Facility Details: VERDON

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"
Contributed By: Y. Pontillon

References: [1] E. Geiger, PhD thesis
Comments: Characterization by EPMA
Contributed By: Y. Pontillon

References: [1] A. GallaisDuring et al., «Overview of the VERDON-ISTP Program and main insights from the VERDON-2 air ingress test», Annals of Nuclear Energy, Volume 101, March 2017, Pages 109-117, https://doi.org/10.1016/j.anucene.2016.09.045
[2] P. Chatelard, L. Laborde, «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.
[3] 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.
[4] H. Shiotsu et al., «Numerical analysis for FP speciation in VERDON-2 experiment: Chemical re-vaporization of iodine in air ingress condition», Annals of Nuclear Energy, vol. 163, p. 108587, 2021, https://doi.org/10.1016/j.anucene.2021.108587.
Comments: Transport of FP (TGTM)
Contributed By: Y. Pontillon

References: "[1] C. Le Gall et al., «MOX fuel microstructural evolution during the VERDON-3 and 4 tests», Journal of Nuclear Materials, vol. 531, p. 152015, avr. 2020, doi: 10.1016/j.jnucmat.2020.152015
[2] C. Le Gall et al., «Fission product speciation in the VERDON-3 and VERDON-4 MOX fuels samples», Journal of Nuclear Materials, Volume 530, March 2020, 151948, https://doi.org/10.1016/j.jnucmat.2019.151948"

Contributed By: F. Audubert

References: [1] C. Le Gall et al., « MOX fuel microstructural evolution during the VERDON-3 and 4 tests », Journal of Nuclear Materials, vol. 531, p. 152015, avr. 2020, doi: 10.1016/j.jnucmat.2020.152015.
Contributed By: Y. Pontillon, F. Audubert

References: [1] C. Le Gall et al., « MOX fuel microstructural evolution during the VERDON-3 and 4 tests », Journal of Nuclear Materials, vol. 531, p. 152015, avr. 2020, doi: 10.1016/j.jnucmat.2020.152015.
Contributed By: Y. Pontillon, F. Audubert

Comments: Transport of FP (TGTM)
Contributed By: Y. Pontillon