A.V. Barashev

University of Michigan–Ann Arbor — United States

Materials Science · Physical Sciences

28h-index2.7kcitations69works0.02yr avg
OpenAlex↗Google Scholar↗Lab page↗

Accepting Students?

No reports yet. Know if this professor is taking students?

Research Topics

Fusion materials and technologies(55), Nuclear Materials and Properties(51), Ion-surface interactions and analysis(19), Nuclear materials and radiation effects(11), High-Temperature Coating Behaviors(7)

Publications69 total

Cluster dynamics simulation of Zr hydrides formation on grain boundaries in Zr
Journal of Nuclear Materials·2022· 3 cited
Sluggish, chemical bias and percolation phenomena in atomic transport by vacancy and interstitial diffusion in Ni Fe alloys
Current Opinion in Solid State and Materials Science·2021· 28 citedOpen Access
Accelerated kinetic Monte Carlo: A case study; vacancy and dumbbell interstitial diffusion traps in concentrated solid solution alloys
The Journal of Chemical Physics·2020· 29 citedOpen Access
Tunable chemical complexity to control atomic diffusion in alloys
npj Computational Materials·2020· 56 citedOpen Access
Frenkel defect recombination in Ni and Ni‒containing concentrated solid‒solution alloys
Acta Materialia·2019· 64 citedOpen Access
Chemically-biased diffusion and segregation impede void growth in irradiated Ni-Fe alloys
Current Opinion in Solid State and Materials Science·2018· 40 citedOpen Access
Dynamics of interaction between dislocations and point defects in bcc iron
Physical Review Materials·2018· 15 citedOpen Access
On the mobility of defect clusters and their effect on microstructure evolution in fcc Ni under irradiation
Materialia·2018· 13 citedOpen Access
On the existence and origin of sluggish diffusion in chemically disordered concentrated alloys
Current Opinion in Solid State and Materials Science·2018· 126 citedOpen Access
Theoretical Study of Swelling of Structural Materials in Light Water Reactors at High Fluencies
˜The œminerals, metals & materials series·2017· 1 cited
Theoretical Study of Swelling of Structural Materials in Light Water Reactors at High Fluencies
˜The œminerals, metals & materials series·2017
Study of High Fluence Radiation-induced Swelling and Hardening under Light Water Reactor Conditions
2016Open Access
On the irradiation creep by climb-enabled glide of dislocations
Journal of Nuclear Materials·2016· 2 citedOpen Access
Reaction Rate Theory
Elsevier eBooks·2015· 14 cited
Corrigendum to “Theoretical investigation of microstructure evolution and deformation of zirconium under neutron irradiation” [J. Nucl. Mater. 461 (2015) 85–94]
Journal of Nuclear Materials·2015· 1 citedOpen Access
Swelling In Light Water Reactor Internal Components: Insights from Computational Modeling
2015Open Access
Theoretical investigation of microstructure evolution and deformation of zirconium under neutron irradiation
Journal of Nuclear Materials·2015· 65 citedOpen Access
Low-temperature swelling in LWR internal components: a computational assessment
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)·2015Open Access
Breakthrough in Understanding Radiation Growth of Zirconium
2014· 27 cited
The behavior of small helium clusters near free surfaces in tungsten
Journal of Nuclear Materials·2014· 35 citedOpen Access
page 1 of 4Next →

Frequent Co-authors

S.I. Golubov(20), Yuri N. Osetsky(12), Yu.N. Osetsky(11), R.E. Stoller(11), David Bacon(9), Yanwen Zhang(7), B.N. Singh(4), L. Malerba(4), A. C. Arokiam(4), D. J. Bacon(4), H. Trinkaus(3), A. Serra(3), A.F. Calder(3), Laurent Karim Béland(3), D. Terentyev(3), K. Tapasa(2), Pär Olsson(2), Zhongwen Yao(2), Keyvan Ferasat(2), H.L. Heinisch(2)