693.932 PEOPLE
| People | Locations | Statistics |
|---|---|---|
| Naji, M. |
| |
| Motta, Antonella |
| |
| Aletan, Dirar |
| |
| Mohamed, Tarek |
| |
| Ertürk, Emre |
| |
| Taccardi, Nicola |
| |
| Kononenko, Denys |
| |
| Petrov, R. H. | Madrid |
|
| Alshaaer, Mazen | Brussels |
|
| Bih, L. |
| |
| Casati, R. |
| |
| Muller, Hermance |
| |
| Kočí, Jan | Prague |
|
| Šuljagić, Marija |
| |
| Kalteremidou, Kalliopi-Artemi | Brussels |
|
| Azam, Siraj |
| |
| Ospanova, Alyiya |
| |
| Blanpain, Bart |
| |
| Ali, M. A. |
| |
| Popa, V. |
| |
| Rančić, M. |
| |
| Ollier, Nadège |
| |
| Azevedo, Nuno Monteiro |
| |
| Landes, Michael |
| |
| Rignanese, Gian-Marco |
|
Toivonen, Aki
VTT Technical Research Centre of Finland
in Cooperation with on an Cooperation-Score of 37%
Topics
Publications (60/60 displayed)
- 2024Effects of surface finishes, heat treatments and printing orientations on stress corrosion cracking behavior of laser powder bed fusion 316L stainless steel in high-temperature watercitations
- 2023SCC behaviour of laser powder bed fused 316L stainless steel in high-temperature water at 288 °Ccitations
- 2022Investigation of surface treatment effects on the environmentally-assisted cracking behaviour of Alloy 182 in boiling water reactor environmentcitations
- 2022Stress corrosion cracking initiation susceptibility of Alloy 182 with different surface treatmentscitations
- 2022The reproducibility of corrosion testing in supercritical water—Results of a second international interlaboratory comparison exercisecitations
- 2021Stress corrosion crack initiation testing with tapered specimens in high-temperature water:Results of a collaborative research projectcitations
- 2021Stress corrosion crack initiation testing with tapered specimens in high-temperature water–results of a collaborative research projectcitations
- 2021Stress corrosion crack initiation testing with tapered specimens in high-temperature watercitations
- 2021Effects of Surface Treatments on Environmentally-Assisted Cracking Susceptibility of Alloy 182 in BWR Environmentcitations
- 2020International Round-Robin on Stress Corrosion Crack Initiation of Alloy 600 Material in Pressurized Water Reactor Primary Watercitations
- 2020Analysis of mechanisms inducing corrosion cracking of irradiated austenitic steels and development of a model for prediction of crack initiationcitations
- 2020Stress corrosion crack initiation testing with tapered specimens in high-temperature water - results of a collaborative research projectcitations
- 2019Water chemistry and corrosion issues in PWR/WWER SGs and current knowledge on water chemistries in SMRs
- 2019Effect of lead and applied potential on corrosion of carbon steel in steam generator crevice solutionscitations
- 2016Oxidation parameters of oxide dispersion-strengthened steels in supercritical watercitations
- 2016European project "supercritical water reactor-fuel qualification test"citations
- 2016Overview of SCWR candidate materials stress corrosion tests
- 2016European Project "Supercritical Water Reactor-Fuel Qualification Test": Overview, Results, Lessons Learned, and Future Outlookcitations
- 2016European project "supercritical water reactor-fuel qualification test":Summary of general corrosion testscitations
- 2015European Project "Supercritical Water Reactor:Fuel Qualification Test" (SCWR-FQT): Results of SCC susceptibility tests
- 2015European Project "Supercritical Water Reactor - Fuel Qualification Test" (SCWR-FQT)
- 2015European Project "Supercritical Water Reactor
- 2015SCC tests in SCW at 550°C on two heats of 316L
- 2015European Project "Supercritical Water Reactor - Fuel Qualification Test" (SCWR-FQT):Overview, Results, Lessons Learnt and Future Outlook
- 2014Structural integrity of Ni-base alloy welds
- 2014Effect of shot peening on oxidation resistance of austenitic alloys in SCW conditions
- 2014Overview and progress in the European project:"Supercritical Water Reactor - Fuel Qualification Test"citations
- 2014Overview and progress in the European projectcitations
- 2013Effect of surface modification on the corrosion resistance of austenitic stainless steel 316L in supercritical water conditionscitations
