In-situ irradiation tolerance investigation of high strength ultrafine tungsten-titanium carbide alloy
Abstract
Refining grain size and adding alloying elements are two complementary approaches for enhancing the radiation tolerance of existing nuclear materials. Here, we present detailed in-situ irradiation research on defect evolution behavior and irradiation tolerance of ultrafine W-TiC alloys (thin foils) irradiated with I MeV Kr+2 at RT and 1073 K, and compare their overall performance to pure coarse grained tungsten. Loop Burgers vector was studied confirming the presence of <100> loops whose population increased at high temperature. Loop density, average loop area, and overall damage are reported as a function of irradiation dose revealing distinct defect evolution behavior from pure materials. The overall damage generally followed the average loop size trend, which decreased with time for both temperatures, but was higher at 1073 K and attributed to biased vacancy sink behavior of the TiC dispersoids evidenced by large vacancy clusters on their interfaces. By comparison, the overall loop and void damage in pure tungsten was larger by a factor of six and two, respectively. The improved irradiation damage resistance in the alloys is thus attributed to the effect of dispersoids in 1) the enhancement in annihilating defects and mutual defect recombination due to both dispersoids and a higher grain boundarymore »
- Authors:
-
- Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
- Stony Brook Univ., NY (United States). Dept. of Materials Science and Chemical Engineering
- Argonne National Lab. (ANL), Argonne, IL (United States). Division of Nuclear Engineering
- Stony Brook Univ., NY (United States). Dept. of Materials Science and Chemical Engineering. Inst. for Advanced Computational Science
- Publication Date:
- Research Org.:
- Argonne National Lab. (ANL), Argonne, IL (United States); Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
- Sponsoring Org.:
- USDOE Office of Science (SC), Fusion Energy Sciences (FES); USDOE Office of Nuclear Energy (NE)
- OSTI Identifier:
- 1483542
- Alternate Identifier(s):
- OSTI ID: 1503318; OSTI ID: 1636975
- Report Number(s):
- LA-UR-18-27540
Journal ID: ISSN 1359-6454
- Grant/Contract Number:
- AC02-06CH11357; AC07-05ID14517; SC0017899; AC07- 051D14517; 20160674PRD3
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Acta Materialia
- Additional Journal Information:
- Journal Volume: 164; Journal ID: ISSN 1359-6454
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 36 MATERIALS SCIENCE; tungsten alloy; ultrafine; electron microscopy; dislocation loops; Burgers vector; irradiation tolerance
Citation Formats
El-Atwani, O., Cunningham, W. S., Esquivel, E., Li, M., Trelewicz, J. R., Uberuaga, B. P., and Maloy, S. A. In-situ irradiation tolerance investigation of high strength ultrafine tungsten-titanium carbide alloy. United States: N. p., 2018.
Web. doi:10.1016/j.actamat.2018.10.038.
El-Atwani, O., Cunningham, W. S., Esquivel, E., Li, M., Trelewicz, J. R., Uberuaga, B. P., & Maloy, S. A. In-situ irradiation tolerance investigation of high strength ultrafine tungsten-titanium carbide alloy. United States. https://doi.org/10.1016/j.actamat.2018.10.038
El-Atwani, O., Cunningham, W. S., Esquivel, E., Li, M., Trelewicz, J. R., Uberuaga, B. P., and Maloy, S. A. Mon .
"In-situ irradiation tolerance investigation of high strength ultrafine tungsten-titanium carbide alloy". United States. https://doi.org/10.1016/j.actamat.2018.10.038. https://www.osti.gov/servlets/purl/1483542.
