Some studies on mechanisms of corrosion of zirconium alloys in-reactor
عنوان مقاله: Some studies on mechanisms of corrosion of zirconium alloys in-reactor
شناسه ملی مقاله: SENACONF01_307
منتشر شده در اولین کنگره سراسری فناوریهای نوین ایران با هدف دستیابی به توسعه پایدار در سال 1393
شناسه ملی مقاله: SENACONF01_307
منتشر شده در اولین کنگره سراسری فناوریهای نوین ایران با هدف دستیابی به توسعه پایدار در سال 1393
مشخصات نویسندگان مقاله:
Abbas Sedghkerdar - Department of Nuclear Engineering, Faculty of Mechanical Engineering, Shiraz University, Shiraz, Iran
خلاصه مقاله:
Abbas Sedghkerdar - Department of Nuclear Engineering, Faculty of Mechanical Engineering, Shiraz University, Shiraz, Iran
In recent years sufficient new information has accumulated to change current views of which mechanisms of corrosion are operating in water-cooled reactors. There seems to be insufficient evidence to support an hypothesis that increased corrosion rates in reactor result directly from displacement damage to the oxide by fast neutron bombardment. Replacing this hypothesis are the observations that redistribution of Fe from second phase particles (SPPs) into the Zr matrix by fast neutron recoil reduces the corrosion resistance of Zircaloy type alloys in-reactor.
کلمات کلیدی: Corrosion, zirconium alloys, Reactor
صفحه اختصاصی مقاله و دریافت فایل کامل: https://civilica.com/doc/345227/