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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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Nuclear Dirigo
On April 22, 1959, Rear Admiral George J. King, superintendent of the Maine Maritime Academy, announced that following the completion of the 1960 training cruise, cadets would begin the study of nuclear engineering. Courses at that time included radiation physics, reactor control and instrumentation, reactor theory and engineering, thermodynamics, shielding, core design, reactor maintenance, and nuclear aspects.
A. Boulin, J. F. Haquet, P. Piluso (CEA), S. Semenov, M. Antoni (CNRS), T. Washiya, A. Nakayoshi, T. Kitagaki (JAEA)
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 1080-1090
In the frame of Severe Accident studies, the VULCANO-facility at PLINIUS-platform (CEA - Cadarache) is devoted to the understanding of the interaction of corium with a concrete containment pit (Molten Corium Concrete Interaction-MCCI) [1]. The VULCANO VF-U1 experiment was designed to be closer as possible of the MCCI conditions possibly occurring in the Fukushima F1 reactor considering the coexistence of two dispersed phases (metallic liquid droplets and gaseous bubbles) in a continuous phase (oxide melt liquid). A MCCI industrial code was used to perform predictive calculation of the VF-U1 experiment, being closer as possible of Fukushima 1-F1 MCCI conditions. The results shown that the axial ablation is 8 times higher than the radial one. Then, a multiplicative factor of 8 for the axial heat exchange coefficient must be applied to find the final cavity shape. VULCANO VF-U1 Post-Test Analyses have shown that the metallic phase is preferably close to the vertical concrete walls and at the bottom of the test section whereas a stratification due to density difference between the oxide and the metallic phase is expected (as modeling by the MCCI code). Regarding to the real coupling physical effects in the integral the VULCANO-ICB test and the difficulties for the MCCI code to reproduce experimental behaviors, numerical simulations were conducted. For this purpose, a multiphase Volume Of Fluid (VOF) code at AMU (MADIREL) has been developed . In these calculations, the corium has been modelled numerically under isothermal conditions as a twodimensional dispersed medium with multiple metal drops and gas bubbles. The results showed a possible hydrodynamic re-localization matching to experimental results.
