Mechanical tests and microstructural characterization of hydrided Zr-1 wt% Nb

被引:5
作者
Vazquez, C. A. [1 ]
Fortis, A. M. [1 ]
机构
[1] Comis Nacl Energia Atom, Radiat Damage Grp, Ctr Atom Constituyentes, Dept Mat, Buenos Aires, DF, Argentina
来源
11TH INTERNATIONAL CONGRESS ON METALLURGY & MATERIALS SAM/CONAMET 2011 | 2012年 / 1卷
关键词
Zirconium alloys; Mechanical Properties; Hydrogen; HYDROGEN;
D O I
10.1016/j.mspro.2012.06.070
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
In this paper results of the characterization by SEM and TEM of Zr-1wt% Nb-0, 05wt% Fe with 200 ppm of hydrogen are presented, as well as the results of tensile tests at 300 degrees C and room temperature to determine the pre-irradiation yield stress and ductility. The results are compared with hydrided Zr-2,5wt% Nb with the same heat treatments. (C) 2012 Published by Elsevier Ltd. Selection and/or peer-review under responsibility of SAM/CONAMET 2011, Rosario, Argentina.
引用
收藏
页码:520 / 527
页数:8
相关论文
共 7 条
  • [1] Garde A.M., 1989, Zircon. Nucl. Ind. Eighth Int. Symp. ASTM STP, V1023, P548
  • [2] EFFECT OF HYDROGEN CONTENTS ON THE MECHANICAL-PROPERTIES OF ZIRCALOY-4
    HUANG, JH
    HUANG, SP
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1994, 208 (1-2) : 166 - 179
  • [3] Kaplar E., 2001, MECH PROPERTIES UNIR MECH PROPERTIES UNIR
  • [4] Solubility and partitioning of hydrogen in metastable Zr-based alloys used in the nuclear industry
    Khatamian, D
    [J]. JOURNAL OF ALLOYS AND COMPOUNDS, 1999, 293 : 893 - 899
  • [5] CORRELATION BETWEEN THE TENSILE STRENGTH AND CORROSION BEHAVIOR OF HEAT TREATED ZR-1.0NB ALLOY
    Kim, Tae Kyu
    Choi, Pyung Sik
    Yang, Sung Ki
    Lee, Chong Tak
    Sohn, Dong Seong
    [J]. NUCLEAR ENGINEERING AND TECHNOLOGY, 2008, 40 (06) : 505 - 510
  • [6] Perez-Fero E., 2007, INT LWR FUEL PERF M
  • [7] Vazquez C.A., 2010, 37 REUN AATN BUEN AI