First-principles calculations of (Y, Ti, O) cluster formation in body centred cubic iron-chromium A Claisse, P Olsson Nuclear Instruments and Methods in Physics Research Section B: Beam …, 2013 | 63 | 2013 |
Density functional theory calculations of self-and Xe diffusion in U3Si2 DA Andersson, XY Liu, B Beeler, SC Middleburgh, A Claisse, CR Stanek Journal of Nuclear Materials 515, 312-325, 2019 | 53 | 2019 |
Spark plasma sintering and porosity studies of uranium nitride KD Johnson, J Wallenius, M Jolkkonen, A Claisse Journal of Nuclear Materials 473, 13-17, 2016 | 52 | 2016 |
GGA+ U study of uranium mononitride: A comparison of the U-ramping and occupation matrix schemes and incorporation energies of fission products A Claisse, M Klipfel, N Lindbom, M Freyss, P Olsson Journal of Nuclear Materials 478, 119-124, 2016 | 48 | 2016 |
Solution of hydrogen in accident tolerant fuel candidate material: U3Si2 SC Middleburgh, A Claisse, DA Andersson, RW Grimes, P Olsson, ... Journal of Nuclear Materials 501, 234-237, 2018 | 42 | 2018 |
Ab-initio study of C and O impurities in uranium nitride DA Lopes, A Claisse, P Olsson Journal of Nuclear Materials 478, 112-118, 2016 | 25 | 2016 |
Transport properties in dilute solid solutions A Claisse, T Schuler, DA Lopes, P Olsson Physical Review B 94 (17), 174302, 2016 | 21 | 2016 |
Choosing the correct strong correlation correction for U3Si2: Influence of magnetism H Liu, A Claisse, SC Middleburgh, P Olsson Journal of Nuclear Materials 527, 151828, 2019 | 18 | 2019 |
Diffusion in doped and undoped amorphous zirconia MW Owen, MJD Rushton, LJ Evitts, A Claisse, M Puide, WE Lee, ... Journal of Nuclear Materials 555, 153108, 2021 | 15 | 2021 |
Understanding the interface interaction between U3Si2 fuel and SiC cladding V Kocevski, DA Lopes, AJ Claisse, TM Besmann Nature Communications 11 (1), 2621, 2020 | 12 | 2020 |
DFT + U Study of the Adsorption and Dissociation of Water on Clean, Defective, and Oxygen-Covered U3Si2{001}, {110}, and {111} Surfaces E Jossou, L Malakkal, NY Dzade, A Claisse, B Szpunar, J Szpunar The Journal of Physical Chemistry C 123 (32), 19453-19467, 2019 | 11 | 2019 |
Towards the inclusion of open fabrication porosity in a fission gas release model A Claisse, P Van Uffelen Journal of Nuclear Materials 466, 351-356, 2015 | 11 | 2015 |
ELECTRA: A lead cooled reactor for training and education J Wallenius, E Suvdantsetseg, S Bortot, JM Pukari М, A Claisse, P Olsson, ... ELECTRA 1999 (1998), 1997, 2000 | 11 | 2000 |
Development and application of a uranium mononitride (UN) potential: Thermomechanical properties and Xe diffusion V Kocevski, MWD Cooper, AJ Claisse, DA Andersson Journal of Nuclear Materials 562, 153553, 2022 | 9 | 2022 |
Experimental and computational assessment of USiN ternary phases DA Lopes, TL Wilson, V Kocevski, EE Moore, TM Besmann, ES Wood, ... Journal of Nuclear Materials 516, 194-201, 2019 | 8 | 2019 |
Transport properties of C and O in UN fuels T Schuler, DA Lopes, A Claisse, P Olsson Physical Review B 95 (9), 094117, 2017 | 8 | 2017 |
Hydrogen solubility in Zr–Nb alloys V Tuli, A Claisse, PA Burr Scripta Materialia 214, 114652, 2022 | 7 | 2022 |
Solubility and vacancy-mediated inter-diffusion in the Zr-Nb-Cr system V Tuli, A Claisse, L Messina, PA Burr Journal of Nuclear Materials 548, 152867, 2021 | 7 | 2021 |
Impact of fission product inclusion on phase development in U3Si2 fuel KE Johnson, DL Adorno, V Kocevski, TL Ulrich, JT White, A Claisse, ... Journal of Nuclear Materials 537, 152235, 2020 | 6 | 2020 |
Diffusion in undoped and Cr-doped amorphous UO2 MW Owen, MWD Cooper, MJD Rushton, A Claisse, WE Lee, ... Journal of Nuclear Materials 576, 154270, 2023 | 5 | 2023 |