@article{osti_1483542,
title = {In-situ irradiation tolerance investigation of high strength ultrafine tungsten-titanium carbide alloy},
author = {El-Atwani, O. and Cunningham, W. S. and Esquivel, E. and Li, M. and Trelewicz, J. R. and Uberuaga, B. P. and Maloy, S. A.},
abstractNote = {Refining grain size and adding alloying elements are two complementary approaches for enhancing the radiation tolerance of existing nuclear materials. Here, we present detailed in-situ irradiation research on defect evolution behavior and irradiation tolerance of ultrafine W-TiC alloys (thin foils) irradiated with I MeV Kr+2 at RT and 1073 K, and compare their overall performance to pure coarse grained tungsten. Loop Burgers vector was studied confirming the presence of <100> loops whose population increased at high temperature. Loop density, average loop area, and overall damage are reported as a function of irradiation dose revealing distinct defect evolution behavior from pure materials. The overall damage generally followed the average loop size trend, which decreased with time for both temperatures, but was higher at 1073 K and attributed to biased vacancy sink behavior of the TiC dispersoids evidenced by large vacancy clusters on their interfaces. By comparison, the overall loop and void damage in pure tungsten was larger by a factor of six and two, respectively. The improved irradiation damage resistance in the alloys is thus attributed to the effect of dispersoids in 1) the enhancement in annihilating defects and mutual defect recombination due to both dispersoids and a higher grain boundary density; 2) decreasing the loop mobility, causing shrinkage and annihilation of loop density, which was confirmed via in-situ video. Several mechanisms are illustrated to describe the performance of the complex alloy system. The results motivate further experimental and modeling research that aims to understand the many different phenomena occurring at different time scales.},
doi = {10.1016/j.actamat.2018.10.038},
journal = {Acta Materialia},
number = ,
volume = 164,
place = {United States},
year = {Mon Oct 29 00:00:00 EDT 2018},
month = {Mon Oct 29 00:00:00 EDT 2018}
}
Web of Science
Figures / Tables:
Works referenced in this record:
Plasma–surface interaction, scrape-off layer and divertor physics: implications for ITER
journal, August 2007
- Lipschultz, B.; Bonnin, X.; Counsell, G.
- Nuclear Fusion, Vol. 47, Issue 9
Tungsten as material for plasma-facing components in fusion devices
journal, August 2011
- Philipps, V.
- Journal of Nuclear Materials, Vol. 415, Issue 1
Designing Radiation Resistance in Materials for Fusion Energy
journal, July 2014
- Zinkle, S. J.; Snead, L. L.
- Annual Review of Materials Research, Vol. 44, Issue 1
Materials research for fusion
journal, May 2016
- Knaster, J.; Moeslang, A.; Muroga, T.
- Nature Physics, Vol. 12, Issue 5
High temperature annealing of ion irradiated tungsten
journal, May 2015
- Ferroni, Francesco; Yi, Xiaoou; Arakawa, Kazuto
- Acta Materialia, Vol. 90
Characterisation of radiation damage in W and W-based alloys from 2 MeV self-ion near-bulk implantations
journal, June 2015
- Yi, Xiaoou; Jenkins, Michael L.; Hattar, Khalid
- Acta Materialia, Vol. 92
In-situ TEM studies of 150 keV W+ ion irradiated W and W-alloys: Damage production and microstructural evolution
journal, June 2016
- Yi, Xiaoou; Jenkins, Michael L.; Kirk, Marquis A.
- Acta Materialia, Vol. 112
In-situ TEM/heavy ion irradiation on ultrafine-and nanocrystalline-grained tungsten: Effect of 3 MeV Si, Cu and W ions
journal, January 2015
- El-Atwani, O.; Suslova, A.; Novakowski, T. J.
- Materials Characterization, Vol. 99
Radiation damage tolerant nanomaterials
journal, November 2013
- Beyerlein, I. J.; Caro, A.; Demkowicz, M. J.
- Materials Today, Vol. 16, Issue 11
Defect-interface interactions
journal, October 2015
- Beyerlein, I. J.; Demkowicz, M. J.; Misra, A.
- Progress in Materials Science, Vol. 74
Efficient Annealing of Radiation Damage Near Grain Boundaries via Interstitial Emission
journal, March 2010
- Bai, X. M.; Voter, A. F.; Hoagland, R. G.
- Science, Vol. 327, Issue 5973
Enhanced radiation tolerance in nanocrystalline MgGa2O4
journal, June 2007
- Shen, Tong D.; Feng, Shihai; Tang, Ming
- Applied Physics Letters, Vol. 90, Issue 26
Impact of irradiation on the microstructure of nanocrystalline materials
journal, August 2004
- Nita, N.; Schaeublin, R.; Victoria, M.
- Journal of Nuclear Materials, Vol. 329-333
Accumulation and recovery of defects in ion-irradiated nanocrystalline gold
journal, September 2001
- Chimi, Y.; Iwase, A.; Ishikawa, N.
- Journal of Nuclear Materials, Vol. 297, Issue 3
In situ studies on radiation tolerance of nanotwinned Cu
journal, June 2016
- Chen, Y.; Li, J.; Yu, K. Y.
- Acta Materialia, Vol. 111
In situ Evidence of Defect Cluster Absorption by Grain Boundaries in Kr Ion Irradiated Nanocrystalline Ni
journal, February 2013
- Sun, C.; Song, M.; Yu, K. Y.
