High temperature hardness testing of d-zirconium hydride: Yield stress estimation by analytical and numerical models

被引:5
作者
Cherubin, Igor J. S. [1 ]
Long, Fei R. [1 ]
Daymond, Mark [1 ]
机构
[1] Queens Univ, Kingston, ON K7L3N6, Canada
基金
加拿大自然科学与工程研究理事会;
关键词
Nuclear materials; Zirconium alloys; Pressure tube; Zircaloy-4; δ -Zirconium hydride; Mechanical properties; Hardness; High temperature; DUCTILE-BRITTLE TRANSITION; MECHANICAL-PROPERTIES; CLADDING TUBES; NANOINDENTATION; HYDROGEN; ORIENTATION; ZIRCALOY-4; ALLOYS; IRRADIATION; BLISTERS;
D O I
10.1016/j.jnucmat.2021.153424
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The mechanical properties of delta-zirconium hydrides were studied using a combination of nanoindentation techniques and numerical and analytical models. Two different alloys, containing different forms of delta-zirconium hydride (blister and rim), were analyzed at room temperature and at elevated temperatures up to 300 C. A reduction of hardness from RT to 300 C showed an approximately linear relationship with the change in temperature. For the delta-zirconium hydride rim, the hardness reduced from 3.73GPa at RT to 1.49GPa at 300 C, a reduction of 61 % . For the delta-zirconium hydride blister, hardness decreased from 3.5GPa at RT to 1.91GPa at 300 C, a reduction of 45 % . The yield stresses were calculated using two approaches: a numerical model proposed by Johnson to calculate values at RT, and another proposed by Dao for values up to 300 C. At RT, the yield stress for the delta-zirconium hydride rim obtained was 883 +/- 21MPa, 224MPa at 300 C. The delta-zirconium hydride blister showed a reduction from 879.5 +/- 10.5MPa at RT to 324MPa at 300 C, a reduction in 61 % and 45 % for the hydride rim and blister, respectively. Through this combination of experimental and modeling techniques, this study showed the variation of hardness and yield stress in complex systems, and in different environments, using nanoindentation as the main characterization technique.(C) 2021 Elsevier B.V. All rights reserved.
引用
收藏
页数:8
相关论文
共 49 条
[1]   Hydride embrittlement and irradiation effects on the hoop mechanical properties of pressurized water reactor (PWR) and boiling-water reactor (BWR) ZIRCALOY cladding tubes:: Part III.: Mechanical behavior of hydride in stress-relieved annealed and recrystallized ZIRCALOYs at 20 °C and 300 °C [J].
Arsene, S ;
Bai, J ;
Bompard, P .
METALLURGICAL AND MATERIALS TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE, 2003, 34 (03) :579-588
[2]  
Bai JB, 1996, J NUCL SCI TECHNOL, V33, P141, DOI [10.1080/18811248.1996.9731876, 10.3327/jnst.33.141]
[3]   Anisotropy of yielding in a Zr-2.5Nb pressure tube material [J].
Christodoulou, N ;
Turner, PA ;
Ho, ETC ;
Chow, CK ;
Levi, MR .
METALLURGICAL AND MATERIALS TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE, 2000, 31 (02) :409-420
[4]   Nanoindentation study of bulk zirconium hydrides at elevated temperatures [J].
Cinbiz, M. Nedim ;
Balooch, Mehdi ;
Hu, Xunxiang ;
Amroussia, Aida ;
Terrani, Kurt .
JOURNAL OF ALLOYS AND COMPOUNDS, 2017, 726 :41-48
[5]   Solute hydrogen and hydride phase implications on the plasticity of zirconium and titanium alloys: a review and some recent advances [J].
Conforto, E. ;
Guillot, I. ;
Feaugas, X. .
PHILOSOPHICAL TRANSACTIONS OF THE ROYAL SOCIETY A-MATHEMATICAL PHYSICAL AND ENGINEERING SCIENCES, 2017, 375 (2098)
[6]   Hydrogen uptake during oxidation of zirconium alloys [J].
Cox, B .
JOURNAL OF ALLOYS AND COMPOUNDS, 1997, 256 (1-2) :244-246
[8]  
Cui J., 2009, ASME 2009 PRESS VESS, P6
[9]   Computational modeling of the forward and reverse problems in instrumented sharp indentation [J].
Dao, M ;
Chollacoop, N ;
Van Vliet, KJ ;
Venkatesh, TA ;
Suresh, S .
ACTA MATERIALIA, 2001, 49 (19) :3899-3918
[10]   Formation and characterization of hydride blisters in Zircaloy-4 cladding tubes [J].
de Menibus, Arthur Hellouin ;
Auzoux, Quentin ;
Dieye, Ousmane ;
Berger, Pascal ;
Bosonnet, Sophie ;
Foy, Eddy ;
Macdonald, Vincent ;
Besson, Jacques ;
Crepin, Jerome .
JOURNAL OF NUCLEAR MATERIALS, 2014, 449 (1-3) :132-147