In situ study of the oxidation of Zircaloy-4 by ESEM

被引:16
作者
Abolhassani, S [1 ]
Dadras, M
Leboeuf, M
Gavillet, D
机构
[1] Paul Scherrer Inst, Lab Mat Behav, CH-5232 Villigen, Switzerland
[2] Univ Neuchatel, IMT, Serv Microscopy & Nanoscopy, CH-2007 Neuchatel, Switzerland
关键词
D O I
10.1016/S0022-3115(03)00201-0
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Zircaloy-4 has been oxidised in environmental scanning electron microscope (ESEM), at a temperature of 700 degreesC and the surface of the material has been observed during the oxidation, directly in the ESEM. The material has been subsequently analysed by atomic force microscopy (AFM) and transmission electron microscopy (TEM). Several aspects of the oxidation were revealed in these experiments. Zircaloy-4 oxidises at a different rate depending on the crystallographic orientation of the grains at the surface. The iron and chromium in the secondary phase particles (SPP) diffuse to the surface and oxidise to produce a profile at the surface of the material. The in situ observations reveal no cracks at the surface during the oxidation. Subsequent examination of the surface (ex situ) by AFM reveals the presence of pores in the oxide. TEM examinations indicate the presence of weak internal planes in the oxide layer, inducing cracks parallel to the metal-oxide interface. (C) 2003 Elsevier B.V. All rights reserved.
引用
收藏
页码:70 / 77
页数:8
相关论文
共 14 条
[1]  
ABOLHASSANI S, 2001, P MICR MICR 2001 LON, P250
[2]  
Anada H., 2000, P ANS INT TOP M LWR, P445
[3]   Depletion of Fe and Cr within precipitates during Zircaloy-4 oxidation [J].
Baek, JH ;
Jeong, YH .
JOURNAL OF NUCLEAR MATERIALS, 2002, 304 (2-3) :107-116
[4]   A hydrogen uptake micro-mechanism for Zr alloys [J].
Cox, B ;
Wong, YM .
JOURNAL OF NUCLEAR MATERIALS, 1999, 270 (1-2) :134-146
[5]   STUDY OF GROWTH OF OXIDE ON ZIRCONIUM AND ZIRCALOY-2 [J].
DAVID, G ;
GESCHIER, R ;
ROY, C .
JOURNAL OF NUCLEAR MATERIALS, 1971, 38 (03) :329-&
[6]  
FRANKLIN D, 1987, ASTM STP, V939, P206
[7]   Metal and oxygen mobilities during Zircaloy-4 oxidation at high temperature [J].
Grandjean, A ;
Serruys, Y .
JOURNAL OF NUCLEAR MATERIALS, 1999, 273 (01) :111-115
[8]  
INAGAKI M, 1991, AM SOC TEST MATER, V1132, P437, DOI 10.1520/STP25521S
[9]  
Isobe T., 1996, ASTM STP, V1295, P203
[10]   Residual stress of monoclinic zircon obtained by X-ray diffraction in ZY4 oxidized cladding tubes [J].
Jacquot, T ;
Guillen, R ;
Francois, M ;
Bourniquel, B ;
Senevat, J .
EUROPEAN POWDER DIFFRACTION: EPDIC IV, PTS 1 AND 2, 1996, 228 :845-850