Improved radiation damage tolerance of titanium nitride ceramics by introduction of vacancy defects

被引：30

作者：

Xue, Jia-Xiang ^{[1
]}

Zhang, Guo-Jun ^{[1
]}

Guo, Li-Ping ^{[2
]}

Zhang, Hai-Bin ^{[3
]}

Wang, Xin-Gang ^{[1
]}

Zou, Ji ^{[1
]}

Peng, Shu-Ming ^{[3
]}

Long, Xing-Gui ^{[3
]}

机构：

[1] Shanghai Inst Ceram, State Key Lab High Performance Ceram & Superfine, Shanghai 200050, Peoples R China

[2] Wuhan Univ, Sch Phys & Technol, Accelerator Lab, Wuhan 430072, Peoples R China

[3] China Acad Engn Phys, Inst Nucl Phys & Chem, Mianyang 621900, Peoples R China

来源：

JOURNAL OF THE EUROPEAN CERAMIC SOCIETY | 2014年 / 34卷 / 03期

基金：

中国国家自然科学基金;

关键词：

Radiation tolerance; Titanium nitride; Vacancy defect; Self-heal; INERT-MATRIX; MECHANICAL-PROPERTIES; TIN; FUELS; TRANSMUTATION; DIFFRACTION; FABRICATION; ZRN;

D O I：

10.1016/j.jeurceramsoc.2013.10.012

中图分类号：

TQ174 [陶瓷工业]; TB3 [工程材料学];

学科分类号：

0805 ; 080502 ;

摘要：

TiN and TiN0.7 were irradiated using a 100 keV Ar-ion beam at 600 degrees C to target doses of 3 x 10(17) ions cm(-2). SRIM estimation, GIXRD and fluorescence analysis have been performed to evaluate the effect of pre-existing vacancy defect on the radiation tolerance. The lattice parameter of TiN increased after irradiation due to interstitial atoms and vacancies in as-irradiated TiN. In contrary, the lattice parameter decreased for as-irradiated TiN0.7, which indicates that the nitrogen atom vacancies in TiN0.7 acted as sinks for displacement atoms generated by irradiation to limit interstitial atoms existing. The intensity of peaks in fluorescence spectrum of as-irradiated TiN was higher than that of as-irradiated TiN0.7. That atiributed to the presence of color centers formed by Frenkel defects in as-irradiated TiN. All of the results indicate that introducing vacancy defect in materials would offer capability to realize self-heal of irradiation damage. (C) 2013 Elsevier Ltd. All rights reserved.

引用

页码：633 / 639

页数：7

共 24 条

[1] Controlling Radiation Damage [J].

Ackland, Graeme .

SCIENCE, 2010, 327 (5973) :1587-1588

[2]

[Anonymous], 2002, A Technology Roadmap for Generation IV Nuclear Energy Systems

[3] Preparation and characterization of PuN pellets containing ZrN and TiN [J].

Arai, Y ;

Nakajima, K .

JOURNAL OF NUCLEAR MATERIALS, 2000, 281 (2-3) :244-247

[4] Efficient Annealing of Radiation Damage Near Grain Boundaries via Interstitial Emission [J].

Bai, Xian-Ming ;

Voter, Arthur F. ;

Hoagland, Richard G. ;

Nastasi, Michael ;

Uberuaga, Blas P. .

SCIENCE, 2010, 327 (5973) :1631-1634

[5] Some aspects of the use of ZrN as an inert matrix for actinide fuels [J].

Burghartz, M ;

Ledergerber, G ;

Hein, H ;

van der Laan, RR ;

Konings, RJM .

JOURNAL OF NUCLEAR MATERIALS, 2001, 288 (2-3) :233-236

[6] EVANESCENT ABSORPTION IN KINEMATIC SURFACE BRAGG-DIFFRACTION [J].

DOSCH, H .

PHYSICAL REVIEW B, 1987, 35 (05) :2137-2143

[7] Gas-cooled fast reactor fuel fabrication [J].

Fielding, Randall ;

Meyer, Mitch ;

Jue, Jan-Fong ;

Gan, Jian .

JOURNAL OF NUCLEAR MATERIALS, 2007, 371 (1-3) :243-249

[8] Radiation tolerance of Cu/W multilayered nanocomposites [J].

Gao, Yuan ;

Yang, Tengfei ;

Xue, Jianming ;

Yan, Sha ;

Zhou, Shengqiang ;

Wang, Yugang ;

Kwok, Dixon T. K. ;

Chu, Paul K. ;

Zhang, Yanwen .

JOURNAL OF NUCLEAR MATERIALS, 2011, 413 (01) :11-15

[9]

Hugh O., 1996, Handbook of Refractory Carbides and Nitrides

[10] Spark plasma sintering of nano-sized TiN prepared from TiO2 by controlled hydrolysis of TiCl4 and Ti(O-i-C3H7)4 solution [J].

Kawano, S ;

Takahashi, J ;

Shimada, S .

JOURNAL OF THE AMERICAN CERAMIC SOCIETY, 2003, 86 (09) :1609-1611

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