Low cycle fatigue behaviour of irradiated stainless steel as shielding material

Nilgun Baydogan*, Murat Baydogan, A. Beril Tugrul, Huseyin Cimenoglu

*Bu çalışma için yazışmadan sorumlu yazar

Araştırma sonucu: Kitap/Rapor/Konferans Bildirisinde BölümKonferans katkısıbilirkişi

Özet

In this study, low cycle fatigue behaviour of a 304 quality austenitic stainless steel irradiated with a 60Co radioisotope at 100-kGray-dose level was examined for the usage at the nuclear reactor vessel or a nuclear waste container. After irradiation, 1 % increment in thickness of the specimens was measured. During fatigue tests, irradiated specimens failed at earlier cycles than unirradiated specimens. The effect of irradiation on number of cycles to failure was more obvious at high strain range values. The difference in failure cycles of unirradiated and irradiated specimens is about 27 %, at 4 % total strain range. However, at 1 % total strain range, both unirradiated and irradiated specimens failed at almost the same cycle value.

Orijinal dilİngilizce
Ana bilgisayar yayını başlığıProceedings of the 2006 International Congress on Advances in Nuclear Power Plants, ICAPP'06
Sayfalar2101-2104
Sayfa sayısı4
Yayın durumuYayınlandı - 2006
EtkinlikAmerican Nuclear Society Embedded Topical Meeting - 2006 International Congress on Advances in Nuclear Power Plants, ICAPP'06 - Reno, NV, United States
Süre: 4 Haz 20068 Haz 2006

Yayın serisi

AdıProceedings of the 2006 International Congress on Advances in Nuclear Power Plants, ICAPP'06
Hacim2006

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???event.eventtypes.event.conference???American Nuclear Society Embedded Topical Meeting - 2006 International Congress on Advances in Nuclear Power Plants, ICAPP'06
Ülke/BölgeUnited States
ŞehirReno, NV
Periyot4/06/068/06/06

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