Low cycle fatigue behaviour of irradiated stainless steel as shielding material

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

*Corresponding author for this work

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

Abstract

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.

Original languageEnglish
Title of host publicationProceedings of the 2006 International Congress on Advances in Nuclear Power Plants, ICAPP'06
Pages2101-2104
Number of pages4
Publication statusPublished - 2006
EventAmerican Nuclear Society Embedded Topical Meeting - 2006 International Congress on Advances in Nuclear Power Plants, ICAPP'06 - Reno, NV, United States
Duration: 4 Jun 20068 Jun 2006

Publication series

NameProceedings of the 2006 International Congress on Advances in Nuclear Power Plants, ICAPP'06
Volume2006

Conference

ConferenceAmerican Nuclear Society Embedded Topical Meeting - 2006 International Congress on Advances in Nuclear Power Plants, ICAPP'06
Country/TerritoryUnited States
CityReno, NV
Period4/06/068/06/06

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