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LNM Publication List (since 2018)

Cui L, Dai Y, Gerstl SSA, Pounchon MA
APT characterization of irradiation effects on MX phase in reduced-activation ferritic/martensitic steels
Journal of Nuclear Materials. 2023; 573: 154121 (10 pp.). https://doi.org/10.1016/j.jnucmat.2022.154121
DORA PSI
Al-Falahat A'a M, Kardjilov N, Woracek R, Boin M, Markötter H, Theil Kuhn L, et al.
Temperature dependence in Bragg edge neutron transmission measurements
Journal of Applied Crystallography. 2022; 55: 919-928. https://doi.org/10.1107/S1600576722006549
DORA PSI
Bender R, Féron D, Mills D, Ritter S
Corrosion challenges towards a sustainable society
Materials and Corrosion, Werkstoffe und Korrosion. 2022; 73(11): 1730-1751. https://doi.org/10.1002/maco.202213140
DORA PSI
Chen K, Liu Z, Guo X, Wang H, Shen Z, Zeng X
Effect of surface finishing on the oxidation characteristics of a Fe-21Cr-32Ni alloy in supercritical carbon dioxide
Corrosion Science. 2022; 195: 110019 (6 pp.). https://doi.org/10.1016/j.corsci.2021.110019
DORA PSI
Chen M, Van Petegem S, Zou Z, Simonelli M, Tse YY, Chang CST, et al.
Microstructural engineering of a dual-phase Ti-Al-V-Fe alloy via in situ alloying during laser powder bed fusion
Additive Manufacturing. 2022; 59: 103173 (10 pp.). https://doi.org/10.1016/j.addma.2022.103173
DORA PSI
Chen Y, Hou F, Dong S, Guo L, Xia T, He G
Reliability evaluation of corroded pipeline under combined loadings based on back propagation neural network method
Ocean Engineering. 2022; 262: 111910 (10 pp.). https://doi.org/10.1016/j.oceaneng.2022.111910
DORA PSI
Chen K, Zhang L, Shen Z, Zeng X
Revealing the oxidation mechanism of 310S stainless steel in supercritical water via high-resolution characterization
Corrosion Science. 2022; 200: 110212 (10 pp.). https://doi.org/10.1016/j.corsci.2022.110212
DORA PSI
Chen K, Ickes MR, Burke MA, Was GS
The effect of potassium hydroxide primary water chemistry on the IASCC behavior of 304 stainless steel
Journal of Nuclear Materials. 2022; 558: 153323 (11 pp.). https://doi.org/10.1016/j.jnucmat.2021.153323
DORA PSI
Colldeweih AW, Fagnoni F, Trtik P, Zubler R, Pouchon MA, Bertsch J
Delayed hydride cracking in Zircaloy-2 with and without liner at various temperatures investigated by high-resolution neutron radiography
Journal of Nuclear Materials. 2022; 561: 153549 (12 pp.). https://doi.org/10.1016/j.jnucmat.2022.153549
DORA PSI
Colldeweih AW
Delayed hydride cracking in irradiated and unirradiated Zircaloy-2 cladding
2022.
DORA PSI
Colldeweih AW, Bertsch J
Effect of temperature and hydrogen concentration on the threshold stress intensity factor of radial delayed hydride cracking in fuel cladding
Journal of Nuclear Materials. 2022; 565: 153737 (11 pp.). https://doi.org/10.1016/j.jnucmat.2022.153737
DORA PSI
Fagnoni F, Konarski P
Hydrogen degassing of zirconium under high-vacuum conditions
Metals. 2022; 12(5): 868 (9 pp.). https://doi.org/10.3390/met12050868
DORA PSI
Gong W, Trtik P, Ma F, Jia Y, Li J, Bertsch J
Hydrogen diffusion and precipitation under non-uniform stress in duplex zirconium nuclear fuel cladding investigated by high-resolution neutron imaging
Journal of Nuclear Materials. 2022; 570: 153971 (10 pp.). https://doi.org/10.1016/j.jnucmat.2022.153971
DORA PSI
Koszelow D, Molin S, Karczewski J, Marone F, Makowska M
Morphology changes in Fe-Cr porous alloys upon high-temperature oxidation quantified by X-ray tomographic microscopy
Materials and Design. 2022; 215: 110492 (14 pp.). https://doi.org/10.1016/j.matdes.2022.110492
DORA PSI
Kursun EC, Supreeti S, Janssens KGF, Schift H, Spätig P
High optical contrast nanoimprinted speckle patterns for digital image correlation analysis
Micro and Nano Engineering. 2022; 17: 100164 (9 pp.). https://doi.org/10.1016/j.mne.2022.100164
DORA PSI
Lingyun G, Niffenegger M, Jing Z
A novel procedure to evaluate the performance of failure assessment models
Reliability Engineering and System Safety. 2022; 226: 108667 (12 pp.). https://doi.org/10.1016/j.ress.2022.108667
DORA PSI
Mao G, Niffenegger M
Probabilistic and deterministic investigation on single crack growth in dissimilar metal welds of a piping system
International Journal of Pressure Vessels and Piping. 2022; 195: 104566 (13 pp.). https://doi.org/10.1016/j.ijpvp.2021.104566
DORA PSI
Mao G, Niffenegger M, Mao X
Probabilistic risk assessment for the piping of a nuclear power plant: uncertainty and sensitivity analysis by using SINTAP procedure
International Journal of Pressure Vessels and Piping. 2022; 200: 104791 (10 pp.). https://doi.org/10.1016/j.ijpvp.2022.104791
DORA PSI
Maric M, Thomas R, Nunez-Iglesias J, Atkinson M, Bertsch J, Frankel P, et al.
A novel method for radial hydride analysis in zirconium alloys: HAPPy
Journal of Nuclear Materials. 2022; 559: 153442 (14 pp.). https://doi.org/10.1016/j.jnucmat.2021.153442
DORA PSI
Mora DF, Niffenegger M
A new simulation approach for crack initiation, propagation and arrest in hollow cylinders under thermal shock based on XFEM
Nuclear Engineering and Design. 2022; 386: 111582 (14 pp.). https://doi.org/10.1016/j.nucengdes.2021.111582
DORA PSI
Pfeiffer S, Florio K, Makowska M, Marone F, Yüzbasi S, Aneziris CG, et al.
Crack-reduced alumina/aluminum titanate composites additive manufactured by laser powder bed fusion of black TiO_2-x doped alumina granules
Journal of the European Ceramic Society. 2022; 42(8): 3515-3529. https://doi.org/10.1016/j.jeurceramsoc.2022.02.046
DORA PSI
Que Z, Seifert HP, Mazánová V, Spätig P
Hydrogen embrittlement on fracture resistance of low-alloy reactor pressure vessel steel with high dynamic strain aging at 288 °C
Materials Letters. 2022; 308: 131269 (5 pp.). https://doi.org/10.1016/j.matlet.2021.131269
DORA PSI
Que Z, Zajec B, Ritter S, Seppänen T, Saario T, Toivonen A, et al.
Investigation of surface treatment effects on the environmentally-assisted cracking behaviour of Alloy 182 in boiling water reactor environment
Corrosion Engineering Science and Technology. 2022; 57(5): 474-485. https://doi.org/10.1080/1478422X.2022.2083746
DORA PSI
Ritter S, Seifert H-P
Impact of chloride on the environmentally-assisted crack initiation behaviour of low-alloy steel under boiling water reactor conditions
Corrosion and Materials Degradation. 2022; 3(2): 178-191. https://doi.org/10.3390/cmd3020010
DORA PSI
Singh S, Suman S, Mitra S, Kumar M
ANN model for prediction of thermo-hydraulic performance of a solar air heater with vertical cylindrical ribs
Energy Reports. 2022; 8(Suppl. 15): 585-592. https://doi.org/10.1016/j.egyr.2022.10.263
DORA PSI
Singh S, Suman S, Mitra S, Kumar M
Solar air heater with rotating circular ribs: hybrid CFD-ANN approach for prediction of thermo-hydraulic performance
Energy Reports. 2022; 8(Suppl. 15): 145-150. https://doi.org/10.1016/j.egyr.2022.10.084
DORA PSI
Song P, Spätig P
Effects of ball size and microstructures on indentation curves of Fe9Cr model alloys and tempered martensitic steel Eurofer97
Nuclear Materials and Energy. 2022; 30: 101143 (7 pp.). https://doi.org/10.1016/j.nme.2022.101143
DORA PSI
Song P, Yabuuchi K, Spätig P
Insights into hardening, plastically deformed zone and geometrically necessary dislocations of two ion-irradiated FeCrAl(Zr)-ODS ferritic steels: a combined experimental and simulation study
Acta Materialia. 2022; 234: 117991 (12 pp.). https://doi.org/10.1016/j.actamat.2022.117991
DORA PSI
Trtik P, Welte J, Yetik O, Grünberger S, Kalt A, Hovind J, et al.
