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APT characterization of irradiation effects on MX phase in reduced-activation ferritic/martensitic steels
Cui, L., Dai, Y., Gerstl, S. S. A., & Pounchon, M. A. (2023). APT characterization of irradiation effects on MX phase in reduced-activation ferritic/martensitic steels. Journal of Nuclear Materials, 573, 154121 (10 pp.). https://doi.org/10.1016/j.jnucmat.2022.154121
Delayed hydride cracking in Zircaloy-2 with and without liner at various temperatures investigated by high-resolution neutron radiography
Colldeweih, A. W., Fagnoni, F., Trtik, P., Zubler, R., Pouchon, M. A., & Bertsch, J. (2022). Delayed hydride cracking in Zircaloy-2 with and without liner at various temperatures investigated by high-resolution neutron radiography. Journal of Nuclear Materials, 561, 153549 (12 pp.). https://doi.org/10.1016/j.jnucmat.2022.153549
A NEA review on innovative structural materials solutions, including advanced manufacturing processes for nuclear applications based on technology readiness assessment
Balbaud, F., Cabet, C., Cornet, S., Dai, Y., Gan, J., Hernández Mayoral, M., … Weisenburger, A. (2021). A NEA review on innovative structural materials solutions, including advanced manufacturing processes for nuclear applications based on technology readiness assessment. Nuclear Materials and Energy, 27, 101006 (13 pp.). https://doi.org/10.1016/j.nme.2021.101006
Effect of the inner liner on radial delayed hydride cracking
Colldeweih, A. W., Fagnoni, F., Pouchon, M. A., Bertsch, J., & Trtik, P. (2021). Effect of the inner liner on radial delayed hydride cracking. In TopFuel2021 (p. (6 pp.). European Nuclear Society.
Quantitative APT analysis of solid transmutants in ferritic-martensitic steels after irradiation in SINQ targets: experimental validation of neutronic calculations
Cui, L., Li, J., Gerstl, S., Pouchon, M., & Dai, Y. (2021). Quantitative APT analysis of solid transmutants in ferritic-martensitic steels after irradiation in SINQ targets: experimental validation of neutronic calculations. Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms, 502, 1-9. https://doi.org/10.1016/j.nimb.2021.05.017
Post-irradiation examinations of SINQ Target-11
Dai, Y., Boutellier, V., Grabherr, R., Urech, A., Blau, B., Welte, J., … Wohlmuther, M. (2021). Post-irradiation examinations of SINQ Target-11. In K. Kikuchi (Ed.), Materials science forum: Vol. 1024. Spallation materials technology (pp. 41-52). https://doi.org/10.4028/www.scientific.net/MSF.1024.41
Framatome's evolutionary ATF solution: feedback from the irradiation programs on PROtect's Cr-coated M5<sub>Framatome</sub> cladding
Duquesne, L., Bischoff, J., Buchanan, K., Schweitzer, E., Nimishakavi, K., Girardin, G., … Pouchon, M. (2021). Framatome's evolutionary ATF solution: feedback from the irradiation programs on PROtect's Cr-coated M5Framatome cladding. In TopFuel2021 (p. (10 pp.). European Nuclear Society.
The high temperature gas-cooled reactor
Fütterer, M. A., Strydom, G., Sato, H., Li, F., Abonneau, E., Abram, T., … Yetisir, M. (2021). The high temperature gas-cooled reactor. In E. Greenspan (Ed.), Vol. 1. Encyclopedia of nuclear energy (pp. 512-522). https://doi.org/10.1016/B978-0-12-409548-9.12205-5
Modeling of sphere-pac fuel
Pouchon, M. A., Nordström, L. Å., & Hellwig, C. (2021). Modeling of sphere-pac fuel. In R. J. M. Konings & R. E. Stoller (Eds.), Vol. 5. Comprehensive nuclear materials (pp. 436-463). https://doi.org/10.1016/B978-0-08-102865-0.00068-6
Quantitative analysis of rhenium in irradiated tungsten
Warnicke, P., Ramanantoanina, H., Li, J., Dai, Y., & Pouchon, M. A. (2021). Quantitative analysis of rhenium in irradiated tungsten. Journal of Nuclear Materials, 554, 153014 (9 pp.). https://doi.org/10.1016/j.jnucmat.2021.153014
Influence of scattering correction on quantitative hydrogen analysis of fuel claddings using high resolution neutron radiography
Yetik, O., Duarte, L. I., Fagnoni, F., Colldeweih, A., Zubler, R., Pouchon, M. A., … Trtik, P. (2021). Influence of scattering correction on quantitative hydrogen analysis of fuel claddings using high resolution neutron radiography. In TopFuel2021 (p. (10 pp.). European Nuclear Society.
