Analysis of tensile deformation and failure in austenitic stainless steels: Part I – Temperature dependence

Kim, Jin Weon; Byun, Thak Sang

doi:10.1016/j.jnucmat.2009.08.010

Cited by 24 publications

(16 citation statements)

References 17 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Ueno et al reported the substantial improvement in monotonic and cyclic strength for austenitic 316L stainless steel by nanostructuring. Nitrogen addition was effective to increase tensile strength with little reduction in elongation for 316L(N) . Nitrogen addition was also effective to increase LCF life, and the increasing rate was more significant at 600 °C than at room temperature.…”

Section: Introductionmentioning

confidence: 92%

See 1 more Smart Citation

Low‐cycle fatigue of 316L stainless steel under proportional and nonproportional loadings

Jin

Tian

et al. 2016

Fatigue Fract Eng Mat Struct

View full text Add to dashboard Cite

This paper discusses low‐cycle fatigue characteristics of 316L stainless steel under proportional and nonproportional loadings. Tension–torsion multiaxial low‐cycle fatigue tests were performed using five strain paths. Additional hardening was observed under nonproportional loadings and was more significant in tests with larger nonproportionality. Mises equivalent strain, Smith–Watson–Topper, Fatemi–Socie, Kandil–Brown–Miller and nonproportional strain parameters were applied to the experimental data to evaluate the multiaxial low‐cycle fatigue damage. The applicability of the damage laws to practical design was discussed.

show abstract

Section: Introductionmentioning

confidence: 92%

“…Nitrogen addition was effective to increase tensile strength with little reduction in elongation for 316L (N). 2,15,16 Nitrogen addition was also effective to increase LCF life, and the increasing rate was more significant at 600°C than at room temperature. Some studies discussed on the corrosion of 316L stainless steel.…”

mentioning

confidence: 99%

Low‐cycle fatigue of 316L stainless steel under proportional and nonproportional loadings

Jin

Tian

et al. 2016

Fatigue Fract Eng Mat Struct

View full text Add to dashboard Cite

show abstract

“…In the past, a very comprehensive review was published [5], dealing with radiation-induced material changes and susceptibility to IG failure of LWR core internals, focused on the explanation of Intergranular Stress Corrosion Cracking (IGSCC) in water environments, but did not mention IG fracture in inner environments. In recent papers [7,8], deformation and fracture of ASSs irradiated to low doses were studied in detail. Moreover, a ductile-to-brittle transition possibility and low temperature embrittlement with increasing neutron exposure and the intergranular fracture kinetics need to be evaluated.…”

Section: Low Temperature Irradiationmentioning

confidence: 99%

Overview of Intergranular Fracture of Neutron Irradiated Austenitic Stainless Steels

Hojná

2017

Metals

View full text Add to dashboard Cite

Austenitic stainless steels are normally ductile and exhibit deep dimples on fracture surfaces. These steels can, however, exhibit brittle intergranular fracture under some circumstances. The occurrence of intergranular fracture in the irradiated steels is briefly reviewed based on limited literature data. The data are sorted according to the irradiation temperature. Intergranular fracture may occur in association with a high irradiation temperature and void swelling. At low irradiation temperature, the steels can exhibit intergranular fracture at low or even at room temperatures during loading in air and in high temperature water (~300 • C). This paper deals with the similarities and differences for IG fractures and discusses the mechanisms involved. The intergranular fracture occurrence at low temperatures might be correlated with decohesion or twinning and strain martensite transformation in local narrow areas around grain boundaries. The possibility of a ductile-to-brittle transition is also discussed. In case of void swelling higher than 3%, quasi-cleavage at low temperature might be expected as a consequence of ductile-to-brittle fracture changes with temperature. Any existence of the change in fracture behavior in the steels of present thermal reactor internals with increasing irradiation dose should be clearly proven or disproven. Further studies to clarify the mechanism are recommended.

show abstract

“…38,39 These steels showed temperature dependencies relative to strength and ductility. Specifically, the strength decreased as temperature increased.…”

Section: 38mentioning

confidence: 99%

“…The gauge section dimensions of sub-sized tensile specimens are 7.62 mm long, 1.5 mm wide and 0.75 mm thick. The temperature dependence of deformation and failure behaviors in these stainless steels in terms of equivalent true stress-true strain curves is analyzed, 39 and the irradiation dose dependencies of strain hardening behavior during unstable deformation and fracture properties are studies based on the calculated true stress strain curves. …”

Section: 38mentioning

confidence: 99%

In-situ Creep Testing Capability Development for Advanced Test Reactor

Kim¹,

Rempe²,

Knudson³

et al. 2010

View full text Add to dashboard Cite

Analysis of tensile deformation and failure in austenitic stainless steels: Part I – Temperature dependence

Cited by 24 publications

References 17 publications

Low‐cycle fatigue of 316L stainless steel under proportional and nonproportional loadings

Low‐cycle fatigue of 316L stainless steel under proportional and nonproportional loadings

Overview of Intergranular Fracture of Neutron Irradiated Austenitic Stainless Steels

In-situ Creep Testing Capability Development for Advanced Test Reactor

Contact Info

Product

Resources

About