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
64 2013 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
56 2016 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
56 2016 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
54 2019 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
45 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
26 2016 Transport properties in dilute 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
16 2021 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
15 2015 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
14 2022 Understanding the interface interaction between U3 Si2 fuel and SiC cladding V Kocevski, DA Lopes, AJ Claisse, TM Besmann
Nature Communications 11 (1), 2621, 2020
13 2020 DFT + U Study of the Adsorption and Dissociation of Water on Clean, Defective, and Oxygen-Covered U3 Si2 {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
13 2019 Hydrogen solubility in Zr–Nb alloys V Tuli, A Claisse, PA Burr
Scripta Materialia 214, 114652, 2022
12 2022 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 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
9 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
9 2017 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
8 2021 Compatibility of UN with refractory metals (V, Nb, Ta, Cr, Mo and W): an ab initio approach to interface reactions and diffusion behavior H Liu, DR Costa, DA Lopes, A Claisse, L Messina, P Olsson
Journal of Nuclear Materials 560, 153482, 2022
7 2022 Impact of fission product inclusion on phase development in U3Si2 fuel TJ Johnson, DL Adorno, V Kocevski, TL Ulrich, JT White, A Claisse, ...
Journal of Nuclear Materials 537, 152235, 2020
7 2020 