Neutron tomography of a highly irradiated spallation target rod
Journal of Radioanalytical and Nuclear Chemistry. 2022. https://doi.org/10.1007/s10967-022-08559-9
DORA PSI
Wang J, Zhu T, Chen K, Bao Y, Ma W, Zhang M, et al.
Investigations on the SCC initiation behavior of cold worked 316 L in high temperature oxygenated water at constant loads
Corrosion Science. 2022; 203: 110336 (18 pp.). https://doi.org/10.1016/j.corsci.2022.110336
DORA PSI
Abolhassani S, Baris A, Grabherr R, Hawes J, Colldeweih A, Vanta R, et al.
Towards an improved understanding of the mechanisms involved in the increased hydrogen uptake and corrosion at high burnups in zirconium based claddings
In: Motta AT, Yagnik SK, eds. Zirconium in the nuclear industry: 19th international symposium. Vol. STP1622. ASTM International: selected technical papers. West Conshohocken, PA: ASTM International; 2021:435-466. https://doi.org/10.1520/STP162220190052
DORA PSI
Balbaud F, Cabet C, Cornet S, Dai Y, Gan J, Hernández Mayoral M, et al.
A NEA review on innovative structural materials solutions, including advanced manufacturing processes for nuclear applications based on technology readiness assessment
Nuclear Materials and Energy. 2021; 27: 101006 (13 pp.). https://doi.org/10.1016/j.nme.2021.101006
DORA PSI
Bosch R-W, Ritter S, Herbst M, Kilian R, Burke MG, Duff J, et al.
Stress corrosion crack initiation testing with tapered specimens in high-temperature water - results of a collaborative research project
Corrosion Engineering Science and Technology. 2021; 56(2): 103-118. https://doi.org/10.1080/1478422X.2020.1815460
DORA PSI
Bruchhausen M, Dundulis G, McLennan A, Arrieta S, Austin T, Cicero R n, et al.
Characterization of austenitic stainless steels with regard to environmentally assisted fatigue in simulated light water reactor conditions
Metals. 2021; 11(2): 307 (20 pp.). https://doi.org/10.3390/met11020307
DORA PSI
Chen W, Spätig P, Seifert HP
Role of mean stress on fatigue behavior of a 316L austenitic stainless steel in LWR and air environments
International Journal of Fatigue. 2021; 145: 106111 (14 pp.). https://doi.org/10.1016/j.ijfatigue.2020.106111
DORA PSI
Colldeweih AW, Fagnoni F, Pouchon MA, Bertsch J, Trtik P
Effect of the inner liner on radial delayed hydride cracking
In: TopFuel2021. Brussels: European Nuclear Society; 2021:(6 pp.).
DORA PSI
Cozzo C, Lind T, Bertsch J, Nichenko S, Girardin G
Quantifying the benefits of the reduced oxidation kinetics in chromium-coated cladding: a parametric study
In: Vázquez-Rodriguez C, Jiménez Carrascosa A, Estevez Albuja S, Duran Vinuesa LF, eds. Book of Proceedings. European nuclear young generation forum 2021. sine loco: European Nuclear Young Generation Forum; 2021:245-248.
DORA PSI
Cui L, Li J, Gerstl S, Pouchon M, Dai Y
Quantitative APT analysis of solid transmutants in ferritic-martensitic steels after irradiation in SINQ targets: experimental validation of neutronic calculations
Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms. 2021; 502: 1-9. https://doi.org/10.1016/j.nimb.2021.05.017
DORA PSI
Dai Y, Boutellier V, Grabherr R, Urech A, Blau B, Welte J, et al.
Post-irradiation examinations of SINQ Target-11
In: Kikuchi K, ed. Spallation materials technology. Materials science forum. Baech, Switzerland: Trans Tech Publications Ltd.; 2021:41-52. https://doi.org/10.4028/www.scientific.net/MSF.1024.41
DORA PSI
Duarte LI, Fagnoni F, Zubler R, Gong W, Trtik P, Bertsch J
Effect of the inner liner on the hydrogen distribution of zircaloy-2 nuclear fuel claddings
Journal of Nuclear Materials. 2021; 557: 153284 (6 pp.). https://doi.org/10.1016/j.jnucmat.2021.153284
DORA PSI
Duarte LI, Yetik O, Fagnoni F, Colldeweih A, Zubler R, Bertsch J, et al.
Neutron radiography imaging: a tool for determination of hydrogen distribution in unirradiated and irradiated fuel claddings
In: TopFuel2021. Brussels: European Nuclear Society; 2021:(10 pp.).
DORA PSI
Duquesne L, Bischoff J, Buchanan K, Schweitzer E, Nimishakavi K, Girardin G, et al.
Framatome's evolutionary ATF solution: feedback from the irradiation programs on PROtect's Cr-coated M5_Framatome cladding
In: TopFuel2021. Brussels: European Nuclear Society; 2021:(10 pp.).
DORA PSI
Fagnoni F, Duarte LI, Bertsch J, Wheeler JM
Elevated temperature nanoindentation of Zry-4 in the presence of hydrogen in solid solution
In: TopFuel2021. Brussels: European Nuclear Society; 2021:(8 pp.).
DORA PSI
Fütterer MA, Strydom G, Sato H, Li F, Abonneau E, Abram T, et al.
The high temperature gas-cooled reactor
In: Greenspan E, ed. Encyclopedia of nuclear energy. sine loco: Elsevier; 2021:512-522. https://doi.org/10.1016/B978-0-12-409548-9.12205-5
DORA PSI
Guo L, Niffenegger M, Jing Z
Statistical inference and performance evaluation for failure assessment models of pipeline with external axial surface cracks
International Journal of Pressure Vessels and Piping. 2021; 194: 104480 (20 pp.). https://doi.org/10.1016/j.ijpvp.2021.104480
DORA PSI
Hawes J, Warnicke P, Burr P, Ferreira Sanchez D, Grolimund D, Partezana J, et al.
The speciation of niobium in the oxide layer of an irradiated Low-Tin ZIRLO nuclear material
Corrosion Science. 2021; 190: 109630 (12 pp.). https://doi.org/10.1016/j.corsci.2021.109630
DORA PSI
Jiang W, Gu L, Zhu Q-F, Zhou Q, Ma F, Zhang L, et al.
RETRACTED: Reactivity worth measurement of the lead target on VENUS-II light water reactor and validation of evaluated nuclear data
Annals of Nuclear Energy. 2021; 154: 108106 (8 pp.). https://doi.org/10.1016/j.anucene.2020.108106
DORA PSI
Karabanova A, Berdiyeva P, Helfen L, Tengattini A, Bücherl T, Makowska MG, et al.
Neutron radiography for local modelling of thermochemical heat storage reactors: case study on SrCl₂-NH₃
International Journal of Heat and Mass Transfer. 2021; 178: 121287 (11 pp.). https://doi.org/10.1016/j.ijheatmasstransfer.2021.121287
DORA PSI
Koszelow D, Makowska M, Marone F, Karczewski J, Jasiński P, Molin S
High temperature corrosion evaluation and lifetime prediction of porous Fe22Cr stainless steel in air in temperature range 700-900°C
Corrosion Science. 2021; 189: 109589 (11 pp.). https://doi.org/10.1016/j.corsci.2021.109589
DORA PSI
Lehmann E, Thomsen K, Strobl M, Trtik P, Bertsch J, Dai Y
NEURAP - a dedicated neutron-imaging facility for highly radioactive samples
Journal of Imaging. 2021; 7(3): 57 (14 pp.). https://doi.org/10.3390/jimaging7030057
DORA PSI
Li J-Y, Dai Y, Gu L, Zhang Y-P, He Z-Y, Xu H-S, et al.
