Controlling diffusion for a self-healing radiation tolerant nanostructured ferritic alloy
Abstract
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.
- Authors:
-
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Publication Date:
- Research Org.:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Org.:
- USDOE Office of Science (SC), Basic Energy Sciences (BES)
- OSTI Identifier:
- 1237626
- Alternate Identifier(s):
- OSTI ID: 1246585
- Grant/Contract Number:
- AC05-00OR22725
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Journal of Nuclear Materials
- Additional Journal Information:
- Journal Volume: 462; Journal Issue: C; Journal ID: ISSN 0022-3115
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 77 NANOSCIENCE AND NANOTECHNOLOGY; 36 MATERIALS SCIENCE
Citation Formats
Miller, Michael K., Parish, Chad M., and Bei, Hongbin. Controlling diffusion for a self-healing radiation tolerant nanostructured ferritic alloy. United States: N. p., 2014.
Web. doi:10.1016/j.jnucmat.2014.12.048.
Miller, Michael K., Parish, Chad M., & Bei, Hongbin. Controlling diffusion for a self-healing radiation tolerant nanostructured ferritic alloy. United States. https://doi.org/10.1016/j.jnucmat.2014.12.048
Miller, Michael K., Parish, Chad M., and Bei, Hongbin. Thu .
"Controlling diffusion for a self-healing radiation tolerant nanostructured ferritic alloy". United States. https://doi.org/10.1016/j.jnucmat.2014.12.048. https://www.osti.gov/servlets/purl/1237626.
@article{osti_1237626,
title = {Controlling diffusion for a self-healing radiation tolerant nanostructured ferritic alloy},
author = {Miller, Michael K. and Parish, Chad M. and Bei, Hongbin},
abstractNote = {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.},
doi = {10.1016/j.jnucmat.2014.12.048},
journal = {Journal of Nuclear Materials},
number = C,
volume = 462,
place = {United States},
year = {Thu Dec 18 00:00:00 EST 2014},
month = {Thu Dec 18 00:00:00 EST 2014}
}
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Works referenced in this record:
Structural materials for fission & fusion energy
journal, November 2009
- Zinkle, Steven J.; Busby, Jeremy T.
- Materials Today, Vol. 12, Issue 11
Materials challenges in nuclear energy
journal, February 2013
- Zinkle, S. J.; Was, G. S.
- Acta Materialia, Vol. 61, Issue 3
Energetic Displacement Cascades and Their Roles in Radiation Effects
journal, January 1987
- Averback, Robert S.; Seidman, David N.
- Materials Science Forum, Vol. 15-18
Displacement Cascades. Dynamics and Atomic Structure
journal, November 1987
- Seidman, D. N.; Averback, R. S.; Benedek, K.
- physica status solidi (b), Vol. 144, Issue 1
Reduced-activation steels: Future development for improved creep strength
journal, August 2008
- Klueh, R. L.
- Journal of Nuclear Materials, Vol. 378, Issue 2
Structural materials for Gen-IV nuclear reactors: Challenges and opportunities
journal, December 2008
- Murty, K. L.; Charit, I.
- Journal of Nuclear Materials, Vol. 383, Issue 1-2
Recent Developments in Irradiation-Resistant Steels
journal, August 2008
- Odette, G. R.; Alinger, M. J.; Wirth, B. D.
- Annual Review of Materials Research, Vol. 38, Issue 1, p. 471-503
Perspective of ODS alloys application in nuclear environments
journal, December 2002
- Ukai, Shigeharu; Fujiwara, Masayuki
- Journal of Nuclear Materials, Vol. 307-311, p. 749-757
Atom probe tomography of nanoscale particles in ODS ferritic alloys
journal, July 2003
- Miller, M. K.; Kenik, E. A.; Russell, K. F.
- Materials Science and Engineering: A, Vol. 353, Issue 1-2
On the role of alloy composition and processing parameters in nanocluster formation and dispersion strengthening in nanostuctured ferritic alloys
journal, January 2009
- Alinger, M. J.; Odette, G. R.; Hoelzer, D. T.
