Safety-oriented SFR core design: Methodology and application to transient bifurcations and stability maps analyses

Author:

Droin J.B.,Seiler N.,Bertrand F.,Manchon X.,Sciora P.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference33 articles.

1. Alpy, N., et al., 2014. Phenomenological Investigation of Sodium Boiling in a SFR Core during a postulated ULOF transient with CATHARE 2 System Code: a Stabilized Boiling Case, NUTHOS-10, Okinawa, Japan, 2014, December 14-18.

2. Bachrata, A., Trotignon, L., Sciora P., Saez, M., 2019. A three-dimensional neutronics – Thermalhydraulics Unprotected Loss of Flow simulation in Sodium-cooled Fast Reactor with mitigation devices, Nuclear Engineering and Design, Volume 346, 2019, Pages 1-9, ISSN 0029-5493.

3. Bertrand, F., Manchon, X., Marie, N., Droin, J., Schmitt, D., Lance, M., Sciora, P., 2012. Coupled thermal-hydraulic neutronic stability extended criterion in a SFR core. Flow stability simplified criterion in a SFR core taking into account flow rate and power variations. Nucl. Eng. Des. 355, 110319, 2019.

4. Simplified criteria for a comparison of the accidental behaviour of Gen IV nuclear reactors and of PWRS;Bertrand;Nucl. Eng. Des.,2021

5. Caraghiaur, D., Marie, N., Bertrand, F., Kudinov P., 2014. Simplified models dedicated to vapour explosion applicable for ASTRID pre-conceptual design, the 13th International Conference on Multiphase Flow in Industrial Plants, Sestri Levante (Genova), Italy, 17-19 September 2014.

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