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A. Bachrata
A. Bachrata
Nuclear engineering
Engineering
Structural engineering
Corium
Flow (psychology)
4
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34
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A three-dimensional neutronics – Thermalhydraulics Unprotected Loss of Flow simulation in Sodium-cooled Fast Reactor with mitigation devices
2019
Nuclear Engineering and Design
A. Bachrata
L. Trotignon
P. Sciora
M. Sáez
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Status of severe accident studies at the end of the conceptual design of ASTRID: Feedback on mitigation features
2018
Nuclear Engineering and Design
F. Bertrand
N Marie
A. Bachrata
V. Brun-Magaud
Jean-Baptiste Droin
X. Manchon
K. Herbreteau
B. Farges
B. Carluec
S. Poumerouly
D. Lemasson
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Citations (20)
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