Journal Articles
Nuclear Engineering and Design
Year : 2018
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https://hal-cea.archives-ouvertes.fr/cea-02339667
Submitted on : Wednesday, October 30, 2019-3:06:08 PM
Last modification on : Wednesday, August 24, 2022-2:45:54 PM
Dates and versions
Identifiers
- HAL Id : cea-02339667 , version 1
- DOI : 10.1016/j.nucengdes.2019.02.015
Cite
A. Bachrata, L. Trotignon, P. Sciora, M. Saez. A three-dimensional neutronics - thermohydraulics Unprotected Loss Of Flow simulation in Sodium-cooled Fast Reactor with mitigation devices. Nuclear Engineering and Design, 2018, ⟨10.1016/j.nucengdes.2019.02.015⟩. ⟨cea-02339667⟩
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