- Acta Materialia, Vol. 57, Issue 2
Role of alloying elements in nanostructured ferritic steels
journal, April 2011
- Miller, M. K.; Parish, C. M.
- Materials Science and Technology, Vol. 27, Issue 4
Effect of neutron irradiation on nanoclusters in MA957 ferritic alloys
journal, November 2011
- Miller, M. K.; Hoelzer, D. T.
- Journal of Nuclear Materials, Vol. 418, Issue 1-3
Limits of detectability for clusters and solute segregation to grain boundaries
journal, October 2013
- Miller, M. K.; Yao, L.
- Current Opinion in Solid State and Materials Science, Vol. 17, Issue 5
Radiation stability of nanoclusters in nano-structured oxide dispersion strengthened (ODS) steels
journal, March 2013
- Certain, A.; Kuchibhatla, S.; Shutthanandan, V.
- Journal of Nuclear Materials, Vol. 434, Issue 1-3
Stability of nanoclusters in 14YWT oxide dispersion strengthened steel under heavy ion-irradiation by atom probe tomography
journal, December 2014
- He, Jianchao; Wan, Farong; Sridharan, Kumar
- Journal of Nuclear Materials, Vol. 455, Issue 1-3
Vacancy Mechanism of High Oxygen Solubility and Nucleation of Stable Oxygen-Enriched Clusters in Fe
journal, November 2007
- Fu, C. L.; Krčmar, Maja; Painter, G. S.
- Physical Review Letters, Vol. 99, Issue 22
Vacancies as a constitutive element for the design of nanocluster-strengthened ferritic steels
journal, November 2008
- Miller, M. K.; Fu, C. L.; Krcmar, M.
- Frontiers of Materials Science in China, Vol. 3, Issue 1
Detection and quantification of solute clusters in a nanostructured ferritic alloy
journal, July 2015
- Miller, M. K.; Reinhard, D.; Larson, D. J.
- Journal of Nuclear Materials, Vol. 462
Ultrafine-grained nanocluster-strengthened alloys with unusually high creep strength
journal, October 2009
- Schneibel, J. H.; Liu, C. T.; Miller, M. K.
- Scripta Materialia, Vol. 61, Issue 8
Fabrication and characterization of APT specimens from high dose heavy ion irradiated materials
journal, May 2011
- Miller, M. K.; Zhang, Y.
- Ultramicroscopy, Vol. 111, Issue 6
Review of Atom Probe FIB-Based Specimen Preparation Methods
journal, November 2007
- Miller, Michael K.; Russell, Kaye F.; Thompson, Keith
- Microscopy and Microanalysis, Vol. 13, Issue 6
On the use of SRIM for computing radiation damage exposure
journal, September 2013
- Stoller, R. E.; Toloczko, M. B.; Was, G. S.
- Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 310
Measurement of hardness and elastic modulus by instrumented indentation: Advances in understanding and refinements to methodology
journal, January 2004
- Oliver, W. C.; Pharr, G. M.
- Journal of Materials Research, Vol. 19, Issue 1
Effects of heavy-ion irradiation on the grain boundary chemistry of an oxide-dispersion strengthened Fe–12wt.% Cr alloy
journal, October 2011
- Marquis, Emmanuelle A.; Lozano-Perez, Sergio; Castro, Vanessa de
- Journal of Nuclear Materials, Vol. 417, Issue 1-3
Works referencing / citing this record:
Oxygen-18 Tracer Measurements of Anion Diffusion in Uranium Dioxide Thin Films
journal, September 2019
- Bernhardt, Joseph R.; Han, Xiaochun; Heuser, Brent J.
- JOM, Vol. 71, Issue 12
In Situ Studies on the Irradiation-Induced Twin Boundary-Defect Interactions in Cu
journal, August 2017
- Fan, C.; Li, Jin; Fan, Zhe
- Metallurgical and Materials Transactions A, Vol. 48, Issue 11
Advanced Materials for Next‐Generation Spacecraft
journal, August 2018
- Levchenko, Igor; Bazaka, Kateryna; Belmonte, Thierry
- Advanced Materials, Vol. 30, Issue 50