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Title: 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. We present detailed in-situ irradiation research on defect evolution behavior and irradiation tolerance of ultrafine W-TiC alloys (thin foils) irradiated with 1 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 » 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. Finally, the results motivate further experimental and modeling research that aims to understand the many different phenomena occurring at different time scales.« less

Authors:
 [1]; ORCiD logo [2];  [1];  [3]; ORCiD logo [4]; ORCiD logo [1]; ORCiD logo [1]
  1. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
  2. Stony Brook Univ., NY (United States). Dept. of Materials Science and Chemical Engineering
  3. Argonne National Lab. (ANL), Argonne, IL (United States). Division of Nuclear Engineering
  4. 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)
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:
Journal Article: 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. doi: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. doi: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. We present detailed in-situ irradiation research on defect evolution behavior and irradiation tolerance of ultrafine W-TiC alloys (thin foils) irradiated with 1 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. Finally, 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},
issn = {1359-6454},
number = ,
volume = 164,
place = {United States},
year = {2018},
month = {10}
}

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Figures / Tables:

Figure 1 Figure 1: (a) TEM bright-field micrograph of the as-received W-TiC (1.1%) sample showing TiC dispersoids on the grain boundaries as well as the grain matrices. Insert shows the diffraction pattern rings of pure W and TiC dispersoids. (b) Cross-section FIB image (using the secondary electrons of the gallium ion beam)more » showing no grain size or dispersoid density change with depth.« less

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