Pär Olsson

KTH Royal Institute of Technology — Sweden

Materials Science · Physical Sciences

38h-index5.5kcitations185works2.92yr avg
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Research Topics

Nuclear Materials and Properties(88), Fusion materials and technologies(87), Microstructure and Mechanical Properties of Steels(27), Microstructure and mechanical properties(26), Nuclear reactor physics and engineering(25)

Publications185 total

Irradiation-induced polymorphism in Fe–Cr alloys
Scientific Reports·2025Open Access
Assessing the near-surface diffusion of Xe and Kr in Zirconia by time-of-flight elastic recoil detection analysis
Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms·2025· 1 citedOpen Access
Fission product solubility and speciation in UN SIMFUEL
Journal of Nuclear Materials·2025· 1 citedOpen Access
Absence of percolation conductivity in uranium-zirconium nitrides
SSRN Electronic Journal·2025Open Access
Revealing the role of oxygen on the defect evolution of electron-irradiated tungsten: A combined experimental and simulation study
Journal of Nuclear Materials·2024· 3 citedOpen Access
First-principles predictions of structural and magnetic phase stability in irradiated <i>α</i> -Fe
Materials Research Letters·2024· 5 citedOpen Access
Temperature-dependent thermal conductivity and fuel performance of UN-UO2 and UN-X-UO2 (X=Mo, W) composite nuclear fuels by finite element modeling
Journal of Materiomics·2024· 7 citedOpen Access
Proton irradiation-induced cracking and microstructural defects in UN and (U,Zr)N composite fuels
Journal of Materiomics·2024· 8 citedOpen Access
Modeling of irradiation-induced microstructure evolution in Fe: Impact of Frenkel pair distribution
Computational Materials Science·2024· 5 citedOpen Access
Revealing the Role of Oxygen on the Microstructure of Electron-Irradiated Tungsten: A Combined Experimental and Simulation Study
SSRN Electronic Journal·2024· 2 citedOpen Access
U(X)N-Based Simfuel with X= Zr, Nb, Mo, and Ru: Fission Product Solubility and Speciation
SSRN Electronic Journal·2024Open Access
Microstructure and magnetization evolution in bcc iron via direct first-principles predictions of radiation effects
Physical Review Materials·2023· 5 citedOpen Access
Systematic investigation of positron annihilation in transition metals from first principles
Physical review. B./Physical review. B·2023· 15 cited
Corrigendum to “Modelling the primary damage in Fe and W: influence of the short-range interactions on the cascade properties: Part 2 –multivariate multiple linear regression analysis of displacement cascades: Journal of nuclear materials 549 (2021) 152887
Journal of Nuclear Materials·2023
Micromechanical modeling of single crystal and polycrystalline UO2 at elevated temperatures
Journal of Nuclear Materials·2022· 9 citedOpen Access
Effect of cationic chemical disorder on defect formation energies in uranium–plutonium mixed oxides
Journal of Applied Physics·2022· 1 citedOpen Access
Identification and evolution of ultrafine precipitates in Fe-Cu alloys by first-principles modeling of positron annihilation
Acta Materialia·2022· 15 citedOpen Access
Cu precipitation in electron-irradiated iron alloys for spent-fuel canisters
Journal of Nuclear Materials·2022· 1 citedOpen Access
A combined experimental and theoretical study of small and large vacancy clusters in tungsten
Journal of Nuclear Materials·2022· 25 citedOpen Access
Coated ZrN sphere-UO2 composites as surrogates for UN-UO2 accident tolerant fuels
Journal of Nuclear Materials·2022· 6 citedOpen Access
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Frequent Co-authors

Christophe Domain(16), L. Malerba(13), D. Terentyev(8), Janne Wallenius(6), Mihai‐Cosmin Marinica(6), G. Bonny(6), K. Nordlund(5), T.P.C. Klaver(5), Luca Messina(5), D. Terentyev(5), S. L. Dudarev(4), Antoine Claisse(4), Jörgen Carlsson(4), Lars Gedda(4), Igor A. Abrikosov(3), J. Wallenius(3), F. Willaime(3), Charlotte Becquart(3), Maylise Nastar(3), Jean‐François Guillemoles(3)