- Metallurgical and Materials Transactions A, Vol. 44, Issue 4
The role of grain size in He bubble formation: Implications for swelling resistance
journal, February 2017
- El-Atwani, O.; Nathaniel, J. E.; Leff, A. C.
- Journal of Nuclear Materials, Vol. 484
In Situ Study of Defect Migration Kinetics and Self-Healing of Twin Boundaries in Heavy Ion Irradiated Nanotwinned Metals
journal, April 2015
- Li, J.; Yu, K. Y.; Chen, Y.
- Nano Letters, Vol. 15, Issue 5
Nanostructured metals under irradiation
journal, June 2009
- Wurster, Stefan; Pippan, Reinhard
- Scripta Materialia, Vol. 60, Issue 12
Mechanical properties of nanocrystalline materials
journal, May 2006
- Meyers, M. A.; Mishra, A.; Benson, D. J.
- Progress in Materials Science, Vol. 51, Issue 4
Microstructure and mechanical properties of super-strong nanocrystalline tungsten processed by high-pressure torsion
journal, September 2006
- Wei, Q.; Zhang, H.; Schuster, B.
- Acta Materialia, Vol. 54, Issue 15
Refinement of tungsten microstructure upon severe plastic deformation
journal, February 2014
- Ganeev, A. V.; Islamgaliev, R. K.; Valiev, R. Z.
- The Physics of Metals and Metallography, Vol. 115, Issue 2
Microstructure refinement of tungsten by surface deformation for irradiation damage resistance
journal, January 2014
- Efe, Mert; El-Atwani, Osman; Guo, Yang
- Scripta Materialia, Vol. 70
Nanocrystalline-grained tungsten prepared by surface mechanical attrition treatment: Microstructure and mechanical properties
journal, November 2016
- Guo, Hong-Yan; Xia, Min; Wu, Zheng-Tao
- Journal of Nuclear Materials, Vol. 480
Design of Stable Nanocrystalline Alloys
journal, August 2012
- Chookajorn, T.; Murdoch, H. A.; Schuh, C. A.
- Science, Vol. 337, Issue 6097
Solute stabilization of nanocrystalline tungsten against abnormal grain growth
journal, September 2017
- Donaldson, Olivia K.; Hattar, Khalid; Kaub, Tyler
- Journal of Materials Research, Vol. 33, Issue 1
Powder-Route Synthesis and Mechanical Testing of Ultrafine Grain Tungsten Alloys
journal, April 2014
- Cordero, Zachary C.; Huskins, Emily L.; Park, Mansoo
- Metallurgical and Materials Transactions A, Vol. 45, Issue 8
Microstructure and Bend Ductility of W-0.3 mass%TiC Alloys Fabricated by Advanced Powder-Metallurgical Processing
journal, January 2005
- Ishijima, Yasuhiro; Kurishita, Hiroaki; Arakawa, Hideo
- MATERIALS TRANSACTIONS, Vol. 46, Issue 3
Development of ultra-fine grained W–TiC and their mechanical properties for fusion applications
journal, August 2007
- Kurishita, H.; Amano, Y.; Kobayashi, S.
- Journal of Nuclear Materials, Vol. 367-370
Development of Nanostructured Tungsten Based Materials Resistant to Recrystallization and/or Radiation Induced Embrittlement
journal, January 2013
- Kurishita, H.; Arakawa, H.; Matsuo, S.
- MATERIALS TRANSACTIONS, Vol. 54, Issue 4
Superplastic deformation in W–0.5wt.% TiC with approximately 0.1μm grain size
journal, March 2008
- Kurishita, H.; Matsuo, S.; Arakawa, H.
- Materials Science and Engineering: A, Vol. 477, Issue 1-2
Deformability enhancement in ultra-fine grained, Ar-contained W compacts by TiC additions up to 1.1%
journal, September 2008
- Matsuo, S.; Kurishita, H.; Arakawa, H.
- Materials Science and Engineering: A, Vol. 492, Issue 1-2
Microstructure and impact properties of ultra-fine grained tungsten alloys dispersed with TiC
journal, May 1999
- Kitsunai, Yuji; Kurishita, Hiroaki; Kayano, Hideo
- Journal of Nuclear Materials, Vol. 271-272
High temperature tensile properties and their application to toughness enhancement in ultra-fine grained W-(0-1.5)wt% TiC
journal, April 2009
- Kurishita, H.; Matsuo, S.; Arakawa, H.
