LNM Publication List (since 2018)

  • Chen J, Jacques S, Barthe M-F, Zhang C, Desgardin P
    In-beam creep of SiCf/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
  • 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. GIF Symposia. Paris: Nuclear Energy Agency (NEA); 2020.
    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
  • 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
  • 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. https://doi.org/10.1002/er.5474
    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 N6,7-edge X-ray absorption
    International Journal of Quantum Chemistry. 2020; 120(3): e26081 (8 pp.). https://doi.org/10.1002/qua.26081
    DORA PSI
  • 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
  • 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. https://doi.org/10.4028/www.scientific.net/KEM.827.294
    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
  • 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
  • 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
  • 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. 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. 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.
    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.
    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.
    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.
    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.
    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
    Presented at: EnvDeg 2019; August 18-22, 2019; Boston, MA, USA.
    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. 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. 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. 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. 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
    Presented at: EnvDeg 2019; August 18-22, 2019; Boston, MA, USA.
    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. 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.
    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. 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
    Presented at: EnvDeg 2019; August 18-22, 2019; Boston, MA, USA.
    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. 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 NobleChemTM 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. 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. 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. ASTM Special Technical Publication. Vol. STP 1597. ASTM International; 2018. https://doi.org/10.1520/STP159720160039
    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. 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.
    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. 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
  • 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
  • Gong W, Zubler R, Trtik P, Bertsch J
    Zirconium liner cladding materials: hydrogen diffusion to the liner under cooling/stress gradient
    Presented at: 2018 MRS Spring Meeting; April 2-6; Phoenix, Arizona, USA.
    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
  • 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
  • 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. 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. https://doi.org/10.1115/ICONE26-81749
    DORA PSI
  • Park JY, Kim D, Lee H-G, Kim W-J, Pouchon M
    Oxidation behaviors of SiCf/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. 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
  • Que Z, Seifert HP, Spaetig P, Zhang A, Ritter S
    Environmental Reduction Effect of High Temperature Water and Hydrogen on Fracture Resistance of Low Alloy Reactor Pressure Vessel Steels
    Presented at: Fontevraud 9; September 17-20, 2018; Avignon, France.
    DORA PSI
  • Que Z, Seifert HP, Spätig P, Ritter S
    Environmental Reduction Effect of High-Temperature Water and Hydrogen on Fracture Resistance of Low-Alloy RPV Steels
    In: Annual Meeting of the Int. Cooperative Group on Environmentally-Assisted Cracking of Water Reactor Materials, ICG-EAC, N.P.O. ; 2018.
