LNM Publication List 2018 ‒ 2014

2018

  • Accelerated Testing of Stress Corrosion Cracking Initiation in High-Temperature Water ? Results from the MICRIN Collaborative Project Ritter S, Kilian R, Herbst M, Bosch RW, Burke G, Scenini F, Dinu A, Ehrnsten U, Hojna A, Novotny R, Martin O, Perosanz FJ, Zajec B
    EUROCORR 2018, EFC, September 9-13, Krakow, Poland , (2018).
  • Annealing effect on the microstructure of tungsten irradiated in SINQ target Horvath B, Dai Y, Lee Y
    JOURNAL OF NUCLEAR MATERIALS 506, 19 (2018).
    DOI: 10.1016/j.jnucmat.2017.12.020
  • 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 Baris A, Abolhassani S, Gabherr R, Restani R, Schaeublin R, Chiu YL, Evans HE, Ammon K, Limbaeck M
    Proceedings of TopFuel Reactor Fuel Performance conference, September 30 - October 4, Prague, Czech Republic A0172, (2018).
  • Characterization of Pt nanoparticle decoration of oxide layers on stainless steel Ritter S, Grundler Pascal V, Schaeublin R, Veleva L
    Surfaces and Interfaces 11, 22 (2018).
    DOI: 10.1016/j.surfin.2018.02.004
  • Chemical and microstructural characterization of a 9 cycle Zircaloy-2 cladding using EPMA and FIB tomography Baris A, Restani R, Grabherr R, Chiu YL, Evans HE, Ammon K, Limbäck M, Abolhassani S
    JOURNAL OF NUCLEAR MATERIALS 504, 144 (2018).
    DOI: 10.1016/j.jnucmat.2018.01.065
  • Chemical state and atomic scale environment of nickel in the corrosion layer of irradiated Zircaloy-2 at a burn-up around 45 MWd/kg Kuri G, Ramanantoanina H, Bertsch J, Martin M, Panas I
    CORROSION SCIENCE 143, 200 (2018).
    DOI: 10.1016/j.corsci.2018.08.032
  • Comparison of constraint analyses with global and local approaches under uniaxial and biaxial loadings Qian G, Cao Y, Niffenegger M, Chao Yuh J, Wu W
    European Journal of Mechanics - A/Solids 69, 135 (2018).
    DOI: 10.1016/j.euromechsol.2017.12.006
  • Deformation twinning in irradiated ferritic/martensitic steels Wang K, Dai Y, Spätig P
    JOURNAL OF NUCLEAR MATERIALS 501, 336 (2018).
    DOI: 10.1016/j.jnucmat.2018.01.057
  • Dislocation loops in ultra-high purity Fe(Cr) alloys after 7.2 MeV proton irradiation Chen J, Duval F, Jung P, Schäublin R, Gao N, Barthe MF
    JOURNAL OF NUCLEAR MATERIALS 503, 81 (2018).
    DOI: 10.1016/j.jnucmat.2018.02.042
  • Electrochemical Noise Measurements with Dummy Cells: Evaluation of a Round-Robin Test Series Huet F, Ritter S
    CORROSION 74, 1457 (2018).
    DOI: 10.5006/3007
  • Electrochemical Noise Measurements with Dummy Cells: Evaluation of a Round-Robin Test Series Huet F, Ritter S
    NACE Corrosion, NACE, April 15-19, Phoenix, AZ, USA CD-ROM, PaperNo. C2018-11040 (2018).
  • Electrochemical and spectroscopic characterization of oxide films formed on Alloy 182 in simulated boiling water reactor environment: Effect of dissolved hydrogen Bai J, Bosch R, Ritter S, Schneider Christof W, Seifert H, Virtanen S
    CORROSION SCIENCE 133, 204 (2018).
    DOI: 10.1016/j.corsci.2018.01.024
  • Enhanced Catalysis by Platinum Nano-Dots in BWR IGSCC Mitigation and Dose Reduction Hettiarachchi S, Weber C, Ritter S, Grundler PV
    Nuclear Plant Chemistry Conference (NPC), EPRI, September 9-14, San Francisco, CA, USA , (2018).
  • Ensuring Data Quality for Environmental Fatigue ? Incefa-Plus Testing Procedure and Data Evaluation Vankeerberghen M, Bruchhausen M, Cicero R, Doremus L, Le-Roux JC, Platts N, Spaetig P, Twite M, Mottershead K
    ASME 2018 Pressure Vessels and Piping Conference (PVP 2018), ASME, July 15-20, Prague, Czech Republic CD-ROM, PVP2018-84081 (2018).
  • Environmental Degradation Effect of High-Temperature Water and Hydrogen on the Fracture Behavior of Low-Alloy Reactor Pressure Vessel Steels Que Z, Seifert HP, Spätig P, Zhang A, Rao GS, Ritter S
    Procedia Structural Integrity 13, 926 (2018).