- 2013General corrosion and SCC tests on ODS steels in supercritical water
- 2013Investigation of coatings, applied by PVD, for the corrosion protection of materials in supercritical water
- 2011Estimation of kinetic parameters of the corrosion layer constituents on steels in supercritical water coolant conditionscitations
- 2011European supercritical water cooled reactorcitations
- 2011European supercritical water cooled reactorcitations
- 2011Environment-assisted cracking and hot cracking susceptibility of nickel-base alloy weld metals
- 2011Corrosion and creep studies of candidate in-core materials for Generation IV supercritical water reactor
- 2011Effect of coating and surface modification on the corrosion resistance of selected alloys in supercritical water
- 2011Deformation microstructures of 30 dpa AISI 304 stainless steel after monotonic tensile and constant load autoclave testing
- 2011Effect of Hot Cracks on EAC Crack initiation and Growth in Nickel-Base Alloy Weld Metalscitations
- 2010Stress corrosion cracking susceptibility of austenitic stainless steels in supercritical water conditionscitations
- 2010Candidate materials performance under Supercritical Water Reactor (SCWR) conditions
- 2010Determination of the time to failure curve as a function of stress for a highly irradiated AISI 304 stainless steel after constant load tests in simulated PWR water environment
- 2010Corrosion products behavior and source term reduction
- 2010Corrosion Studies of Candidate Materials for European HPLWRcitations
- 2010Environment-assisted cracking and hot cracking of Ni-base alloy dissimilar metal welds
- 2010Generation IV material issuescitations
- 2010Generation IV material issues:Case SCWRcitations
- 2009SCC properties and oxidation behaviour of austenitic alloys at supercritical water conditions
- 2009EAC Crack Initiation in Ni-based Dissimilar metal Welds using Doped Steam Test
- 2007Hot cracking and environment-assisted cracking susceptibility of dissimilar metal welds
- 2006SCC growth rate quantification in CW 316L stainless steel in PWR primary water using reduced size compact tension specimens
- 2006Post-irradiation SCC investigations on highly-irradiated core internals component materials
- 2006Dissimilar metal weld joints and their performance in nuclear power plant and oil refinery conditions
- 2004Stress corrosion crack growth rate measurement in high temperature water using small precracked bend specimens:Dissertation
- 2004Stress corrosion crack growth rate measurement in high temperature water using small precracked bend specimens
- 2004Comparison of the Electric Properties and ESCA Result of Oxide Films Formed on AISI 316L Steel in Simulated BWR Conditions during SSRTcitations
- 2003Effects of water chemistry transients on crack growth rate of nickel-based weld metals
- 2003Properties and IASCC susceptibility of austenitic stainless steel 08X18H10T
- 2002Facts and views on the role of anionic impurities, crack tip chemistry and oxide films in environmentally assisted cracking
- 2001Irradiation assisted stress corrosion cracking of core components
Places of action
| Organizations | Location | People |
|---|
article
Analysis of mechanisms inducing corrosion cracking of irradiated austenitic steels and development of a model for prediction of crack initiation
Abstract
The austenitic steels used for RPV internals of light water reactors (LWR) are considered. Mechanisms having a potential effect on irradiation assisted stress corrosion cracking (IASCC) of austenitic steels in the LWR environment have been analyzed. Based on the analysis and generalization of reference and original data on IASCC, an IASCC initiation criterion has been formulated. The nature of low-temperature creep of irradiated austenitic steels has been considered, constitutive equations have been derived. Relying on the formulated criterion of grain-boundary microcrack nucleation and the derived creep equations, an IASCC initiation model has been developed. The model allows one to predict the dependence of the threshold stress σ th IASCC on neutron dose and also to calculate the IASCC initiation time with stresses exceeding σ th IASCC .