1. N. A. Mosunova, “Integrated code EUCLID/V1 to justify the safety of fast-neutron reactor installations with a liquid metal coolant. Part 1: Basic models,” Teploenergetika, No. 5, 69–84 (2018).
2. E. V. Usov, A. A. Butov, V. I. Chukhno, et al., “Fuel pin melting in a fast reactor and melt solidification: simulation using the SAFR/V1 module of the EVKLID/V2 integral code,” At. Energ., 124, No. 3, 1–7 (2018).
3. E. V. Usov, A. A. Butov, V. I. Chukhno, et al., “SAFR / V1 (EVKLID / V2 integral code module) aided simulation of melt movement along the surface of a fuel element in a fast reactor during a serious accident,” At. Energ., 124, No. 4, 1–7 (2018).
4. A. A. Butov, V. S. Zhdanov, I. A. Klimonov, et al., “Physical models for calculating the destruction of a fuel rod and the core of a reactor with liquid metal coolant, implemented in the EUCLID / V2 code,” Teploenergetika, No. 5, 5–15 (2019).
5. A. Flores, V. Matuzas, S. Perez-Martin, et al., “Analysis of ASTEC-Na capabilities for simulating a loss of flow CABRI experiment,” An. Nucl. Energy, 94, 175–188 (2016).