Controlling diffusion for a self-healing radiation tolerant nanostructured ferritic alloy

Miller, Michael K.; Parish, Chad M.; Bei, Hongbin

doi:10.1016/j.jnucmat.2014.12.048

Title: Controlling diffusion for a self-healing radiation tolerant nanostructured ferritic alloy

Journal Article · Thu Dec 18 00:00:00 EST 2014 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2014.12.048· OSTI ID:1237626

Miller, Michael K. ^[1]; Parish, Chad M. ^[1]; Bei, Hongbin ^[1]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

Diffusion plays a major role in the stability of microstructures to extreme conditions of high temperature and high doses of irradiation. In nanostructured ferritic alloys, first principle calculations indicate that the binding energy of vacancies is reduced by the presence of oxygen, titanium and yttrium atoms. Therefore, the number of free vacancies available for diffusion can be greatly reduced. The mechanical properties of these alloys, compared to traditional wrought alloys of similar composition and grain structure, is distinctly different, and the ultrafine grained alloy is distinguished by a high number density of Ti–Y–O-enriched nanoclusters and solute clusters, which drives the mechanical response. When a displacement cascade interacts with a nanocluster, the solute atoms are locally dispersed into the matrix by ballistic collisions, but immediately a new nanocluster reforms due to the local supersaturation of solutes and vacancies until the excess vacancies are consumed. Furthermore, the result of these processes is a structural material for advanced energy systems with a microstructure that is self-healing and tolerant to high doses of radiation and high temperatures.

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

Sponsoring Organization:: USDOE Office of Science (SC), Basic Energy Sciences (BES)

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1237626

Alternate ID(s):: OSTI ID: 1246585

Journal Information:: Journal of Nuclear Materials, Vol. 462, Issue C; 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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Oxygen-18 Tracer Measurements of Anion Diffusion in Uranium Dioxide Thin Films Bernhardt, Joseph R.; Han, Xiaochun; Heuser, Brent J. JOM, Vol. 71, Issue 12 https://doi.org/10.1007/s11837-019-03796-y	journal	September 2019
In Situ Studies on the Irradiation-Induced Twin Boundary-Defect Interactions in Cu Fan, C.; Li, Jin; Fan, Zhe Metallurgical and Materials Transactions A, Vol. 48, Issue 11 https://doi.org/10.1007/s11661-017-4293-5	journal	August 2017
Advanced Materials for Next‐Generation Spacecraft Levchenko, Igor; Bazaka, Kateryna; Belmonte, Thierry Advanced Materials, Vol. 30, Issue 50 https://doi.org/10.1002/adma.201802201	journal	August 2018

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