Genetic algorithm based temperature control of the dense granular spallation target in China initiative accelerator driven system
Annals of Nuclear Energy. 2021; 154: 108127 (8 pp.). https://doi.org/10.1016/j.anucene.2021.108127
DORA PSI
Li J-Y, Gu L, Xu H-S, Zhang Y-P, Dai Y, Yao C-F, et al.
Neutronics analysis of thorium-uranium based molten salt blanket in stellarator-type FFHR
Fusion Engineering and Design. 2021; 162: 112098 (8 pp.). https://doi.org/10.1016/j.fusengdes.2020.112098
DORA PSI
Li J-Y, Gu L, Xu H-S, Dai Y, Zhang Y-P, Yao C-F, et al.
The PyNE-based burnup analysis method for accelerator-driven subcritical systems
Nuclear Technology. 2021; 207(2): 270-284. https://doi.org/10.1080/00295450.2020.1757963
DORA PSI
Mackiewicz A, Ritter S, Chen K, Seifert H-P, Virtanen S
Zinc injection in light water reactors to mitigate stress corrosion cracking of Alloy 182 and 316L stainless steel
Presented at: Annual meeting of the international cooperative group on environmentally-assisted cracking of water reactor materials; May 17-21, 2021; Mills River, USA.
DORA PSI
Mackiewicz A, Ritter S, Chen K, Seifert H-P, Virtanen S
Zinc injection in light water reactors to mitigate stress corrosion cracking of alloy 182 and cold-worked type 316L stainless steel
Presented at: EUROCORR 2021. The European corrosion congress; September 20-24, 2021; Budapest.
DORA PSI
Malerba L, Caturla MJ, Gaganidze E, Kaden C, Konstantinović MJ, Olsson P, et al.
Multiscale modelling for fusion and fission materials: the M4F project
Nuclear Materials and Energy. 2021; 29: 101051 (34 pp.). https://doi.org/10.1016/j.nme.2021.101051
DORA PSI
Mao X, Chen D, Wang Y, Mao G, Zheng Y
Investigation on optimization of self-adaptive closure law for load rejection to a reversible pump turbine based on CFD
Journal of Cleaner Production. 2021; 283: 124739 (15 pp.). https://doi.org/10.1016/j.jclepro.2020.124739
DORA PSI
Mora DFM, Niffenegger M
Crack propagation calculation for axial cracks in hollow cylinders subjected to thermal shock
In: Proceedings of ASME 2021 pressure vessels and piping conference (PVP 2021). Vol. 2. American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP. American Society of Mechanical Engineers (ASME); 2021:PVP2021-61406 (8 pp.). https://doi.org/10.1115/PVP2021-61406
DORA PSI
Niffenegger M, Solaz VH
Microstructural based fem-calculation of stress/strain fields in steel aisi 316l and its validation by digital image correlation
In: ASME Pressure Vessels and Piping Conference. Vol. 2. American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP. Danvers, MA: American Society of Mechanical Engineers (ASME); 2021:PVP2021-62779 (10 pp.). https://doi.org/10.1115/PVP2021-62779
DORA PSI
Pouchon MA, Nordström L-Å, Hellwig C
Modeling of sphere-pac fuel
In: Konings RJM, Stoller RE, eds. Comprehensive nuclear materials. Amsterdam: Elsevier; 2021:436-463. https://doi.org/10.1016/B978-0-08-102865-0.00068-6
DORA PSI
Prakash S, Suman S
Neural network-based prediction for surface characteristics in CO₂ laser micro-milling of glass fiber reinforced plastic composite
Neural Computing & Applications. 2021; 33: 11517-11529. https://doi.org/10.1007/s00521-021-05818-w
DORA PSI
Rao GS, Yagodzinskyy Y, Que Z, Spätig P, Seifert HP
Study on hydrogen embrittlement and dynamic strain ageing on low-alloy reactor pressure vessel steels
Journal of Nuclear Materials. 2021; 556: 153161 (13 pp.). https://doi.org/10.1016/j.jnucmat.2021.153161
DORA PSI
Ritter S, Bosch R-W, Huet F, Ngo K, Cottis RA, Bakalli M, et al.
Results of an international round-robin exercise on electrochemical impedance spectroscopy
Corrosion Engineering Science and Technology. 2021; 56(3): 254-268. https://doi.org/10.1080/1478422X.2020.1850070
DORA PSI
Seifert H-P, Bertsch J
Materials and corrosion issues in the primary coolant circuit of boiling water reactors
Tech. Ing. 2021:EBN 3 762 (30 pp.).
DORA PSI
Singh S, Noky J, Bhattacharya S, Vir P, Sun Y, Kumar N, et al.
Anisotropic nodal-line-rerived large anomalous hall conductivity in ZrMnP and HfMnP
Advanced Materials. 2021; 33(48): 2104126 (6 pp.). https://doi.org/10.1002/adma.202104126
DORA PSI
Singh S, Mitra S, Kumar M, Suman S
Thermal performance evaluation of a solar air heater with rotating turbulators
Sustainable Energy Technologies and Assessments. 2021; 48: 101647 (19 pp.). https://doi.org/10.1016/j.seta.2021.101647
DORA PSI
Spätig P, Roux JCL, Bruchhausen M, Mottershead K
Mean stress effect on the fatigue life of 304L austenitic steel in air and pwr environments determined with strain-and load-controlled experiments
Metals. 2021; 11(2): 1-14. https://doi.org/10.3390/met11020221
DORA PSI
Torregrosa Martin C, Solieri N, Fornasiere E, Busom Descarrega J, Calviani M, Canhoto Espadanal J, et al.
First observation of spalling in tantalum at high temperatures induced by high energy proton beam impacts
European Journal of Mechanics: A/Solids. 2021; 85: 104149 (16 pp.). https://doi.org/10.1016/j.euromechsol.2020.104149
DORA PSI
Trummer D, Searles K, Algasov A, Guda SA, Soldatov AV, Ramanantoanina H, et al.
Deciphering the Phillips catalyst by orbital analysis and supervised machine learning from Cr pre-edge XANES of molecular libraries
Journal of the American Chemical Society. 2021; 143(19): 7326-7341. https://doi.org/10.1021/jacs.0c10791
DORA PSI
Verga F, Makowska M, Cellerai G, Florio K, Schmid M, Wegener K
Crack-healing, a novel approach for a laser-based powder bed fusion of high-performance ceramic oxides
Additive Manufacturing Letters. 2021; 1: 100021 (7 pp.). https://doi.org/10.1016/j.addlet.2021.100021
DORA PSI
Vladislavova L, Smolorz T, Orlovskaya N, Lugovy M, Reece MJ, Kӧbel S, et al.
Strength analysis and stress-strain deformation behavior of 3 mol% Y-TZP and 21 wt.% Al₂O₃-3 mol% Y-TZP
Materials. 2021; 14(14): 3903 (20 pp.). https://doi.org/10.3390/ma14143903
DORA PSI
Warnicke P, Ramanantoanina H, Li J, Dai Y, Pouchon MA
Quantitative analysis of rhenium in irradiated tungsten
Journal of Nuclear Materials. 2021; 554: 153014 (9 pp.). https://doi.org/10.1016/j.jnucmat.2021.153014
DORA PSI
Yao CF, Dai Y
DBTT shift of Optifer-IX, Eurofer 97 and MA956 steels after irradiation evaluated with small punch tests
Journal of Nuclear Materials. 2021; 544: 152725 (9 pp.). https://doi.org/10.1016/j.jnucmat.2020.152725
DORA PSI
Yetik O, Duarte LI, Fagnoni F, Colldeweih A, Zubler R, Pouchon MA, et al.
Influence of scattering correction on quantitative hydrogen analysis of fuel claddings using high resolution neutron radiography
In: TopFuel2021. Brussels: European Nuclear Society; 2021:(10 pp.).
