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Naji, M. |
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Motta, Antonella |
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Aletan, Dirar |
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Mohamed, Tarek |
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Ertürk, Emre |
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Taccardi, Nicola |
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Kononenko, Denys |
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Petrov, R. H. | Madrid |
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Alshaaer, Mazen | Brussels |
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Bih, L. |
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Casati, R. |
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Muller, Hermance |
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Kočí, Jan | Prague |
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Šuljagić, Marija |
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Kalteremidou, Kalliopi-Artemi | Brussels |
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Azam, Siraj |
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Ospanova, Alyiya |
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Blanpain, Bart |
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Ali, M. A. |
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Popa, V. |
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Rančić, M. |
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Ollier, Nadège |
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Azevedo, Nuno Monteiro |
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Landes, Michael |
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Rignanese, Gian-Marco |
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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 |
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report
Environment-assisted cracking and hot cracking susceptibility of nickel-base alloy weld metals
Abstract
The Tekes project PERDI (Performance and ageing ofdissimilar metal joints) was carried out at TKK and VTTduring the period 2006 to 2009. It was primarily drivenby the needs of the nuclear power plant (NPP) industry,but the oil refining, conventional energy production andthe pulp and paper industries also benefitted from theresults and expertise developed in the project. Theextensive studies carried out in the project on weldingtechnology, microstructural characterization,non-destructive examination (NDE) and environmentallyassisted cracking (EAC) revealed a number of openresearch issues regarding the dissimilar metal welds(DMW) and pure Ni-based weld metals of modern nuclearpower plants. Alloy 690 and its associated weld metalsAlloy 152 and Alloy 52 are nowadays widely used forrepair and replacement of thick-section components and inthe construction of new reactors like the EuropeanPressurized Water Reactor (EPR). Some aspects of theproject were focused on the repair welding of BWRdissimilar metal welds, where the repair method and thefiller material were chosen taking into account theresidual stresses produced in the structure, possiblematerial property changes of the remaining materials, andthe resistance of the new weld metal (Alloy 82 or 52) toEAC. In addition to examining the materials propertiesand weldability of DMWs, the studies also covered NDEinspection and residual stress measurement and modellingin DMWs.The weldability research utilized a modern, versatileVarestraint test system for hot crack susceptibilitytesting of the Ni-based alloys used for nuclear and oilrefinery DMWs. Weld metals and hot cracks were examinedusing a modern FEG-SEM/EBSD system and by ATEM.Additionally the solidification and precipitationprocesses were characterized by differential scanningcalorimetry (DSC) methods. It was found that hot crackingis generally associated with the segregation of Nb, Siand Mn in the final melt of the solidifying weld. TheVarestraint test technique was also used for producingcontrolled amounts of hot cracking type defects in thetest samples for subsequent EAC studies carried out atVTT and at Tohoku University, Japan. A full scale DMWmock-up of a thick-wall weld was prepared for an oilrefinery application, and the whole manufacturingprocedure was documented on video film. The mock-up wasthen methodically characterized by both non-destructiveand destructive methods. About 2/3 of the pipe weld wasthen used for a NDE performance demonstration mock-upsample, where all possible defects expected in the oilrefinery conditions were present. Extensive NDE studieswere made of the mock-up sample, and the sample is nowused by Neste Oil for NDE performance demonstrations(separate report [1]).To assess the relative EAC susceptibilities of varioustypes of Alloy 182, 82, 52 and 152 pure weld metals andDMW configurations with and without hot cracks,four-point bend tests were carried out in ahigh-temperature steam environment that was doped withimpurities to enhance crack initiation. The resultsshowed a relatively high susceptibility of Alloys 182 and82 to EAC, while Alloys 152 and 52 showed no crackinitiation. The hot cracks and other weld defects presentin the samples did not show any signs of extension in thedoped steam test, in any of the studied materials. Thecracking mechanism of Alloy 182 and 82 weld metals aswell as Alloy 600 was studied by FEG-SEM and discussedbased on high-temperature electrochemistry and oxidation.The dynamic strain aging (DSA) behaviour of the weldmetals was determined. In an international round robin,crack growth rate data obtained by participants forAlloys 600 and 182 were compared. VTT results were foundto be like those of the others [2].Through the PINC project, an international NDE roundrobin was held using DMW mock-ups provided by NRC, USA.The test results obtained by VTT were analysed andpublished in the PINC final report (separate report [3]).The roles of the stress state and the accessibility ofthe DMWs in the inspection results were especiallyevaluated, and guidance was given on the detectability ofvarious defects by the ultrasonic techniques used forDMWs, as well as on the sizing techniques. The techniquesused in the international round robin were also employedfor the NDE inspections of the Neste Oil mock-up sample.DMWs are at present a major research topic in the nuclearindustry internationally, because a number of crackindications have been detected in DMWs in both BWR andPWR plants. During the PERDI project cooperationagreements were made and joint research was performed orstarted with the following international researchactivities:International Cooperative Research Project onNon-destructive Examinatio...