Low cycle fatigue (LCF) tests on 316L(N) austenitic stainless steel base and weld joints were at 823 K and 873 K at a constant strain rate of 3 × 10 -3 s -1 with strain ranges varying from {±}0.4% to {±}1.0% in a servo-hydraulic fatigue test system under flowing sodium environment. The cyclic stress response exhibited a similar trend as that in air comprising of an initial rapid hardening, followed by a slight softening stage before saturation. The fatigue lives are significantly improved in sodium environment when compared to identical testing conditions in air environment. The lack of oxidation in sodium environment is attributed to the delayed crack initiation, reduced crack propagation rate and consequent increase in fatigue life. Compa...
The effect of 20% prior cold work on low cycle fatigue (LCF) behaviour of type 316L(N) stainless ste...
Direct strain controlled LCF data for solid specimens is still very rare. In PVP2013-97500 and PVP20...
The fatigue life design curves in nuclear codes are generally derived from uniaxial straincontrolled...
Mechanical property data on isothermally annealed, thermally aged, and sodium-exposed Fe-2 1/4Cr-1Mo...
AbstractLow cycle fatigue and long-term creep properties, as well as compatibility with liquid sodiu...
Strain-controlled low cycle fatigue tests have been conducted in air between 298-873 K to ascertain ...
Austenitic stainless steels is used in many components of nuclear power plants, particularly in the ...
AbstractNitrogen-alloyed low-carbon grade type 316L(N) SS is the principal material for high tempera...
The low-cycle fatigue behavior of Type 304 stainless steel has been investigated at 593 degrees C in...
An investigation of the below KISCC corrosion fatigue crack propagation behavior of HY-130 steel in ...
Strain controlled low cycle fatigue tests on solution annealed nitrogen modified 316L stainless stee...
Corrosion fatigue and fatigue properties of weld‐bonded and spot‐welded austenitic stainless steels ...
Our research on fatigue performance of stainless steel and transferability of laboratory data to nuc...
A tailored-for-purpose environmental fatigue testing facility was previously developed to perform di...
AbstractThe aim of the present paper is to study the effect of strain rate on the low cycle fatigue ...
The effect of 20% prior cold work on low cycle fatigue (LCF) behaviour of type 316L(N) stainless ste...
Direct strain controlled LCF data for solid specimens is still very rare. In PVP2013-97500 and PVP20...
The fatigue life design curves in nuclear codes are generally derived from uniaxial straincontrolled...
Mechanical property data on isothermally annealed, thermally aged, and sodium-exposed Fe-2 1/4Cr-1Mo...
AbstractLow cycle fatigue and long-term creep properties, as well as compatibility with liquid sodiu...
Strain-controlled low cycle fatigue tests have been conducted in air between 298-873 K to ascertain ...
Austenitic stainless steels is used in many components of nuclear power plants, particularly in the ...
AbstractNitrogen-alloyed low-carbon grade type 316L(N) SS is the principal material for high tempera...
The low-cycle fatigue behavior of Type 304 stainless steel has been investigated at 593 degrees C in...
An investigation of the below KISCC corrosion fatigue crack propagation behavior of HY-130 steel in ...
Strain controlled low cycle fatigue tests on solution annealed nitrogen modified 316L stainless stee...
Corrosion fatigue and fatigue properties of weld‐bonded and spot‐welded austenitic stainless steels ...
Our research on fatigue performance of stainless steel and transferability of laboratory data to nuc...
A tailored-for-purpose environmental fatigue testing facility was previously developed to perform di...
AbstractThe aim of the present paper is to study the effect of strain rate on the low cycle fatigue ...
The effect of 20% prior cold work on low cycle fatigue (LCF) behaviour of type 316L(N) stainless ste...
Direct strain controlled LCF data for solid specimens is still very rare. In PVP2013-97500 and PVP20...
The fatigue life design curves in nuclear codes are generally derived from uniaxial straincontrolled...