کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن |
---|---|---|---|---|
1585736 | 1514917 | 2006 | 7 صفحه PDF | دانلود رایگان |
عنوان انگلیسی مقاله ISI
Tensile and corrosion behavior of Zr705 for nuclear hydrogen generation
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کلمات کلیدی
موضوعات مرتبط
مهندسی و علوم پایه
مهندسی مواد
دانش مواد (عمومی)
پیش نمایش صفحه اول مقاله
![عکس صفحه اول مقاله: Tensile and corrosion behavior of Zr705 for nuclear hydrogen generation Tensile and corrosion behavior of Zr705 for nuclear hydrogen generation](/preview/png/1585736.png)
چکیده انگلیسی
Zr705 has been evaluated for its metallurgical and corrosion properties for application in nuclear hydrogen generation using a thermochemical process that involves the decomposition of hydroiodic acid at temperatures up to 400 °C. The results indicate that the tensile strength was gradually reduced with increasing temperature. However, the failure strain was enhanced up to a critical temperature (200 °C) followed by its reduction beyond it, possibly due to the dynamic strain aging effect. As to the cracking susceptibility in an acidic solution, no failure was observed under constant-load and self-loaded conditions. However, enhanced ductility was observed in slow-strain-rate (SSR) testing in an identical environment at elevated temperatures. The application of external potential during SSR testing enhanced the cracking susceptibility. The critical potentials obtained in the electrochemical polarization study became more active with increasing temperature. Ductile failures, characterized by dimples, were noted in all failed specimens.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Materials Science and Engineering: A - Volume 427, Issues 1â2, 15 July 2006, Pages 320-326
Journal: Materials Science and Engineering: A - Volume 427, Issues 1â2, 15 July 2006, Pages 320-326
نویسندگان
Ajit K. Roy, Ancila V. Kaiparambil,