Analysis of tensile deformation and failure in austenitic stainless steels: Part II – Irradiation dose dependence

Kim, Jin Weon; Byun, Thak Sang

doi:10.1016/j.jnucmat.2009.08.009

Cited by 22 publications

(12 citation statements)

References 21 publications

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“…50 Figure 4-4 shows some engineering stress-strain curves for irradiated 316 SS and EC316LN SS to analyze irradiation dose dependence. 40 As shown in this figure, most engineering stress-strain curves are impacted by irradiation, exhibiting increases in strength and decreases in elongation. The one exception being 316 SS tested at 288°C, for which radiation effects were minimal.…”

Section: Ss316mentioning

confidence: 85%

In-situ Creep Testing Capability Development for Advanced Test Reactor

Kim¹,

Rempe²,

Knudson³

et al. 2010

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Section: Ss316mentioning

confidence: 85%

In-situ Creep Testing Capability Development for Advanced Test Reactor

Kim¹,

Rempe²,

Knudson³

et al. 2010

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“…Fig. 14a shows stress-strain curves for SA 316 stainless steel irradiated to several doses <1 dpa in the mixed spectrum HFIR test reactor at 60 8C and tested at room temperature [81]. In addition to the strength increases and loss of ductility and work-hardening, a yield point drop was observed at doses of 0.01 dpa and higher.…”

Section: Radiation Hardening and Embrittlementmentioning

confidence: 98%

“…Stress-strain curves for (a) a solution-annealed 316 stainless steel irradiated to several doses <1 dpa in the mixed spectrum HFIR test reactor at 60 8C and tested at room temperature[81] and (b) a solution-annealed J316 both irradiated in HFIR and tested at 330 8C[82].…”

mentioning

confidence: 99%

Radiation-induced degradation of stainless steel light water reactor internals

Kenik¹,

Busby²

2012

Materials Science and Engineering: R: Reports

102

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“…Fitting this unsaturated damage model to the experimental SS316 tensile data in [22] provides a K value of approximately 990 MPa/ √ dpa, which the authors have rounded up to 1000 MPa/ √ dpa for simplification. The fitting of the data was carried out in MATLAB [17] using the non-linear least squares fit which solves for…”

Section: Finite Element Modellingmentioning

confidence: 99%

Comparative Study of Two Nanoindentation Approaches for Assessing Mechanical Properties of Ion-Irradiated Stainless Steel 316

Saleh

Zaidi

Hurt

et al. 2018

Metals

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Nanoindentation is a commonly used method to measure the hardness of surfaces with thin layers, and is especially useful in studying the change in mechanical properties of ion irradiated materials. This research compares two different methods of nanoindentation to study the changes in hardness resulting from ion irradiation of SS316 alloy. The samples were irradiated by He2+ ions at beam energies of 1, 2, and 3 MeV, respectively. The first method involves the indentation of the irradiated surface perpendicular to it using the continuous stiffness mode (CSM), while the second applies the indents on an oblique surface, accessing an inclined cross-section of the irradiated material. Finite element modelling has been used to further illuminate the deformation processes below the indents in the two methods. The hardness profiles obtained from the two nanoindentation methods reveal the differences in the outcomes and advantages of the respective procedures, and provide a useful guideline for their applicability to various experimental conditions. It is shown through an in depth analysis of the results that the ‘top-down’ method is preferable in the case when the ion irradiation energy, or, equivalently, the irradiated depth is small, due to its greater spatial resolution. However, the oblique cross section method is more suitable when the ion irradiation energy is >1 MeV, since it allows a more faithful measurement of hardness as a function of dose, as the plastic field is much smaller and more sensitive to local hardness values.

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Analysis of tensile deformation and failure in austenitic stainless steels: Part II – Irradiation dose dependence

Cited by 22 publications

References 21 publications

In-situ Creep Testing Capability Development for Advanced Test Reactor

In-situ Creep Testing Capability Development for Advanced Test Reactor

Radiation-induced degradation of stainless steel light water reactor internals

Comparative Study of Two Nanoindentation Approaches for Assessing Mechanical Properties of Ion-Irradiated Stainless Steel 316

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