Defect evolution in Ni and solid-solution alloys of NiFe and NiFeCoCr under ion irradiation at 16 and 300 K

Mieszczynski, C.; Ratajczak, R.; Jagielski, J.; Velişa, G.; Bei, H.; Sales, B. C.; Wendler, E.; Weber, W. J.; Zhang, Y.

doi:10.1016/j.jnucmat.2020.152138

Title: Defect evolution in Ni and solid-solution alloys of NiFe and NiFeCoCr under ion irradiation at 16 and 300 K

Journal Article · Mon Jun 01 00:00:00 EDT 2020 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2020.152138· OSTI ID:1649245

Mieszczynski, C. ^[1]; Ratajczak, R. ^[1]; Jagielski, J. ^[2]; Velişa, G. ^[3]; Bei, H. ^[4]; Sales, B. C. ^[3]; Wendler, E. ^[5]; Weber, W. J. ^[6]; Zhang, Y. ^[6]

National Center for Nuclear Research, Otwock-Swierk (Poland). NOMATEN MAB+ Group
National Center for Nuclear Research, Otwock-Swierk (Poland). NOMATEN MAB+ Group; Lukasiewicz Research Network, Inst. of Electronic Materials Technology, Warsaw (Poland)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Univ. of Tennessee, Knoxville, TN (United States)
Friedrich Schiller Univ., Jena (Germany). Inst. fuer Festkoerperphysik
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Univ. of Tennessee, Knoxville, TN (United States)

Single-phase concentrated solid-solution alloys (SP-CSAs) have shown unique chemical complexity at the levels of electrons and atoms, and their defect evolution is expected to be different from conventional dilute alloys. Single crystals of Ni, NiFe and NiFeCoCr are chosen as model systems to understand the chemical complexity on defect formation and damage accumulation in SP-CSAs under ion irradiation. The high-quality crystals were irradiated at 16 and 300 K to different ion fluences, to form irradiated region with little to heavy damages. Additionally, the ion-induced damage was determined using Rutherford backscattering spectrometry technique along a channeling direction (RBS/C) and the level of lattice damage in irradiated Ni and SP-CSAs was quantified from Monte Carlo (MC) simulations. The results are interpreted using the Multi Step Damage Accumulation model to reveal material damage accumulation kinetics. Key findings of the study are that in case of room temperature irradiations the damage level measured for complex alloys at the highest irradiation fluence of 2 × 10¹⁵ cm^-2 (~3 dpa) is significantly higher than that obtained for pure nickel samples and suggest two-step damage accumulation process with a defect transformation taking place at a fluence of about 1.5 × 10¹⁵ cm^-2. Furthermore, structural and damage kinetic differences clearly imply that, with increasing degree of chemical complexity and high solid-solution strengthening effects from Ni to NiFe and to NiFeCoCr, the enhanced lattice stiffness resists to randomization of atomic configurations and inhibits the growth of extended defects.

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Research Organization:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE Office of Science (SC), Basic Energy Sciences (BES). Materials Sciences & Engineering Division; USDOE Office of Science (SC), Basic Energy Sciences (BES)

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1649245

Alternate ID(s):: OSTI ID: 1615675

Journal Information:: Journal of Nuclear Materials, Vol. 534, Issue N/A; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 8 works

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