References:"[1] Y. Pontillon et al., « International Source Term Program - VERDON-1 test: Fission product release from High Burn Up UO2 fuel in severe accident conditions. Final Report », CEA-DEN-CAD-DEC-SA3C-LAMIR NT, vol. 12‑013, déc. 2012
[2] E. Geiger et al., « Modelling nuclear fuel behaviour with TAF-ID: Calculations on the VERDON-1 experiment, representative of a nuclear severe accident », Journal of Nuclear Materials, vol. 522, p. 294‑310, août 2019, doi: 10.1016/j.jnucmat.2019.05.027.
[3] E. Geiger et al., « Fission products and nuclear fuel behaviour under severe accident conditions part 2: Fuel behaviour in the VERDON-1 sample », Journal of Nuclear Materials, vol. 495, p. 49‑57, nov. 2017, doi: 10.1016/j.jnucmat.2017.08.002
[4] S. Nichenko et al., «Modelling of fission products release in VERDON-1 experiment with cGEMS: Coupling of severe accident code MELCOR with GEMS thermodynamic modelling package», Annals of Nuclear Energy, vol. 152, p. 107972, 2021, doi.org/10.1016/j.anucene.2020.107972
[5] A. Germain et al., «Modeling of fission product release during severe accidents with the fuel performance code ALCYONE», Nuclear Engineering and Design, vol. 393,
p. 111778, 2022,
https://doi.org/10.1016/j.nucengdes.2022.111778.
[6] P. Chatelard et al., «ASTEC V2.2 code validation: Illustrative results and main outcomes», Nuclear Engineering and Design, vol. 413, p. 112547, 2023,
https://doi.org/10.1016/j.nucengdes.2023.112547.
[7] Yu.B. Shmelkov et al., «Development and validation of the MAVR-TA code for analyzing the release and transport of fission products during a severe accident at a nuclear power plant with VVER. Part 1 –Release of fission products from a fuel», Nuclear Engineering and Design, vol. 385, p. 111407, 2021,
https://doi.org/10.1016/j.nucengdes.2021.111407.
[8] E. Geiger et al., «Modelling nuclear fuel behaviour with TAF-ID: Calculations on the VERDON-1 experiment, representative of a nuclear severe accident», Journal of Nuclear Materials, vol. 522, p. 294-310, 2019,
https://doi.org/10.1016/j.jnucmat.2019.05.027"Link to PIRT:WP-1.5 ST-3, ST-5
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