氢化物取向对Zr-4包壳管室温拉伸和爆破性能的影响
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摘要
通过室温爆破和室温拉伸实验,研究了氢化物取向对氢含量140±20μg/g和260±20μg/g的Zr-4管材力学性能的影响。结果表明:在研究的2种氢含量下,氢化物取向对室温拉伸性能和室温爆破强度无明显影响,周向延性对氢化物取向十分敏感。随着氢化物取向因子增加,室温爆破延伸率显著降低。与氢含量140±20μg/g的管材相比,氢含量260±20μg/g的管材室温爆破延伸率下降得更快。
The effect of hydride orientation on mechanical properties of Zr-4 tubes with hydrogen contents with 140±20 μg/g and 260±20 μg/g was investigated by tensile and bursting tests at room temperature. The results showed that with the two studied hydrogen contents, the hydride orientation had little influence on tensile properties and bursting strengths at room temperature. The circumferential ductility was extremely sensitive to the hydride orientation. The bursting elongation at room temperature was degraded remarkably with the increasing of the hydride orientation factor. The bursting elongation at room temperature for tubes with 260±20μg/g hydrogen decreased faster compared with that for 140±20 μg/g.
The effect of hydride orientation on mechanical properties of Zr-4 tubes with hydrogen contents with 140±20 μg/g and 260±20 μg/g was investigated by tensile and bursting tests at room temperature. The results showed that with the two studied hydrogen contents, the hydride orientation had little influence on tensile properties and bursting strengths at room temperature. The circumferential ductility was extremely sensitive to the hydride orientation. The bursting elongation at room temperature was degraded remarkably with the increasing of the hydride orientation factor. The bursting elongation at room temperature for tubes with 260±20μg/g hydrogen decreased faster compared with that for 140±20 μg/g.
引文
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[6]Kim J,Lee M,Choi B.Effect of the hydrogen contents on the circumferential mechanical properties of zirconium alloy claddings[J].Journal of Alloys and Compounds,2007,431:155-161.
[7]周军,李中奎,张建军.不同氢含量的新锆合金(NZ2)的力学性能[J].稀有金属材料与工程,2008,3:2244-2248.
[8]孙超.核动力用锆合金氢致延迟开裂行为研究[D].成都:中国核动力研究设计院学位论文,2010.
[2]Pickman D O.Design of fuel elements[J].Nuclear Engineering and Design,1972,21:303-317.
[3]Marshall R P.Influence of fabrication history on stressoriented hydrides in zircaloy tubing[J].Journal of Nuclear Materials,1967,24:34-38.
[4]Ells C E.The stress orientation of hydride in zirconium alloys[J].Journal of Nuclear Materials,1970,35:306-315.
[5]田振业.氢化物对Zr-4管合金管材性能的影响[J].稀有金属合金加工,1979,3:16-25.
[6]Kim J,Lee M,Choi B.Effect of the hydrogen contents on the circumferential mechanical properties of zirconium alloy claddings[J].Journal of Alloys and Compounds,2007,431:155-161.
[7]周军,李中奎,张建军.不同氢含量的新锆合金(NZ2)的力学性能[J].稀有金属材料与工程,2008,3:2244-2248.
[8]孙超.核动力用锆合金氢致延迟开裂行为研究[D].成都:中国核动力研究设计院学位论文,2010.