1. Brachet, J.-C., Le Saux, M., Le Flem, M., Urvoy, S., Rouesne, E., Guilbert, T., Cobac, C., Lahogue, F., Rousselot, J., Tupin, M., Billaud, P., Hossepied, C., Schuster, F., Lomello, F., Billard, A., Velisa, G., Monsifrot, E., Bischoff, J., Ambard, A., 2015. On-going studies at CEA on chromium coated zirconium based nuclear fuel claddings for enhanced accident tolerant LWRS fuel.
2. Research on thermal behaviors of several accident tolerant fuels based on 5 × 5 bundle subchannel model;Cai;Ann. Nucl. Energy,2019
3. Development of thermal models and analysis of UO-BeO fuel during a loss of coolant accident;Chandramouli;Int. J. Nucl. Energy,2014
4. Neutronic analysis on potential accident tolerant fuel-cladding combination U3Si2–FeCrAl;Chen;Technol. Nucl. Installations,2017
5. Preliminary thermal hydraulic analysis of various accident tolerant fuels and claddings for control rod ejection accidents in LWRs;Chen;Nucl. Eng. Des.,2018