    DORA PSI
  • Que Z, Seifert HP, Spätig P, Zhang A, Rao GS, Ritter S
    Environmental degradation effect of high-temperature water and hydrogen on the fracture behavior of low-alloy reactor pressure vessel steels
    In: Sedmak A, Radaković Z, Rakin M, eds. ECF22 - loading and environmental effects on structural integrity. Vol. 13. Procedia structural integrity. Elsevier; 2018. https://doi.org/10.1016/j.prostr.2018.12.174
    DORA PSI
  • Ramanantoanina H
    A DFT-based theoretical model for the calculation of spectral profiles of lanthanide M4,5-edge x-ray absorption
    Journal of Chemical Physics. 2018; 149(5): 054104 (12 pp.). https://doi.org/10.1063/1.5043052
    DORA PSI
  • Ranganath S, Carter RG, Pathania R, Ritter S, Seifert H-P
    Evaluation of stress corrosion crack growth in low alloy steel vessel materials in the BWR environment
    In: American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP. Vol. 6B-2018. American Society of Mechanical Engineers (ASME); 2018.
    DORA PSI
  • Ritter S
    Accelerated Testing of Stress Corrosion Cracking Initiation in High-Temperature Water – Results from the MICRIN Collaborative Project
    Presented at: EUROCORR 2018, EFC; September 9-13, 2018; Krakow, Poland.
    DORA PSI
  • Ritter S, Grundler PV, Schaeublin R, Veleva L
    Characterization of Pt nanoparticle decoration of oxide layers on stainless steel
    Surfaces and Interfaces. 2018; 11: 22-27. https://doi.org/10.1016/j.surfin.2018.02.004
    DORA PSI
  • Ritter S
    Electrochemical noise measurements with dummy cells: evaluation of a round-robin test series
    Presented at: NACE international corrosion conference; April 15-19, 2018; Phoenix, AZ, USA.
    DORA PSI
  • Ritter S, Grundler PV
    Enhanced catalysis by platinum nano-dots in BWR IGSCC mitigation and dose reduction
    Presented at: Nuclear plant chemistry conference (NPC 2018); September 9-14, 2018; San Francisco, CA, USA.
    DORA PSI
  • Ritter S, Seifert HP
    Evaluation of Stress Corrosion Crack Growth in Low Alloy Steel Vessel Materials in the Boiling Water Reactor (BWR) Environment
    Presented at: Fontevraud 9; September 17-20, 2018; Avignon, France.
    DORA PSI
  • Ritter S
    Meactos - Mitigation of EAC through the Optimisation of Surface Condition
    Presented at: Fontevraud 9; September 17-20, 2018; Avignon, France.
    DORA PSI
  • Rowthu S, Ritter S
    Non-destructive ways to characterize local and spatial distributions of platinum nanoparticles on boiling water reactor materials
    Presented at: Nuclear plant chemistry conference (NPC 2018); September 9-14, 2018; San Francisco, CA, USA.
    DORA PSI
  • Rowthu S, Grundler PV, Ritter S, Helmerson B, Oliver L
    Oxidation and hydrogen pickup properties of zircaloy cladding upon deposition of platinum nanoparticles in boiling water reactor environment
    In: Topfuel 2018. Part 5. Brussels: European Nuclear Society; 2018.
    DORA PSI
  • Rowthu S, Hoffmann P
    Perfluoropolyether-impregnated mesoporous alumina composites overcome the dewetting-tribological properties trade-off
    ACS Applied Materials and Interfaces. 2018; 10(12): 10560-10570. https://doi.org/10.1021/acsami.8b00061
    DORA PSI
  • Seifert H-P, Ritter S, Spätig P, Bai J, Chen W, Rao SG, et al.
    Safe long-term operation in the context of environmental effects on fracture, fatigue and environmentally-assisted cracking. Final report of the SAFE-II project
    Villigen PSI, Switzerland: Paul Scherrer Institut; 2018. PSI Bericht: 18-03.
    DORA PSI
  • Seifert HP, Ritter S
    Updated Evaluation of Stress Corrosion Crack Growth in Low-Alloy Steel Vessel Materials in BWR Environment
    In: Annual Meeting of the Int. Cooperative Group on Environmentally-Assisted Cracking of Water Reactor Materials, ICG-EAC, N.P.O. ; 2018.
    DORA PSI
  • Spätig P, Heczko M, Kruml T, Seifert H-P
    Influence of mean stress and light water reactor environment on fatigue life and dislocation microstructures of 316L austenitic steel
    Journal of Nuclear Materials. 2018; 509: 15-28. https://doi.org/10.1016/j.jnucmat.2018.05.064
    DORA PSI
  • Sudhakar Rao G, Singh SR, Krsjak V, Singh V