DORA PSI
Chen J, Jacques S, Barthe M-F, Zhang C, Desgardin P
In-beam creep of SiC_f/SiC minicomposites under uniaxial tensile loading
Journal of Nuclear Materials. 2020; 533: 152086 (7 pp.). https://doi.org/10.1016/j.jnucmat.2020.152086
DORA PSI
Chen B, Janssens KGF, Dunne FPE
Role of geometrically necessary dislocation density in multiaxial and non-proportional fatigue crack nucleation
International Journal of Fatigue. 2020; 135: 105517 (13 pp.). https://doi.org/10.1016/j.ijfatigue.2020.105517
DORA PSI
Dai Y, Odette GR, Yamamoto T
The effects of helium in irradiated structural alloys
In: Konings RJM, Stoller RE, eds. Comprehensive nuclear materials. Amsterdam: Elsevier; 2020:186-234. https://doi.org/10.1016/B978-0-12-803581-8.12046-6
DORA PSI
Fagnoni F, Duarte LI, Wheeler JM, Bertsch J
High temperature nanoindentation of hydrogenated Zry-4
Presented at: NuMat 2020; October 26-29, 2020; Ghent, Belgium.
DORA PSI
Féron D, Ritter S
Fifty years of nuclear corrosion in Europe: evolutions and contributions of the working party on nuclear corrosion
In: Ritter S, ed. Nuclear corrosion: research, progress and challenges. European Federation of Corrosion publications. Cambridge; Kidlington: Elsevier; 2020:1-17. https://doi.org/10.1016/B978-0-12-823719-9.00001-9
DORA PSI
Hawes J, Baris A, Chiu Y-L, Abolhassani S
Characterization of the conductivity of metal-oxide interface of zirconium based fuel cladding at low and high burnups
Journal of Nuclear Materials. 2020; 534: 152133 (12 pp.). https://doi.org/10.1016/j.jnucmat.2020.152133
DORA PSI
Hawes JED
The causes of increased hydrogen uptake of zirconium based fuel claddings at high burnup
2020.
DORA PSI
Herrera-Solaz V, Cepeda-Jiménez CM, Pérez-Prado MT, Segurado J, Niffenegger M
The influence of underlying microstructure on surface stress and strain fields calculated by crystal plasticity finite element method
Materials Today Communications. 2020; 24: 101176 (11 pp.). https://doi.org/10.1016/j.mtcomm.2020.101176
DORA PSI
Janssens KGF
Universal cycle counting for non-proportional and random fatigue loading
International Journal of Fatigue. 2020; 133: 105409 (11 pp.). https://doi.org/10.1016/j.ijfatigue.2019.105409
DORA PSI
Kirk E, Bull C, Finizio S, Sepehri-Amin H, Wintz S, Suszka AK, et al.
Anisotropy-induced spin reorientation in chemically modulated amorphous ferrimagnetic films
Physical Review Materials. 2020; 4(7): 074403 (7 pp.). https://doi.org/10.1103/PhysRevMaterials.4.074403
DORA PSI
Kurihara E, Takehara M, Suetake M, Ikehara R, Komiya T, Morooka K, et al.
Particulate plutonium released from the Fukushima Daiichi meltdowns
Science of the Total Environment. 2020; 743: 140539 (10 pp.). https://doi.org/10.1016/j.scitotenv.2020.140539
DORA PSI
Li J-Y, Gu L, Xu H-S, Dai Y, Zhang Y-P, Yu R, et al.
FreeCAD based Monte Carlo modeling approach for fusion reactor facilities
Fusion Engineering and Design. 2020; 155: 111711 (10 pp.). https://doi.org/10.1016/j.fusengdes.2020.111711
DORA PSI
Mao X, Liu Z, Li T, Mao G, Chen D
A brief review of numerical solving methods for internal fluid of pumped storage unit
International Journal of Energy Research. 2020; 44(10): 7886-7902. https://doi.org/10.1002/er.5474
DORA PSI
Mclennan A, Spätig P, Le Roux J-C, Waters J, Gill P, Beswick J, et al.
INCEFA-PLUS project: the impact of using fatigue data generated from multiple specimen geometries on the outcome of a regression analysis
In: Volume 1: codes and standards. Vol. 1. Pressure vessels and piping conference. New York, NY, USA: ASME; 2020:V001T01A017. https://doi.org/10.1115/PVP2020-21422
DORA PSI
Meadows PJ, Andresen PL, Toloczko MB, Kuang W-J, Ritter S, Bjurman M, et al.
International round-robin on stress corrosion crack initiation of Alloy 600 material in pressurized water reactor primary water
Corrosion. 2020; 76(8): 719-733. https://doi.org/10.5006/3532
DORA PSI
Mebtouche F, Zergoug T, El Hak Abaidia S, Bertsch J, Seddik Kebaili AB, Nedjar A
The effect of (Si, Cr, Fe, Ni, Nb, Sn) and monovacancy on hydrogen incorporation into Zr (0001): ab initio insights
Computational and Theoretical Chemistry. 2020; 1178: 112781 (9 pp.). https://doi.org/10.1016/j.comptc.2020.112781
DORA PSI
Mora DF, Niffenegger M, Mukin R
Crack propagation modeling in a PWR under PTS Using XFEM
In: Volume 6: materials and fabrication. Vol. 6. Pressure vessels and piping conference. New York, NY, USA: ASME; 2020:V006T06A001. https://doi.org/10.1115/PVP2020-21026
DORA PSI
Mora DF, Costa Garrido O, Mukin R, Niffenegger M
Fracture mechanics analyses of a reactor pressure vessel under non-uniform cooling with a combined TRACE-XFEM approach
Engineering Fracture Mechanics. 2020; 238: 107258 (16 pp.). https://doi.org/10.1016/j.engfracmech.2020.107258
DORA PSI
Mouginot R, Spätig P, Seifert H-P
Dynamic study of contact damping in martensitic stainless steels using nano-indentation
Mechanics of Materials. 2020; 149: 103541 (10 pp.). https://doi.org/10.1016/j.mechmat.2020.103541
DORA PSI
Niffenegger M, Mora DF, Kottmann H
Non-destructive evaluation of RPV embrittlement by means of the thermoelectric power method
In: Non-destructive examination. Emerging NDE and prognostic techniques and applications. Vol. 7. Pressure vessels and piping conference. New York, NY, USA: ASME; 2020:V007T07A002 (8 pp.). https://doi.org/10.1115/PVP2020-21446
DORA PSI
Pouchon MA, Ledergerber G, Ingold F, Bakker K
Sphere-pac and Vipac fuel
In: Konings RJM, Stoller RE, eds. Comprehensive nuclear materials. sine loco: Elsevier; 2020:398-435. https://doi.org/10.1016/B978-0-12-803581-8.12050-8
DORA PSI
Que Z, Heczko M, Kuběna I, Seifert HP, Spätig P
Microstructural characterization of the synergic effects of dynamic strain ageing and hydrogen on fracture behaviour of low-alloy RPV steels in high-temperature water environments
Materials Characterization. 2020; 165: 110405 (12 pp.). https://doi.org/10.1016/j.matchar.2020.110405
DORA PSI
Ramanantoanina H, Merzoud L, Muya JT, Chermette H, Daul C
Electronic structure and photoluminescence properties of Eu(ƞ⁹-C₉H₉)₂
Journal of Physical Chemistry A. 2020; 124(1): 152-164. https://doi.org/10.1021/acs.jpca.9b09755
DORA PSI
Ramanantoanina H, Gruden M
Theoretical insight into the magnetic circular dichroism of uranium N_6,7-edge X-ray absorption
International Journal of Quantum Chemistry. 2020; 120(3): e26081 (8 pp.). https://doi.org/10.1002/qua.26081
DORA PSI
Rowthu S, Grundler PV, Müller E, Ritter S
Pt catalytic effects on the corrosion and hydrogen chemisorption properties of Zircaloy-2
Journal of Nuclear Materials. 2020; 544: 152716 (15 pp.). https://doi.org/10.1016/j.jnucmat.2020.152716
DORA PSI
Ruiz-Moreno A, Hähner P, Kurpaska L, Jagielski J, Spätig P, Trebala M, et al.