- Journal of Nuclear Materials, Vol. 386-388
SRIM – The stopping and range of ions in matter (2010)
journal, June 2010
- Ziegler, James F.; Ziegler, M. D.; Biersack, J. P.
- Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 268, Issue 11-12
Loop and void damage during heavy ion irradiation on nanocrystalline and coarse grained tungsten: Microstructure, effect of dpa rate, temperature, and grain size
journal, May 2018
- El-Atwani, O.; Esquivel, E.; Efe, M.
- Acta Materialia, Vol. 149
Characterisation of radiation-damage microstructures by TEM
journal, October 1994
- Jenkins, M. L.
- Journal of Nuclear Materials, Vol. 216
Neutron irradiation hardening and microstructure changes in Fe–Mn binary alloys
journal, July 2011
- Yabuuchi, Kiyohiro; Saito, Masashi; Kasada, Ryuta
- Journal of Nuclear Materials, Vol. 414, Issue 3
Displacement cascades and defects annealing in tungsten, Part I: Defect database from molecular dynamics simulations
journal, July 2015
- Setyawan, Wahyu; Nandipati, Giridhar; Roche, Kenneth J.
- Journal of Nuclear Materials, Vol. 462
Structure and metastability of mesoscopic vacancy and interstitial loop defects in iron and tungsten
journal, August 2008
- Gilbert, M. R.; Dudarev, S. L.; Derlet, P. M.
- Journal of Physics: Condensed Matter, Vol. 20, Issue 34
Development of ultra-fine grained W–(0.25–0.8)wt%TiC and its superior resistance to neutron and 3MeV He-ion irradiations
journal, June 2008
- Kurishita, H.; Kobayashi, S.; Nakai, K.
- Journal of Nuclear Materials, Vol. 377, Issue 1
Observations of suppressed retention and blistering for tungsten exposed to deuterium–helium mixture plasmas
journal, May 2009
- Miyamoto, M.; Nishijima, D.; Ueda, Y.
- Nuclear Fusion, Vol. 49, Issue 6
Direct Observation of Sink-Dependent Defect Evolution in Nanocrystalline Iron under Irradiation
journal, May 2017
- El-Atwani, O.; Nathaniel, J. E.; Leff, A. C.
- Scientific Reports, Vol. 7, Issue 1
First temperature stage evolution of irradiation-induced defects in tungsten studied by positron annihilation spectroscopy
journal, May 2008
- Debelle, A.; Barthe, M. F.; Sauvage, T.
- Journal of Nuclear Materials, Vol. 376, Issue 2
Vacancy defect mobilities and binding energies obtained from annealing studies
journal, February 1978
- Balluffi, R. W.
- Journal of Nuclear Materials, Vol. 69-70
Defect Distributions and Transport in Nanocomposites: A Theoretical Perspective
journal, July 2013
- Pedro Uberuaga, Blas; Martinez, Enrique; Bi, Zhenxing
- Materials Research Letters, Vol. 1, Issue 4
Detailed transmission electron microscopy study on the mechanism of dislocation loop rafting in tungsten
journal, April 2018
- El-Atwani, O.; Aydogan, E.; Esquivel, E.
- Acta Materialia, Vol. 147
“Rafting” in neutron irradiated tungsten
journal, March 1973
- Sikka, V. K.; Moteff, J.
- Journal of Nuclear Materials, Vol. 46, Issue 2
Reduction of helium embrittlement in stainless steel by finely dispersed TiC precipitates
journal, January 1981
- Kesternich, W.; Rothaut, J.
- Journal of Nuclear Materials, Vol. 104
Elastic trapping of dislocation loops in cascades in ion-irradiated tungsten foils
journal, August 2014
- Mason, D. R.; Yi, X.; Kirk, M. A.
- Journal of Physics: Condensed Matter, Vol. 26, Issue 37
Effect of grain boundary character on sink efficiency
journal, October 2012
- Han, W. Z.; Demkowicz, M. J.; Fu, E. G.
- Acta Materialia, Vol. 60, Issue 18
Works referencing / citing this record:
Ion beam analysis of fusion plasma-facing materials and components: facilities and research challenges
journal, December 2019
- Mayer, M.; Möller, S.; Rubel, M.
- Nuclear Fusion, Vol. 60, Issue 2
W–Cu composites with submicron- and nanostructures: progress and challenges
journal, December 2019
- Hou, Chao; Song, Xiaoyan; Tang, Fawei
- NPG Asia Materials, Vol. 11, Issue 1
Figures / Tables found in this record: