کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن |
---|---|---|---|---|
5453857 | 1514151 | 2017 | 9 صفحه PDF | دانلود رایگان |
عنوان انگلیسی مقاله ISI
Aging effect on the thermal transient behavior of the fuel cladding of a sodium-cooled fast reactor
ترجمه فارسی عنوان
اثر پیری بر رفتار حرارتی مایع روانکاری سوخت یک راکتور سریع سدیم سرد
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کلمات کلیدی
موضوعات مرتبط
مهندسی و علوم پایه
مهندسی انرژی
انرژی هسته ای و مهندسی
چکیده انگلیسی
The transient behavior of the fuel cladding of a sodium-cooled fast reactor (SFR) is one of the main design issues concerning the safety of a reactor. The safety margin of the cladding during transient events has been widely studied in the past. However, previously, the transient testing was conducted using as-received specimens (and not aged specimens). For ensuring safety margin of the fuel rod of an SFR, the effect of aging on the transient behavior of the fuel cladding should be considered. This study examines this effect on the transient behavior of HT9 cladding by correlating between the UTS and the result of the ramp test and proposes a modified Dorn parameter that reflects the aging effect. At 100Â MPa of the hoop stress, the modified Dorn parameter, which reflects an aging effect, is 7.7266Â ÃÂ 10â14 and the Dorn parameter of as-received specimen is 1.749Â ÃÂ 10â12. This results in the enhanced safety during transient event by considering aging effect.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Journal of Nuclear Materials - Volume 495, November 2017, Pages 225-233
Journal: Journal of Nuclear Materials - Volume 495, November 2017, Pages 225-233
نویسندگان
Sang Hun Shin, Jun Hwan Kim, Woo Seog Ryu, Hyeong Min Heo, Sung Ho Kim,