Round robin into best practices for the determination of indentation size effects
Nanomaterials. 2020; 10(1): 130 (15 pp.). https://doi.org/10.3390/nano10010130
DORA PSI
Saito S, Suzuki K, Hatakeyama Y, Suzuki M, Dai Y
Experimental validation of tensile properties measured with thick samples taken from MEGAPIE target
Journal of Nuclear Materials. 2020; 534: 152146 (16 pp.). https://doi.org/10.1016/j.jnucmat.2020.152146
DORA PSI
Seifert H-P, Hickling J, Lister D
Corrosion and environmentally-assisted cracking of carbon and low-alloy steels
In: Konings RJM, Stoller RE, eds. Comprehensive nuclear materials. 2020: Elsevier; 2020:129-189. https://doi.org/10.1016/B978-0-12-803581-8.11763-1
DORA PSI
Seifert H-P, Ritter S
Environmentally-assisted cracking of carbon and low-alloy steels in light water reactors
In: Ritter S, ed. Nuclear corrosion: research, progress and challenges. European Federation of Corrosion publications. Cambrige; Kidlington: Elsevier; 2020:119-211. https://doi.org/10.1016/B978-0-12-823719-9.00005-6
DORA PSI
Spätig P, Mazánová V, Suman S, Seifert HP
Evaluation of quasi-static and dynamic fracture toughness on the low-alloy reactor pressure vessel steel JRQ in the transition region
In: Paipetis SA, Aliabadi FMH, eds. Advances in fracture and damage mechanics XVIII. Vol. 827. Key engineering materials. sine loco: Trans Tech Publications; 2020:294-299. https://doi.org/10.4028/www.scientific.net/KEM.827.294
DORA PSI
Sáez-Maderuelo A, Perosanz-Lopez FJ, Molinero-Merino L, Ritter S, Ehrnsten U, Burke MG, et al.
Mitigating environmentally-assisted cracking through optimisation of surface condition
Presented at: EUROCORR 2020; September 7-11, 2020; online.
DORA PSI
Tirbonod B
Simulations of isothermal and thermomechanical fatigue of a polycrystal made out of austenitic stainless steels and relation to the Coffin-Manson law
Theoretical and Applied Fracture Mechanics. 2020; 109: 102656 (13 pp.). https://doi.org/10.1016/j.tafmec.2020.102656
DORA PSI
Trtik P, Zubler R, Gong W, Grabherr R, Bertsch J, Duarte LI
Sample container for high-resolution neutron imaging of spent nuclear fuel cladding sections
Review of Scientific Instruments. 2020; 91(5): 056103 (3 pp.). https://doi.org/10.1063/1.5143226
DORA PSI
Volpe L, Burke MG, Zaiqing Q, Ehrnstén U, Treichel A, Ritter S, et al.
Exploring the effect of surface machining treatments on microstructure of cold-rolled type 316L austenitic stainless steel and Alloy 182
Presented at: EUROCORR 2020; September 7-11, 2020; online.
DORA PSI
Wu W, Schäublin R
Synergistic effects of anisotropy and image force on TEM diffraction contrast of dislocation loops
Journal of Microscopy. 2020; 278(1): 29-41. https://doi.org/10.1111/jmi.12884
DORA PSI
Ritter S, ed.
Nuclear corrosion: research, progress and challenges
Cambridge; Kidlington: Elsevier; 2020. https://doi.org/10.1016/B978-0-12-823719-9.00014-7
DORA PSI
Aulet D, Dai Y, Bergmann RM, Wohlmuther M
Radiation damage assessment of the sixth SINQ target irradiation program based on MCNPX simulation
Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2019; 922: 310-321. https://doi.org/10.1016/j.nima.2018.12.013
DORA PSI
Baris A
Increased hydrogen uptake of zirconium based claddings ata high burnup
2019.
DORA PSI
Bosch R-W, Cottis RA, Huet F, Ngo K, Ritter S
Reliability of electrochemical impedance spectroscopy measurements: results of round‐robin testing
Presented at: 11th international symposium on electrochemical impedance spectroscopy (EIS 2019); June 2-7, 2019; Lège-Cap-Ferret, France.
DORA PSI
Chen W, Spätig P, Seifert HP
Mean stress effect on fatigue behavior of austenitic stainless steel in air and LWR conditions
In: Correia JAFO, De Jesus AMP, Fernandes AA, Calçada R, eds. Mechanical fatigue of metals. Experimental and simulation perspectives. Vol. 7. Structural integrity. Cham: Springer; 2019:57-63. https://doi.org/10.1007/978-3-030-13980-3_8
DORA PSI
Chen B, Janssens K, Dunne F
Multiaxial and non-proportional microstructure-sensitive fatigue crack nucleation
In: Palin-Luc T, Morel F, Carpinteri A, eds. ICMFF12 - 12th international conference on multiaxial fatigue and fracture. Vol. 300. MATEC web of conferences. sine loco: EDP Sciences; 2019:010001 (13 pp.). https://doi.org/10.1051/matecconf/201930001001
DORA PSI
Colldeweih AW, Baris A, Spätig P, Abolhassani S
Evaluation of mechanical properties of irradiated zirconium alloys in the vicinity of the metal-oxide interface
Materials Science and Engineering A: Structural Materials: Properties, Microstructure and Processing. 2019; 742: 842-850. https://doi.org/10.1016/j.msea.2018.09.107
DORA PSI
Colldeweih AW, Gong W, Zubler R, Bertsch J, Trtik P
Influence of cracking direction on fracture mechanics during DHC of Zircaloy-2 cladding
In: Global/top fuel 2019. La Grange Park, IL, USA: American Nuclear Society (ANS); 2019:240-245.
DORA PSI
Cozzo C, Ngayam-Happy R, Chen J-C, Pecchia M, Girardin G
Modeling of the U₃Si₂/SiC fuel system behavior for a RIA scenario
In: Global/top fuel 2019. LaGrange Park, IL, USA: American Nuclear Society (ANS); 2019:643-647.
DORA PSI
Duarte LI, Fagnoni F, Zubler R, Gong W, Trtik P, Bertsch J
Hydride characterization in Zircaloy-2 liner cladding after C-shaped ring compression tests
In: Global/top fuel 2019. La Grange Park, IL, USA: American Nuclear Society (ANS); 2019:166-172.
DORA PSI
Duarte LI, Fagnoni F, Zubler R, Gong W, Trtik P, Bertsch J
Hydrides in irradiated liner cladding - local and in-depth concentration determination by neutron radiography
In: Global/top fuel 2019. La Grange Park, IL, USA: American Nuclear Society (ANS); 2019:928-932.
DORA PSI
Gong W, Mille M, Zubler R, Bertsch J
Anisotropic influence of hydrides on Zircaloy fatigue
In: Global/top fuel 2019. La Grange Park, IL, USA: American Nuclear Society (ANS); 2019:334-343.
DORA PSI
Gong W, Trtik P, Zubler R, Bertsch J
Hydride reorientation and redistribution under non-uniform stress
In: Global/top fuel 2019. La Grange Park, IL, USA: American Nuclear Society (ANS); 2019:354-359.
DORA PSI
Gong W, Trtik P, Colldeweih AW, Duarte LI, Grosse M, Lehmann E, et al.
Hydrogen diffusion and precipitation in duplex zirconium nuclear fuel cladding quantified by high-resolution neutron imaging
Journal of Nuclear Materials. 2019; 526: 151757 (13 pp.). https://doi.org/10.1016/j.jnucmat.2019.151757
DORA PSI
Grundler PV, Ritter S, Rowthu S, Seifert H-P
Assessment of the SCC mitigation capabilities of the noble metal chemical application technology in a simulated BWR environment
In: Nineteenth international conference on environmental degradation of materials in nuclear power systems - water reactors. La Grange Park: American Nuclear Society (ANS); 2019:189-198.
DORA PSI
Grundler PV, Ritter S, Veleva L
SCC mitigation in boiling water reactors: platinum deposition and durability on structural materials
In: Jackson JH, Paraventi D, Wright M, eds. Proceedings of the 18th international conference on environmental degradation of materials in nuclear power systems – water reactors. Vol. 2. The minerals, metals & materials series. Cham: Springer; 2019:1685-1700. https://doi.org/10.1007/978-3-030-04639-2_113
DORA PSI
Guo H, Warnicke P, Griffa M, Müller U, Chen Z, Schaeublin R, et al.
Hierarchical porous wood cellulose scaffold with atomically dispersed Pt catalysts for low-temperature ethylene decomposition
ACS Nano. 2019; 13(12): 14337-14347. https://doi.org/10.1021/acsnano.9b07801
DORA PSI
Habainy J, Dai Y, Lee Y, Iyengar S
Mechanical properties of tungsten irradiated with high-energy protons and spallation neutrons
Journal of Nuclear Materials. 2019; 514: 189-195. https://doi.org/10.1016/j.jnucmat.2018.12.003
DORA PSI
Habainy J, Lee Y, Surreddi KB, Prosvetov A, Simon P, Iyengar S, et al.