Sphere-pac and Vipac fuel
Pouchon, M. A., Ledergerber, G., Ingold, F., & Bakker, K. (2020). Sphere-pac and Vipac fuel. In R. J. M. Konings & R. E. Stoller (Eds.), Vol. 5. Comprehensive nuclear materials (pp. 398-435). https://doi.org/10.1016/B978-0-12-803581-8.12050-8
Simulation of the microfluidic mixing and the droplet generation for 3D printing of nuclear fuels
Shama, A., Pouchon, M. A., & Clifford, I. (2019). Simulation of the microfluidic mixing and the droplet generation for 3D printing of nuclear fuels. Additive Manufacturing, 26, 1-14. https://doi.org/10.1016/j.addma.2018.12.011
Advances in the GIF very high temperature reactor system
Fütterer, M. A., Li, F., Gougar, H., Edwards, L., Pouchon, M. A., Kim, M., … Sato, H. (2018). Advances in the GIF very high temperature reactor system. In 2018 GIF symposium proceedings (pp. 9-22). Generation IV International Forum.
Oxidation behaviors of SiC<sub>f</sub>/SiC composites tested at high temperature in air by an ablation method
Park, J. Y., Kim, D., Lee, H. G., Kim, W. J., & Pouchon, M. (2018). Oxidation behaviors of SiCf/SiC composites tested at high temperature in air by an ablation method. Journal of the Korean Ceramic Society, 55(5), 498-503. https://doi.org/10.4191/kcers.2018.55.5.03
Fabrication of CeO&lt;sub&gt;2&lt;/sub&gt; ceramic spheres as a surrogate of nuclear fuel by an improved microwave-assisted rapid internal gelation process
Tian, W., Pouchon, M. A., Guo, H., Chen, D., Yin, X., & Qin, Z. (2018). Fabrication of CeO2 ceramic spheres as a surrogate of nuclear fuel by an improved microwave-assisted rapid internal gelation process. Ceramics International, 44(6), 6739-6746. https://doi.org/10.1016/j.ceramint.2018.01.090
Preparation of UC ceramic nuclear fuel microspheres by combination of an improved microwave-assisted rapid internal gelation with carbothermic reduction process
Tian, W., Guo, H., Chen, D., Pouchon, M. A., Horwege, A., Yin, X., … Qin, Z. (2018). Preparation of UC ceramic nuclear fuel microspheres by combination of an improved microwave-assisted rapid internal gelation with carbothermic reduction process. Ceramics International, 44(15), 17945-17952. https://doi.org/10.1016/j.ceramint.2018.06.270
SiC cladding behavior: experiments and modelling at PSI
Cozzo, C., Bertsch, J., Fave, L., Rahman, S., Dokhane, A., Krack, M., … Pytel, M. (2017). SiC cladding behavior: experiments and modelling at PSI (p. (10 pp.). Presented at the Water reactor fuel performance meeting 2017 (WRFPM 2017). .
A radial heat flow apparatus for thermal conductivity characterisation of cylindrical samples
Fave, L., Pouchon, M. A., & Hébert, C. (2017). A radial heat flow apparatus for thermal conductivity characterisation of cylindrical samples. Journal of Thermal Analysis and Calorimetry, 130(3), 1855-1863. https://doi.org/10.1007/s10973-017-6578-8
Developing an in situ EXAFS experiment of microwave-induced gelation
Cozzo, C., Ishizaki, K., Pouchon, M. A., & Vaucher, S. (2016). Developing an in situ EXAFS experiment of microwave-induced gelation. Journal of Sol-Gel Science and Technology, 78(3), 507-513. https://doi.org/10.1007/s10971-016-3992-5
 

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