High temperature annealing of ion irradiated tungsten

被引:186
作者
Ferroni, Francesco [1 ]
Yi, Xiaoou [1 ,4 ]
Arakawa, Kazuto [2 ,3 ]
Fitzgerald, Steven P. [1 ]
Edmondson, Philip D. [5 ]
Roberts, Steve G. [1 ,4 ]
机构
[1] Univ Oxford, Dept Mat, Oxford OX1 3PH, England
[2] Shimane Univ, Fac Sci & Engn, Dept Mat Sci, Matsue, Shimane 6908504, Japan
[3] JST, CREST, Chiyoda Ku, Tokyo 1020076, Japan
[4] EURATOM CCFE Fus Assoc, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England
[5] Oak Ridge Natl Lab, Div Mat Sci & Technol, Oak Ridge, TN 37831 USA
基金
英国工程与自然科学研究理事会;
关键词
Tungsten; Ion irradiation; Annealing; TEM; Fusion; DISLOCATION LOOPS; ELECTRICAL-RESISTIVITY; NEUTRON-IRRADIATION; RADIATION-DAMAGE; RECOVERY; VACANCIES; DEFECTS; CLIMB; COALESCENCE; EVOLUTION;
D O I
10.1016/j.actamat.2015.01.067
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Transmission electron microscopy of high temperature annealing of pure tungsten irradiated by self-ions was conducted to elucidate microstructural and defect evolution in temperature ranges relevant to fusion reactor applications (500-1200 degrees C). Bulk isochronal and isothermal annealing of ion irradiated pure tungsten (2 MeV W+ ions, 500 degrees C, 10(14) W+/cm(2)) with temperatures of 800, 950,1100 and 1400 degrees C, from 0.5 to 8 h, was followed by ex situ characterisation of defect size, number density, Burgers vector and nature. Loops with diameters larger than 2-3 nm were considered for detailed analysis, among which all loops had b = 1/2 < 111 > and were predominantly of interstitial nature. In situ annealing experiments from 300 up to 1200 degrees C were also carried out, including dynamic temperature ramp-ups. These confirmed an acceleration of loop loss above 900 degrees C. At different temperatures within this range, dislocations exhibited behaviour such as initial isolated loop hopping followed by large-scale rearrangements into loop chains, coalescence and finally line loop interactions and widespread absorption by free-surfaces at increasing temperatures. An activation energy for the annealing of dislocation length was derived, finding E-a = 1.34 +/- 0.2 eV for the 700-1100 degrees C range. (C) 2015 Acta Materialia Inc. Published by Elsevier Ltd. All rights reserved.
引用
收藏
页码:380 / 393
页数:14
相关论文
共 60 条
[31]  
Keys L. K., 1967, SCRIPTA METALL, V1, P71, DOI [10.1016/0036-9748(67)90017-8, DOI 10.1016/0036-9748(67)90017-8]
[32]   COMPARISON OF RECOVERY OF DAMAGE IN W AND MO AFTER NEUTRON IRRADIATION [J].
KEYS, LK ;
MOTEFF, J .
JOURNAL OF APPLIED PHYSICS, 1969, 40 (09) :3866-&
[33]   HIGH-TEMPERATURE RECOVERY OF TUNGSTEN AFTER NEUTRON IRRADIATION [J].
KEYS, LK ;
SMITH, JP ;
MOTEFF, J .
PHYSICAL REVIEW, 1968, 176 (03) :851-&
[34]   NEUTRON IRRADIATION AND DEFECT RECOVERY OF TUNGSTEN [J].
KEYS, LK ;
MOTEFF, J .
JOURNAL OF NUCLEAR MATERIALS, 1970, 34 (03) :260-&
[35]   RADIATION-DAMAGE AND STAGE-III DEFECT ANNEALING IN THERMAL-NEUTRON IRRADIATED TUNGSTEN [J].
KIM, YW ;
GALLIGAN, JM .
ACTA METALLURGICA, 1978, 26 (03) :379-390
[36]   NEUTRON RADIATION DAMAGE IN TUNGSTEN SINGLE CRYSTALS [J].
LACEFIEL.K ;
MOTEFF, J ;
SMITH, JP .
PHILOSOPHICAL MAGAZINE, 1966, 13 (125) :1079-&
[37]   Study of defect evolution by TEM with in situ ion irradiation and coordinated modeling [J].
Li, Meimei ;
Kirk, M. A. ;
Baldo, P. M. ;
Xu, Donghua ;
Wirth, B. D. .
PHILOSOPHICAL MAGAZINE, 2012, 92 (16) :2048-2078
[38]   Influence of carbon-vacancy interaction on carbon and vacancy diffusivity in tungsten [J].
Liu, Yue-Lin ;
Dai, Zhen-Hong ;
Wang, Wei-Tian .
COMPUTATIONAL MATERIALS SCIENCE, 2014, 83 :1-4
[39]  
Mason D., 2014, COMMUNICATION
[40]   Elastic trapping of dislocation loops in cascades in ion-irradiated tungsten foils [J].
Mason, D. R. ;
Yi, X. ;
Kirk, M. A. ;
Dudarev, S. L. .
JOURNAL OF PHYSICS-CONDENSED MATTER, 2014, 26 (37)