Study of heavy ion beam induced damage in tungsten for high power target applications
Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms. 2019; 439: 7-16. https://doi.org/10.1016/j.nimb.2018.11.017
DORA PSI
Herrera-Solaz V, Patriarca L, Segurado J, Niffenegger M
Microstructure-based modelling and digital image correlation measurement of (residual) strain fields in austenitic stainless steel 316L during tension loading
In: Gdoutos EE, ed. Proceedings of the first international conference on theoretical, applied and experimental mechanics. Vol. 5. Structural integrity. Cham: Springer; 2019:313-314. https://doi.org/10.1007/978-3-319-91989-8_66
DORA PSI
Herrera-Solaz V, Patriarca L, Foletti S, Segurado J, Niffenegger M
Microstructure-based modelling and digital image correlation measurement of strain fields in austenitic stainless steel 316L during tension loading
Materials Science and Engineering A: Structural Materials: Properties, Microstructure and Processing. 2019; 751: 99-106. https://doi.org/10.1016/j.msea.2019.02.063
DORA PSI
Horváth B, Schäublin R, Dai Y
Flash electropolishing of TEM lamellas of irradiated tungsten
Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms. 2019; 449: 29-34. https://doi.org/10.1016/j.nimb.2019.04.047
DORA PSI
Janssens KGF
A universal, damage-criterion-independent cycle counting method for multiaxial and variable amplitude fatigue
In: Palin-Luc T, Morel F, Carpinteri A, eds. ICMFF12 - 12th international conference on multiaxial fatigue and fracture. Vol. 300. MATEC web of conferences. sine loco: EDP Sciences; 2019:17004 (8 pp.). https://doi.org/10.1051/matecconf/201930017004
DORA PSI
Korepanova N, Gu L, Zhang L, Dai Y
Evaluation of displacement cross-section for neutron-irradiated 15-15Ti steel and its swelling behavior in CiADS radiation environment
Annals of Nuclear Energy. 2019; 133: 937-949. https://doi.org/10.1016/j.anucene.2019.07.035
DORA PSI
Krsjak V, Degmova J, Simeg Veternikova J, Yao CF, Dai Y
Experimental comparison of the (ODS)EUROFER steels implanted by helium ions and irradiated in spallation neutron target
Journal of Nuclear Materials. 2019; 523: 51-55. https://doi.org/10.1016/j.jnucmat.2019.05.044
DORA PSI
Krsjak V, Vieh C, Dai Y
Microstructural aspects of helium bubbles formation in ferritic martensitic steels
In: Selim F, ed. The 18th international conference on positron annihilation (ICPA-18): positron annihilation spectroscopy-fundamentals, techniques ad applications. Vol. 2182. AIP conference proceedings. sine loco: AIP Publishing; 2019:050026 (5 pp.). https://doi.org/10.1063/1.5135869
DORA PSI
Martin TL, Warren AD, Kumar D, Siberry A, Springell R, Holmes R, et al.
Insights into prospective fusion reactor coolong systems from fission reactor cooling circuits
In: Nineteenth international conference on environmental degradation of materials in nuclear power systems - water reactors. La Grange Park: American Nuclear Society (ANS); 2019:1059-1068.
DORA PSI
Mora DF, Mukin R, Costa Garrido O, Niffenegger M
Fracture mechanics analysis of a PWR under PTS using XFEM and input from TRACE
In: Materials and fabrication: advanced and additive manufacturing and material technologies. Vol. 6A. PVP - American Society of Mechanical Engineers. Pressure vessels and piping division. sine loco: American Society of Mechanical Engineers (ASME); 2019:PVP2019-94019 (7 pp.). https://doi.org/10.1115/PVP2019-94019
DORA PSI
Mora DF, Niffenegger M, Qian G, Jaros M, Niceno B
Modelling of reactor pressure vessel subjected to pressurized thermal shock using 3D-XFEM
Nuclear Engineering and Design. 2019; 353: 110237 (13 pp.). https://doi.org/10.1016/j.nucengdes.2019.110237
DORA PSI
Mora Mendez DF, Olaniran SO, Rüggeberg M, Burgert I, Herrmann HJ, Wittel FK
Mechanical behavior of chemically modified Norway spruce: a generic hierarchical model for wood modifications
Wood Science and Technology. 2019; 53(2): 447-467. https://doi.org/10.1007/s00226-019-01082-3
DORA PSI
Mouginot R, Sarikka T, Ehrnstén U, Hänninen H
Nanoindentation study of short-range ordering
Materials Research Express. 2019; 6(4): 045052 (7 pp.). https://doi.org/10.1088/2053-1591/aafeaf
DORA PSI
Mukin R, Clifford I, Costa Garrido O, Mora DF, Niffenegger M, Niceno B, et al.
Screening analysis for pressurized thermal shock (PTS) transient scenarios
In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park, USA: American Nuclear Society (ANS); 2019:2536-2549.
DORA PSI
Niffenegger M, Garrido OC, Mora DF, Qian G, Mukin R, Sharabi M, et al.
Uncertainties in pressurized thermal shock analyses
In: Design and analysis: 4th international symposium on coke drum life cycle management. Vol. 3. PVP - American Society of Mechanical Engineers. Pressure vessels and piping division. sine loco: American Society of Mechanical Engineers (ASME); 2019:PVP2019-94076 (10 pp.). https://doi.org/10.1115/PVP2019-94076
DORA PSI
Olaniran SO, Michen B, Mora Mendez DF, Wittel FK, Bachtiar EV, Burgert I, et al.
Mechanical behaviour of chemically modified Norway spruce (Picea abies L. Karst.): experimental mechanical studies on spruce wood after methacrylation and in situ polymerization of styrene
Wood Science and Technology. 2019; 53(2): 425-445. https://doi.org/10.1007/s00226-019-01080-5
DORA PSI
Que Z, Seifert HP, Spätig P, Holzer J, Zhang A, Rao GS, et al.
Degradation effects of hydrogen and high-temperature water environments on the fracture resistance of low-alloy RPV steels
In: Nineteenth international conference on environmental degradation of materials in nuclear power systems - water reactors. La Grange Park: American Nuclear Society (ANS); 2019:934-948.
DORA PSI
Que Z, Seifert HP, Spätig P, Zhang A, Holzer J, Rao GS, et al.
Effect of dynamic strain ageing on environmental degradation of fracture resistance of low-alloy RPV steels in high-temperature water environments
Corrosion Science. 2019; 152: 172-189. https://doi.org/10.1016/j.corsci.2019.03.013
DORA PSI
Que Z, Seifert HP, Spätig P, Rao GS, Ritter S
Effect of high-temperature water environment on the fracture behaviour of low-alloy RPV steels
In: Jackson JH, Paraventi D, Wright M, eds. Proceedings of the 18th international conference on environmental degradation of materials in nuclear power systems - water reactors. Minerals, metals & materials series. Cham: Springer; 2019:1077-1099. https://doi.org/10.1007/978-3-319-67244-1_68
DORA PSI
Que Z, Seifert HP, Spätig P, Holzer J, Zhang A, Rao GS, et al.
Environmental degradation of fracture resistance in high-temperature water environments of low-alloy reactor pressure vessel steels with high sulphur or phosphorus contents
Corrosion Science. 2019; 154: 191-207. https://doi.org/10.1016/j.corsci.2019.04.011
DORA PSI
Ramanantoanina H, Studniarek M, Daffé N, Dreiser J
Non-empirical calculation of X-ray magnetic circular dichroism in lanthanide compounds
Chemical Communications. 2019; 55(20): 2988-2991. https://doi.org/10.1039/C8CC09321K
DORA PSI
Ramanantoanina H, Kuri G, Martin M, Bertsch J
Study of electronic structure in the L-edge spectroscopy of actinide materials: UO₂ as an example
Physical Chemistry Chemical Physics. 2019; 21(15): 7789-7801. https://doi.org/10.1039/c9cp01021a
DORA PSI
Ritter S, Grundler PV, Rowthu S
Assessment of the SCC mitigation capabilities of the NobleChem^TM technology in simulated BWR environment
Presented at: ICG-EAC Annual Meeting 2019; May 12-17, 2019; Tainan, Taiwan.
