LNM Publication List

  • Chen M, Simonelli M, Van Petegem S, Tse YY, Chang CST, Makowska MG, et al.
    A quantitative study of thermal cycling along the build direction of Ti-6Al-4V produced by laser powder bed fusion
    Materials and Design. 2023; 225: 111458 (11 pp.). https://doi.org/10.1016/j.matdes.2022.111458
    DORA PSI
  • Colldeweih AW, Makowska MG, Tabai O, Sanchez DF, Bertsch J
    Zirconium hydride phase mapping in Zircaloy-2 cladding after delayed hydride cracking
    Materialia. 2023; 27: 101689 (10 pp.). https://doi.org/10.1016/j.mtla.2023.101689
    DORA PSI
  • 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
  • Fallon CM, Bower WR, Powell BA, Livens FR, Lyon IC, McNulty AE, et al.
    Vadose-zone alteration of metaschoepite and ceramic UO2 in Savannah River Site field lysimeters
    Science of the Total Environment. 2023; 862: 160862 (12 pp.). https://doi.org/10.1016/j.scitotenv.2022.160862
    DORA PSI
  • Saito S, Suzuki K, Obata H, Dai Y
    Mechanical properties of pure tungsten and tantalum irradiated by protons and neutrons at the Swiss spallation-neutron source
    Nuclear Materials and Energy. 2023; 34: 101338 (9 pp.). https://doi.org/10.1016/j.nme.2022.101338
    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
  • Baykal BA, Spätig P
    Analysis of crack front loading to improve reliability of fracture toughness calculations based on miniaturized CT specimens
    In: Moreira P, Galrao dos Reis LF, eds. 23 European conference on fracture. Vol. 42. Procedia structural integrity. sine loco: Elsevier; 2022:1350-1360. https://doi.org/10.1016/j.prostr.2022.12.172
    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
  • Lingyun G, Niffenegger M
    An evaluation of probabilistic integrity assessment codes
    In: Proceedings of ASME 2022 pressure vessels and piping conference (PVP2022). Volume 2. Computer technology and bolted joints; design and analysis. Pressure vessels and piping conference. sine loco: American Society of Mechanical Engineers ASME; 2022:PVP2022-84277 (7 pp.). https://doi.org/10.1115/PVP2022-84277
    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
  • Mora M. DF, Niffenegger M, Mao G
    Thick-walled cylindrical specimens under PTS loading: crack propagation analysis with XFEM-IGA
    In: Proceedings of ASME 2022 pressure vessels and piping conference (PVP2022). Volume 2. Computer technology and bolted joints; design and analysis. Pressure vessels and piping conference. sine loco: American Society of Mechanical Engineers ASME; 2022:PVP2022-83771 (9 pp.). https://doi.org/10.1115/PVP2022-83771
    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 TiO2-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
  • Zarazovskii M, Pistora V, Lauerova D, Obermeier F, Mora D, Dubyk Y, et al.
    State-of-the-art of WPS in RPV PTS analysis
    In: Proceedings of ASME 2022 pressure vessels and piping conference (PVP2022). Volume 1. Codes and standards. Pressure vessels and piping conference. sine loco: American Society of Mechanical Engineers ASME; 2022:PVP2022-83699 (11 pp.). https://doi.org/10.1115/PVP2022-83699
    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; 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 M5Framatome 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
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    In-beam creep of SiCf/SiC minicomposites under uniaxial tensile loading
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    The effects of helium in irradiated structural alloys
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    Presented at: NuMat 2020; October 26-29, 2020; Ghent, Belgium.
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    Fifty years of nuclear corrosion in Europe: evolutions and contributions of the working party on nuclear corrosion
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    The causes of increased hydrogen uptake of zirconium based fuel claddings at high burnup
    2020.
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    Universal cycle counting for non-proportional and random fatigue loading
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    FreeCAD based Monte Carlo modeling approach for fusion reactor facilities
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  • 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
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    INCEFA-PLUS project: the impact of using fatigue data generated from multiple specimen geometries on the outcome of a regression analysis
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  • 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
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  • 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
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  • Mora DF, Niffenegger M, Mukin R
    Crack propagation modeling in a PWR under PTS Using XFEM
    In: Materials and fabrication. Vol. 6. Pressure vessels and piping conference. New York, NY, USA: ASME; 2020:V006T06A001. https://doi.org/10.1115/PVP2020-21026
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  • 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
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  • 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
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  • 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
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  • 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
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  • 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
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  • Ramanantoanina H, Merzoud L, Muya JT, Chermette H, Daul C
    Electronic structure and photoluminescence properties of Eu(ƞ9-C9H9)2
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    Theoretical insight into the magnetic circular dichroism of uranium N6,7-edge X-ray absorption
    International Journal of Quantum Chemistry. 2020; 120(3): e26081 (8 pp.). https://doi.org/10.1002/qua.26081
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  • 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
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    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
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    Experimental validation of tensile properties measured with thick samples taken from MEGAPIE target
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  • 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
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  • Seifert H-P, Ritter S
    Environmentally-assisted cracking of carbon and low-alloy steels in light water reactors
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  • 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
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    Mitigating environmentally-assisted cracking through optimisation of surface condition
    Presented at: EUROCORR 2020; September 7-11, 2020; online.
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  • 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
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    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
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    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.
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    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
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  • 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
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  • Baris A
    Increased hydrogen uptake of zirconium based claddings ata high burnup
    2019.
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  • 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.
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  • 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
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  • 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
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  • 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
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  • 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.
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  • 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.
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  • 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.
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  • 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.
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  • 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.
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  • 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.
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  • 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
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  • 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.
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  • 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
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  • 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
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  • 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
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    Study of heavy ion beam induced damage in tungsten for high power target applications
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  • 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
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  • 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
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    Flash electropolishing of TEM lamellas of irradiated tungsten
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    A universal, damage-criterion-independent cycle counting method for multiaxial and variable amplitude fatigue
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    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
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  • 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
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  • 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
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    Insights into prospective fusion reactor coolong systems from fission reactor cooling circuits
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  • 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
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  • Mora DF, Niffenegger M, Qian G, Jaros M, Niceno B
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    In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park, USA: American Nuclear Society (ANS); 2019:2536-2549.
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    Study of electronic structure in the L-edge spectroscopy of actinide materials: UO2 as an example
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  • Ritter S, Grundler PV, Rowthu S
    Assessment of the SCC mitigation capabilities of the NobleChemTM technology in simulated BWR environment
    Presented at: ICG-EAC Annual Meeting 2019; May 12-17, 2019; Tainan, Taiwan.
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    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
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  • 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
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  • Rowthu S, Hoffmann P
    Versatile micro- and nanotexturing techniques for antibacterial applications
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  • Shama A, Pouchon MA, Clifford I
    Simulation of the microfluidic mixing and the droplet generation for 3D printing of nuclear fuels
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  • 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
    In: Corrosion conference & expo 2018. Houston, Texas: NACE International; 2018:11040 (12 pp.).
    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
  • 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 UO2 spent 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

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