branden
E. Koonen
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Loss-of-Flow and Loss-of-Pressure Simulations of the BR2 Research Reactor with HEU and LEU Fuel
2016
J. R. Licht
A. Bergeron
B. Dionne
E. Sikik
G. Van den Branden
E. Koonen
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Steady-State Thermal-Hydraulics Analyses for the Conversion of the BR2 Reactor to LEU
2015
J. R. Licht
A. Bergeron
B. Dionne
G. Van den Branden
Silva Kalcheva
E. Sikik
E. Koonen
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RELAP5 Model Description and Validation for the BR2 Loss-of-Flow Experiments
2015
J. R. Licht
B. Dionne
G. Van den Branden
E. Sikik
E. Koonen
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Steady-State Thermal-Hydraulics Analyses for the Conversion of BR2 to Low Enriched Uranium Fuel
2015
J. R. Licht
A. Bergeron
B. Dionne
G. Van den Branden
Silva Kalcheva
E. Sikik
E. Koonen
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