In-situ TEM studies of 150 keV W+ ion irradiated W and W-alloys: Damage production and microstructural evolution. (15th June 2016)
- Record Type:
- Journal Article
- Title:
- In-situ TEM studies of 150 keV W+ ion irradiated W and W-alloys: Damage production and microstructural evolution. (15th June 2016)
- Main Title:
- In-situ TEM studies of 150 keV W+ ion irradiated W and W-alloys: Damage production and microstructural evolution
- Authors:
- Yi, Xiaoou
Jenkins, Michael L.
Kirk, Marquis A.
Zhou, Zhongfu
Roberts, Steven G. - Abstract:
- Abstract: In-situ irradiations with 150 keV W + ions have been performed on W and W-5wt.% (Re; Ta; V) alloys in a comprehensive study of the influences of irradiation temperature Tirr, dose, alloying elements and grain orientations on radiation damage production and microstructural evolution. For Tirr between 30 K and 1073 K, the first observable defects in pure W appeared at doses ≤0.01 dpa, and were most likely vacancy loops, with Burgers vectors predominantly of typeb = ½ <111>. With increasing Tirr, the retained defect concentration decreased strongly and the maximum cluster size increased from ∼1300 point defects at 30 K to ∼2300 point defects at 1073 K. At all irradiation temperatures, the evolution of damage microstructures with dose from 0.1 to 1.0 dpa involved defect cluster migration, with mutual elastic interactions often leading to spatial inhomogeneities and loop reactions. In pure W, spatial ordering of loops was observed at doses >0.4 dpa and Tirr ≥ 773 K in grains close toz = <001>. No such ordering was found in similar grain orientations for the W-(Re; Ta) alloys, but it was found in the non-z = <001> grains. Post-irradiation analysis on W and W-5 wt% (Re; Ta) at 1.0 dpa showed that ½ <111> and <100> loops of both vacancy and interstitial type were present, at number densities ∼ 10 15 loops m −2 . In all cases ½ <111> loops were dominant, the fraction of these with interstitial nature increased with Tirr, and the proportion of <100> loops decreased withAbstract: In-situ irradiations with 150 keV W + ions have been performed on W and W-5wt.% (Re; Ta; V) alloys in a comprehensive study of the influences of irradiation temperature Tirr, dose, alloying elements and grain orientations on radiation damage production and microstructural evolution. For Tirr between 30 K and 1073 K, the first observable defects in pure W appeared at doses ≤0.01 dpa, and were most likely vacancy loops, with Burgers vectors predominantly of typeb = ½ <111>. With increasing Tirr, the retained defect concentration decreased strongly and the maximum cluster size increased from ∼1300 point defects at 30 K to ∼2300 point defects at 1073 K. At all irradiation temperatures, the evolution of damage microstructures with dose from 0.1 to 1.0 dpa involved defect cluster migration, with mutual elastic interactions often leading to spatial inhomogeneities and loop reactions. In pure W, spatial ordering of loops was observed at doses >0.4 dpa and Tirr ≥ 773 K in grains close toz = <001>. No such ordering was found in similar grain orientations for the W-(Re; Ta) alloys, but it was found in the non-z = <001> grains. Post-irradiation analysis on W and W-5 wt% (Re; Ta) at 1.0 dpa showed that ½ <111> and <100> loops of both vacancy and interstitial type were present, at number densities ∼ 10 15 loops m −2 . In all cases ½ <111> loops were dominant, the fraction of these with interstitial nature increased with Tirr, and the proportion of <100> loops decreased with increasing Tirr . Compared with pure W, microstructures in the W-(Re; Ta) alloys exhibited higher loop number densities and evolved more quickly with increasing dose towards damage saturation. Graphical abstract: … (more)
- Is Part Of:
- Acta materialia. Volume 112(2016)
- Journal:
- Acta materialia
- Issue:
- Volume 112(2016)
- Issue Display:
- Volume 112, Issue 2016 (2016)
- Year:
- 2016
- Volume:
- 112
- Issue:
- 2016
- Issue Sort Value:
- 2016-0112-2016-0000
- Page Start:
- 105
- Page End:
- 120
- Publication Date:
- 2016-06-15
- Subjects:
- W/W-alloys -- In-situ irradiations -- TEM -- Damage production -- Microstructure evolution
Materials -- Periodicals
Materials science -- Periodicals
Materials -- Mechanical properties -- Periodicals
Metallurgy -- Periodicals
Chemistry, Inorganic -- Periodicals
620.112 - Journal URLs:
- http://www.sciencedirect.com/science/journal/13596454 ↗
http://www.elsevier.com/journals ↗ - DOI:
- 10.1016/j.actamat.2016.03.051 ↗
- Languages:
- English
- ISSNs:
- 1359-6454
- Deposit Type:
- Legaldeposit
- View Content:
- Available online (eLD content is only available in our Reading Rooms) ↗
- Physical Locations:
- British Library DSC - 0629.920000
British Library DSC - BLDSS-3PM
British Library HMNTS - ELD Digital store - Ingest File:
- 7348.xml