کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن |
---|---|---|---|---|
790959 | 1466132 | 2008 | 9 صفحه PDF | دانلود رایگان |
عنوان انگلیسی مقاله ISI
Development of an ASME-NH program for nuclear component design at elevated temperatures
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کلمات کلیدی
موضوعات مرتبط
مهندسی و علوم پایه
سایر رشته های مهندسی
مهندسی مکانیک
پیش نمایش صفحه اول مقاله
چکیده انگلیسی
In this paper, we discuss an ASME-NH program that has been developed to overcome the complexity and costs arising from the real application of the ASME-NH rules by hand calculations for class 1 nuclear facility component design for elevated temperature operations. A computerized program is described for implementing all the assessment procedures such as the time-dependent primary stress limits, total accumulated creep-ratcheting strain limits, and the creep–fatigue damage limits by the elastic and inelastic analysis methods complying with the ASME-NH rules. As an example application, a preliminary structural integrity evaluation for a high-temperature reactor vessel design of a typical lead-cooled reactor is described.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: International Journal of Pressure Vessels and Piping - Volume 85, Issue 6, June 2008, Pages 385–393
Journal: International Journal of Pressure Vessels and Piping - Volume 85, Issue 6, June 2008, Pages 385–393
نویسندگان
Gyeong-Hoi Koo, Jae-Han Lee,