DORA PSI
Roters F, Diehl M, Shanthraj P, Eisenlohr P, Reuber C, Wong SL, et al.
DAMASK – the Düsseldorf Advanced Material Simulation Kit for modeling multi-physics crystal plasticity, thermal, and damage phenomena from the single crystal up to the component scale
Computational Materials Science. 2019; 158: 420-478. https://doi.org/10.1016/j.commatsci.2018.04.030
DORA PSI
Rowthu S, Yeh Y-W, Grundler PV, Holmes R, Ritter S
Assessment of the Pt nanoparticle distribution on oxidized stainless steel surfaces by electrochemical techniques
Presented at: EUROCORR 2019; September 9-13, 2019; Seville, Spain.
DORA PSI
Rowthu S, Hoffmann P
Versatile micro- and nanotexturing techniques for antibacterial applications
In: Dinca V, Petruta Suchea M, eds. Functional nanostructured interfaces for environmental and biomedical applications. Micro & nano technologies. Amsterdam: Elsevier; 2019:27-62. https://doi.org/10.1016/B978-0-12-814401-5.00003-7
DORA PSI
Shama A, Pouchon MA, Clifford I
Simulation of the microfluidic mixing and the droplet generation for 3D printing of nuclear fuels
Additive Manufacturing. 2019; 26: 1-14. https://doi.org/10.1016/j.addma.2018.12.011
DORA PSI
Spätig P, Chen J-C, Odette GR
Ferritic and tempered martensitic steels
In: Odette GR, Zinkle SJ, eds. Structural alloys for nuclear energy applications. Cambridge: Elsevier; 2019:485-527. https://doi.org/10.1016/B978-0-12-397046-6.00011-3
DORA PSI
Treichel A, Ritter S, Seifert H-P, Virtanen S
Effect of temperature and surface treatment on SCC initiation in Alloy 182 weld metal under BWR conditions
Presented at: ICG-EAC annual meeting 2019; May 12-17, 2019; Tainan, Taiwan.
DORA PSI
Treichel A, Ritter S, Seifert H-P, Virtanen S
Effect of temperature and surface treatment on SCC initiation in alloy 182 weld metal under BWR conditions
Presented at: EUROCORR 2019; September 9-13, 2019; Seville, Spain.
DORA PSI
Wu W, Schaeublin R
TEM diffraction contrast images simulation of dislocations
Journal of Microscopy. 2019; 275(1): 11-23. https://doi.org/10.1111/jmi.12797
DORA PSI
Abolhassani S, Proff C, Veleva L, Karlsen TM, Bennett P, Oberländer B, et al.
Transmission electron microscopy examinations of metal-oxide interface of zirconium-based alloys irradiated in Halden reactor-IFA-638
In: Comstock RJ, Motta AT, eds. Zirconium in the nuclear industry: 18th international symposium. Vol. STP1597. ASTM special technical publication. West Conshohocken, PA: ASTM International; 2018:614-644. https://doi.org/10.1520/STP159720160039
DORA PSI
Bai J
Effect of hydrogen on the stress corrosion cracking behaviour in Alloy 182 weld metal under boiling water reactor hydrogen water chemistry conditions
Villigen PSI, Switzerland: Paul Scherrer Institut; 2018. PSI Bericht: 18-01.
DORA PSI
Bai J, Bosch R-W, Ritter S, Schneider CW, Seifert H-P, Virtanen S
Electrochemical and spectroscopic characterization of oxide films formed on Alloy 182 in simulated boiling water reactor environment: effect of dissolved hydrogen
Corrosion Science. 2018; 133: 204-216. https://doi.org/10.1016/j.corsci.2018.01.024
DORA PSI
Bai J, Ritter S, Seifert H-P, Virtanen S
Stress corrosion cracking initiation and short crack growth behaviour in Alloy 182 weld metal under simulated boiling water reactor hydrogen water chemistry conditions
Corrosion Science. 2018; 131: 208-222. https://doi.org/10.1016/j.corsci.2017.11.021
DORA PSI
Bai J, Ritter S, Seifert H-P, Vankeerberghen M, Bosch R-W
The use of tapered specimens to evaluate the SCC initiation susceptibility in alloy 182 in BWR and PWR environments
In: Jackson JH, Paraventi D, Wright M, eds. Proceedings of the 18th international conference on environmental degradation of materials in nuclear power systems – water reactors. The minerals, metals & materials series. Cham: Springer; 2018:1929-1948. https://doi.org/10.1007/978-3-030-04639-2_131
DORA PSI
Baris A, Abolhassani S, Grabherr R, Restani R, Schäublin R, Chiu YL, et al.
Causes of increased corrosion and hydrogen uptake of zircaloy-2 cladding at high burnups – a comparative study of the chemical composition of a 3 cycle and a 9 cycle cladding
In: Topfuel 2018. Part 5. Brussels: European Nuclear Society; 2018:A0172 (13 pp.).
DORA PSI
Baris A, Restani R, Grabherr R, Chiu Y-L, Evans HE, Ammon K, et al.
Chemical and microstructural characterization of a 9 cycle Zircaloy-2 cladding using EPMA and FIB tomography
Journal of Nuclear Materials. 2018; 504: 144-160. https://doi.org/10.1016/j.jnucmat.2018.01.065
DORA PSI
Baris A, Abolhassani S, Chiu YL, Evans HE
Observation of crack microstructure in oxides and its correlation to oxidation and hydrogen-uptake by 3D FIB Tomography – case of Zr-ZrO₂ in reactor
Materials at High Temperatures. 2018; 35(1-3): 14-21. https://doi.org/10.1080/09603409.2017.1392412
DORA PSI
Cao Y, Qian G, He Y, Niffenegger M, Chao YJ
Constraint assessment for specimens tested under uniaxial and biaxial loading conditions
Journal of Pressure Vessel Technology. 2018; 140(3): 031401 (7 pp.). https://doi.org/10.1115/1.4039346
DORA PSI
Chen M, Yu W, Qian G, Shi J, Cao Y, Yu Y
Crack initiation, arrest and tearing assessments of a RPV subjected to PTS events
Annals of Nuclear Energy. 2018; 116: 143-151. https://doi.org/10.1016/j.anucene.2018.01.032
DORA PSI
Chen J, Duval F, Jung P, Schäublin R, Gao N, Barthe MF
Dislocation loops in ultra-high purity Fe(Cr) alloys after 7.2 MeV proton irradiation
Journal of Nuclear Materials. 2018; 503: 81-90. https://doi.org/10.1016/j.jnucmat.2018.02.042
DORA PSI
Chen W, Spätig P, Seifert H-P
Fatigue behavior of 316L austenitic stainless steel in air and LWR environment with and without mean stress
In: Henaff G, ed. 12th International Fatigue Congress (FATIGUE 2018). Vol. 165. MATEC web of conferences. sine loco: EDP Sciences; 2018:03012 (8 pp.). https://doi.org/10.1051/matecconf/201816503012
DORA PSI
Dai Y, Krsjak V, Kuksenko V, Schäublin R
Microstructural changes of ferritic/martensitic steels after irradiation in spallation target environments
Journal of Nuclear Materials. 2018; 511: 508-522. https://doi.org/10.1016/j.jnucmat.2018.09.028
DORA PSI
Degueldre C, Fahy J, Kolosov O, Wilbraham RJ, Döbeli M, Renevier N, et al.
Mechanical properties of advanced gas-cooled reactor stainless steel cladding after irradiation
Journal of Materials Engineering and Performance. 2018; 27(5): 2081-2088. https://doi.org/10.1007/s11665-018-3323-9
DORA PSI
Du Y, Han W, Cui L, Wan F
Electron-irradiation-induced Cr segregation in Fe-Cr model alloy pre-implanted with hydrogen ions
Materials Characterization. 2018; 139: 364-372. https://doi.org/10.1016/j.matchar.2018.03.019
DORA PSI
Fütterer MA, Li F, Gougar H, Edwards L, Pouchon MA, Kim M, et al.
Advances in the GIF very high temperature reactor system
In: 2018 GIF symposium proceedings. sine loco: Generation IV International Forum; 2018:9-22.
