Effect of alloying elements on the properties of Zr and the Zr-H system

被引:63
作者
Christensen, M. [1 ]
Wolf, W. [1 ]
Freeman, C. M. [1 ]
Wimmer, E. [1 ]
Adamson, R. B. [2 ]
Hallstadius, L. [3 ]
Cantonwine, P. E. [4 ]
Mader, E. V. [5 ]
机构
[1] Mat Design Inc, Santa Fe, NM 87501 USA
[2] Zircol Plus, Fremont, CA 94536 USA
[3] Westinghouse Elect Sweden, SE-72163 Vasteras, Sweden
[4] Global Nucl Fuel Amer, Wilmington, NC 28402 USA
[5] Elect Power Res Inst, Palo Alto, CA 94303 USA
关键词
ALPHA-ZR; DIFFUSION; IRRADIATION; PHASE; FE; SOLUBILITY; ZIRCALOY-2; DYNAMICS; SN; NB;
D O I
10.1016/j.jnucmat.2013.10.040
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The effect of the alloying elements Sn, Fe, Cr, Ni, Nb, and O on hydrogen-containing alpha-zirconium and zirconium hydrides is investigated using ab initio quantum mechanical calculations and classical simulations. Cr, Fe, and Ni atoms attract interstitially dissolved H atoms whereas interstitial oxygen atoms show no pronounced interaction with H atoms. The alloying elements destabilize the hydride phases in the order Sn > Fe > Cr > Ni > Nb. Hence, substitutional Sn (if atomically dispersed), Cr and Fe atoms are likely to delay hydride precipitation, effectively increasing the hydrogen solubility. Nb and Sn influence the mobility of Zr self-interstitial atoms (SIA's), which diffuse rapidly and preferentially parallel to the basal planes forming interstitial dislocations loops perpendicular to the basal planes (a-loops). Nb suppresses this diffusion of SIA's, thereby reducing the rate of formation of interstitial a-loops. Sn atoms, if present on substitutional sites, have a similar, but smaller effect. If SIA's approach substitutional Fe, Cr, and Ni atoms, the simulations indicate a spontaneous swap promoting the smaller transition metal atoms into interstitial atoms, which diffuse very rapidly with a preference in the c-direction, thereby facilitating their segregation to energetically more favorable sites such as vacancies, vacancy c-loops, grain boundaries, surfaces, and intermetallic precipitates. (C) 2013 Elsevier B.V. All rights reserved.
引用
收藏
页码:241 / 250
页数:10
相关论文
共 56 条
[1]  
Abriata J., 1983, Bulletin of Alloy Phase Diagrams, V4, P147
[2]  
Adamson R.B., 2010, RPS2 ASTM
[3]   Effects of neutron irradiation on microstructure and properties of Zircaloy [J].
Adamson, RB .
ZIRCONIUM IN THE NUCLEAR INDUSTRY: TWELFTH INTERNATIONAL SYMPOSIUM, 2000, 1354 :15-31
[4]  
[Anonymous], MEDEA 2 5
[5]   ON CALCULATION OF MELTING TEMPERATURES FOR LOW-TEMPERATURE PHASES OF POLYMORPHIC METALS [J].
ARDELL, AJ .
ACTA METALLURGICA, 1963, 11 (06) :591-&
[6]   PROJECTOR AUGMENTED-WAVE METHOD [J].
BLOCHL, PE .
PHYSICAL REVIEW B, 1994, 50 (24) :17953-17979
[7]   Effect of impurity and alloying elements on Zr grain boundary strength from first-principles computations [J].
Christensen, M. ;
Angeliu, T. M. ;
Ballard, J. D. ;
Vollmer, J. ;
Najafabadi, R. ;
Wimmer, E. .
JOURNAL OF NUCLEAR MATERIALS, 2010, 404 (02) :121-127
[8]  
Christensen M., PHYS REV B UNPUB
[9]  
Christensen M., 2013, ASTM STP
[10]   Cluster Dynamics modelling of irradiation growth of zirconium single crystals [J].
Christien, F. ;
Barbu, A. .
JOURNAL OF NUCLEAR MATERIALS, 2009, 393 (01) :153-161