    Cyclic softening in annealed Zircaloy-2: role of edge dislocation dipoles and vacancies
    Journal of Nuclear Materials. 2018; 502: 154-160. https://doi.org/10.1016/j.jnucmat.2018.02.011
    DORA PSI
  • Suszka AK, Gliga S, Warnicke P, Wintz S, Saha S, Charipar KM, et al.
    Observation of the out-of-plane magnetization in a mesoscopic ferromagnetic structure superjacent to a superconductor
    Applied Physics Letters. 2018; 113(16): 162601 (4 pp.). https://doi.org/10.1063/1.5051653
    DORA PSI
  • Tian W, Pouchon MA, Guo H, Chen D, Yin X, Qin Z
    Fabrication of CeO2 ceramic spheres as a surrogate of nuclear fuel by an improved microwave-assisted rapid internal gelation process
    Ceramics International. 2018; 44(6): 6739-6746. https://doi.org/10.1016/j.ceramint.2018.01.090
    DORA PSI
  • Tian W, Guo H, Chen D, Pouchon MA, Horwege A, Yin X, et al.
    Preparation of UC ceramic nuclear fuel microspheres by combination of an improved microwave-assisted rapid internal gelation with carbothermic reduction process
    Ceramics International. 2018; 44(15): 17945-17952. https://doi.org/10.1016/j.ceramint.2018.06.270
    DORA PSI
  • Tiete R, Trewin R, Blasset S, Pistora V, Posta M, Niffenegger M, et al.
    Presentation of DEFI-PROSAFE project: probabilistic methodology to assess margin in deterministic RPV integrity assessment and proposed benchmark
    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. https://doi.org/10.1115/PVP2018-84615
    DORA PSI
  • Vankeerberghen M, Doremus L, Spätig P, Bruchhausen M, Le-Roux J-C, Twite M, et al.
    Ensuring data quality for environmental fatigue – INCEFA-Plus testing procedure and data evaluation
    In: American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP. Vol. 1A-2018. American Society of Mechanical Engineers (ASME); 2018. https://doi.org/10.1115/PVP201884081
    DORA PSI
  • Villacampa I, Chen JC, Spätig P, Seifert HP, Duval F
    Helium bubble evolution and hardening in 316L by post-implantation annealing
    Journal of Nuclear Materials. 2018; 500: 389-402. https://doi.org/10.1016/j.jnucmat.2018.01.017
    DORA PSI
  • Wang K, Dai Y, Spätig P
    Deformation twinning in irradiated ferritic/martensitic steels
    Journal of Nuclear Materials. 2018; 501: 336-346. https://doi.org/10.1016/j.jnucmat.2018.01.057
    DORA PSI
  • Wu W, Qi D, Liao H, Qian G, Geng L, Niu Y, et al.
    Deformation mechanism of innovative 3D chiral metamaterials
    Scientific Reports. 2018; 8(1): 12575 (10 pp.). https://doi.org/10.1038/s41598-018-30737-7
    DORA PSI
  • Wu W, Song X, Liang J, Xia R, Qian G, Fang D
    Mechanical properties of anti-tetrachiral auxetic stents
    Composite Structures. 2018; 185: 381-392. https://doi.org/10.1016/j.compstruct.2017.11.048
    DORA PSI
  • Wu W, Schäublin R
    Simulations of weak-beam diffraction contrast images of dislocation loops by the many-beam Schaeublin–Stadelmann equations
    Journal of Materials Science. 2018; 53(22): 15694-15702. https://doi.org/10.1007/s10853-018-2735-0
    DORA PSI
  • Wu W, Schäublin R
    The elasticity of the ½ a0 <111> and a0 <100> dislocation loop in α-Fe thin foil
    Journal of Nuclear Materials. 2018; 510: 61-69. https://doi.org/10.1016/j.jnucmat.2018.07.057
    DORA PSI
  • Xia R, Song X, Sun L, Wu W, Li C, Cheng T, et al.
    Mechanical properties of 3D isotropic anti-tetrachiral metastructure
    Physica Status Solidi B: Basic Research. 2018; 255(4): 1700343 (9 pp.). https://doi.org/10.1002/pssb.201700343
    DORA PSI
  • Xu Q, Popov E, Troev T, Zhang J, Dai Y
    Positron lifetime calculation of vacancy clusters in tantalum containing hydrogen and helium
    Journal of Nuclear Materials. 2018; 506: 71-75. https://doi.org/10.1016/j.jnucmat.2017.06.011
    DORA PSI

Contact

Research Division
Nuclear Energy and Safety
Paul Scherrer Institute
OHSA/E72
5232 Villigen PSI
Switzerland

Division Head
Prof. Dr. Andreas Pautz
Telephone: +41 56 310 3497
E-mail: Andreas.Pautz@psi.ch

Secretary
Laura Wenger
Telephone: +41 56 310 2740
E-mail: Laura.Wenger@psi.ch
Ramona Dreier
Telephone: +41 56 310 2741
E-mail: Ramona.Dreier@psi.ch

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