DORA PSI
Gong W, Trtik P, Valance S, Bertsch J
Hydrogen diffusion under stress in Zircaloy: high-resolution neutron radiography and finite element modeling
Journal of Nuclear Materials. 2018; 508: 459-464. https://doi.org/10.1016/j.jnucmat.2018.05.079
DORA PSI
Grilli N, Janssens KGF, Nellessen J, Sandlöbes S, Raabe D
Multiple slip dislocation patterning in a dislocation-based crystal plasticity finite element method
International Journal of Plasticity. 2018; 100: 104-121. https://doi.org/10.1016/j.ijplas.2017.09.015
DORA PSI
Grosse M, Santisteban JR, Bertsch J, Schillinger B, Kaestner A, Daymond MR, et al.
Neutronenradiographie- und -tomographieuntersuchungen der Wasserstoffdiffusion und -verteilung in Zirkonium. Investigations of the hydrogen diffusion and distribution in Zirconium by means of neutron imaging
Kerntechnik. 2018; 83(6): 495-501. https://doi.org/10.3139/124.110946
DORA PSI
Grundler PV, Rowthu S, Ritter S
Influence of fluid flow on platinum nanoparticles transport and deposition under simulated boiling water reactor conditions
Presented at: Nuclear plant chemistry conference (NPC 2018); September 9-14, 2018; San Francisco, CA, USA.
DORA PSI
Habainy J, Lövberg A, Iyengar S, Lee Y, Dai Y
Fatigue properties of tungsten from two different processing routes
Journal of Nuclear Materials. 2018; 506: 83-91. https://doi.org/10.1016/j.jnucmat.2017.10.061
DORA PSI
Habainy J, Iyengar S, Surreddi KB, Lee Y, Dai Y
Formation of oxide layers on tungsten at low oxygen partial pressures
Journal of Nuclear Materials. 2018; 506: 26-34. https://doi.org/10.1016/j.jnucmat.2017.12.018
DORA PSI
Habainy J, Dai Y, Lee Y, Iyengar S
Thermal diffusivity of tungsten irradiated with protons up to 5.8 dpa
Journal of Nuclear Materials. 2018; 509: 152-157. https://doi.org/10.1016/j.jnucmat.2018.06.041
DORA PSI
Horvath B, Dai Y, Lee Y
Annealing effect on the microstructure of tungsten irradiated in SINQ target
Journal of Nuclear Materials. 2018; 506: 19-25. https://doi.org/10.1016/j.jnucmat.2017.12.020
DORA PSI
Huet F, Ritter S
Electrochemical noise measurements with dummy cells: evaluation of a round-robin test series
Corrosion. 2018; 74(12): 1457-1465. https://doi.org/10.5006/3007
DORA PSI
Huet F, Ritter S
Electrochemical noise measurements with dummy cells: evaluation of a round-robin test series
In: Corrosion conference & expo 2018. Houston, Texas: NACE International; 2018:11040 (12 pp.).
DORA PSI
Janssens KGF
Proportionally and non-proportionally perturbed fatigue of stainless steel
International Journal of Fatigue. 2018; 110: 42-48. https://doi.org/10.1016/j.ijfatigue.2017.12.013
DORA PSI
Jiang W, Gu L, Zhou Q, Zhu Q-F, Chen L, Liu X-Q, et al.
Measurement of tungsten reactivity worth on VENUS-II light water reactor and validation of evaluated nuclear data
Progress in Nuclear Energy. 2018; 108: 81-88. https://doi.org/10.1016/j.pnucene.2018.05.002
DORA PSI
Knitel S, Spätig P, Yamamoto T, Seifert HP, Dai Y, Odette GR
Evolution of the tensile properties of the tempered martensitic steel Eurofer97 after spallation irradiation at SINQ
Nuclear Materials and Energy. 2018; 17: 69-77. https://doi.org/10.1016/j.nme.2018.09.002
DORA PSI
Krsjak V, Kuriplach J, Vieh C, Peng L, Dai Y
On the empirical determination of positron trapping coefficient at nano-scale helium bubbles in steels irradiated in spallation target
Journal of Nuclear Materials. 2018; 504: 277-280. https://doi.org/10.1016/j.jnucmat.2018.03.045
DORA PSI
Krsjak V, Degmova J, Lauko R, Snopek J, Saro M, Sedlackova K, et al.
Positron annihilation spectroscopy studies of irradiated Fe-based alloys using different radioisotope sources
Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms. 2018; 434: 73-80. https://doi.org/10.1016/j.nimb.2018.08.031
DORA PSI
Kuri G, Ramanantoanina H, Bertsch J, Martin M, Panas I
Chemical state and atomic scale environment of nickel in the corrosion layer of irradiated Zircaloy-2 at a burn-up around 45 MWd/kg
Corrosion Science. 2018; 143: 200-211. https://doi.org/10.1016/j.corsci.2018.08.032
DORA PSI
Kuri G, Martin M, Bertsch J
Residual stress/strain analysis in UO₂spent fuel by synchrotron micro-beam X-ray diffraction
In: Topfuel 2018. Brussels: European Nuclear Society; 2018:(5 pp.).
DORA PSI
Mora Méndez DF, Niffenegger M, Qian G, Jaros M, Niceno B
3D FEM modeling of crack initiation in a reactor pressure vessel during a PTS event (LBLOCA)
In: ASME 2018 pressure vessels and piping conference. Proceedings papers. Materials and fabrication. Vol. 6A. PVP - American Society of Mechanical Engineers. Pressure vessels and piping division. sine loco: American Society of Mechanical Engineers (ASME); 2018:PVP2018-85024 (8 pp.). https://doi.org/10.1115/PVP2018-85024
DORA PSI
Mukin R, Clifford I, Ferroukhi H, Niffenegger M
Pressurized Thermal Shock (PTS) transient scenarios analysis with TRACE
In: Proceedings of the 26th international conference on nuclear engineering (ICONE26). Thermal hydraulics and safety analyses. New York: American Society of Mechanical Engineers (ASME); 2018:ICONE26-81749 (7 pp.). https://doi.org/10.1115/ICONE26-81749
DORA PSI
Park JY, Kim D, Lee H-G, Kim W-J, Pouchon M
Oxidation behaviors of SiC_f/SiC composites tested at high temperature in air by an ablation method
Journal of the Korean Ceramic Society. 2018; 55(5): 498-503. https://doi.org/10.4191/kcers.2018.55.5.03
DORA PSI
Qian G, Lei W-S, Niffenegger M
A new local approach model for cleavage fracture in ferritic steels and its validation
In: Henaff G, ed. 12th international fatigue congress (FATIGUE 2018). Vol. 165. MATEC web of conferences. sine loco: EDP Sciences; 2018:22035 (6 pp.). https://doi.org/10.1051/matecconf/201816522035
DORA PSI
Qian G, Cao Y, Niffenegger M, Chao YJ, Wu W
Comparison of constraint analyses with global and local approaches under uniaxial and biaxial loadings
European Journal of Mechanics: A/Solids. 2018; 69: 135-146. https://doi.org/10.1016/j.euromechsol.2017.12.006
DORA PSI
Qian G, Niffenegger M, Sharabi M, Lafferty N
Effect of non-uniform reactor cooling on fracture and constraint of a reactor pressure vessel
Fatigue and Fracture of Engineering Materials and Structures. 2018; 41(7): 1559-1575. https://doi.org/10.1111/ffe.12796
DORA PSI
Qian G, González-Albuixech VF, Niffenegger M
Effects of embedded cracks and residual stresses on the integrity of a reactor pressure vessel
Engineering Failure Analysis. 2018; 90: 451-462. https://doi.org/10.1016/j.engfailanal.2018.04.009
DORA PSI
Qian G, Lei W-S, Niffenegger M, González-Albuixech VF
On the temperature independence of statistical model parameters for cleavage fracture in ferritic steels
Philosophical Magazine. 2018; 98(11): 959-1004. https://doi.org/10.1080/14786435.2018.1425011
DORA PSI
Qian G, Lei W-S, Peng L, Yu Z, Niffenegger M
Statistical assessment of notch toughness against cleavage fracture of ferritic steels
Fatigue and Fracture of Engineering Materials and Structures. 2018; 41(5): 1120-1131. https://doi.org/10.1111/ffe.12756
DORA PSI