    DOI: 10.1016/j.prostr.2018.12.174
  • Environmental Reduction Effect of High Temperature Water and Hydrogen on Fracture Resistance of Low Alloy Reactor Pressure Vessel Steels Que Z, Seifert HP, Spaetig P, Zhang A, Ritter S, Rao GS
    Fontevraud 9, September 17-20, Avignon, France Paper No. 00032, (2018).
  • Environmental Reduction Effect of High-Temperature Water and Hydrogen on Fracture Resistance of Low-Alloy RPV Steels Que Z, Seifert HP, Spätig P, Ritter S, Rao GS, Zhang A
    Annual Meeting of the Int. Cooperative Group on Environmentally-Assisted Cracking of Water Reactor Materials, ICG-EAC, N.P.O., April 15-20, Knoxville, TN, USA CD-ROM, Paper No. LA04 (2018).
  • Evaluation of Stress Corrosion Crack Growth in Low Alloy Steel Vessel Materials in the BWR Environment Ranganath S, Carter R, Pathania R, Ritter S, Seifert HP
    ASME 2018 Pressure Vessels and Piping Conference (PVP 2018), ASME, July 15-20, Prague, Czech Republic CD-ROM, Paper PVP2018-84257 (2018).
  • Evaluation of Stress Corrosion Crack Growth in Low Alloy Steel Vessel Materials in the Boiling Water Reactor (BWR) Environment Ranganath S, Carter R, Pathania R, Ritter S, Seifert HP
    Fontevraud 9, September 17-20, Avignon, France Paper No. 000163, (2018).
  • Evolution of the tensile properties of the tempered martensitic steel Eurofer97 after spallation irradiation at SINQ Knitel S, Spätig P, Yamamoto T, Seifert HP, Dai Y, Odette GR
    Nuclear Materials and Energy 17, 69 (2018).
    DOI: 10.1016/j.nme.2018.09.002
  • Fabrication of CeO 2 ceramic spheres as a surrogate of nuclear fuel by an improved microwave-assisted rapid internal gelation process Tian W, Pouchon MA, Guo H, Chen D, Yin X, Qin Z
    CERAMICS INTERNATIONAL 44, 6739 (2018).
    DOI: 10.1016/j.ceramint.2018.01.090
  • Fatigue behavior of 316L austenitic stainless steel in air and LWR environment with and without mean stress Chen W, Spätig P, Seifert H
    MATEC Web of Conferences 165, 03012 (2018).
    DOI: 10.1051/matecconf/201816503012
  • Fatigue properties of tungsten from two different processing routes Habainy J, Lövberg A, Iyengar S, Lee Y, Dai Y
    JOURNAL OF NUCLEAR MATERIALS 506, 83 (2018).
    DOI: 10.1016/j.jnucmat.2017.10.061
  • Formation of oxide layers on tungsten at low oxygen partial pressures Habainy J, Iyengar S, Surreddi K, Lee Y, Dai Y
    JOURNAL OF NUCLEAR MATERIALS 506, 26 (2018).
    DOI: 10.1016/j.jnucmat.2017.12.018
  • H2 Permeation Behavior of Cr2AlC and Ti2AlC max Phase Coated Zircaloy-4 by Neutron Radiography Tang C, Grosse M, Trtik P, Steinbrück M, Stüber M, Seifert H
    Acta Polytechnica 58, 69 (2018).
    DOI: 10.14311/AP.2018.58.0069
  • Helium bubble evolution and hardening in 316L by post-implantation annealing Villacampa I, Chen JC, Spätig P, Seifert HP, Duval F
    JOURNAL OF NUCLEAR MATERIALS 500, 389 (2018).
    DOI: 10.1016/j.jnucmat.2018.01.017
  • Hydrogen diffusion under stress in Zircaloy: High-resolution neutron radiography and finite element modeling Gong W, Trtik P, Valance S, Bertsch J
    JOURNAL OF NUCLEAR MATERIALS 508, 459-464 (2018).
    DOI: 10.1016/j.jnucmat.2018.05.079
  • Influence of Fluid Flow on Platinum Nanoparticles Transport and Deposition under Simulated Boiling Water Reactor Conditions Grundler PV, Rowthu S, Ritter S
    Nuclear Plant Chemistry Conference (NPC), EPRI, September 9-14, San Francisco, CA, USA , (2018).
  • Influence of mean stress and light water reactor environment on fatigue life and dislocation microstructures of 316L austenitic steel Spätig P, Heczko M, Kruml T, Seifert HP
    JOURNAL OF NUCLEAR MATERIALS 509, 15 (2018).
    DOI: 10.1016/j.jnucmat.2018.05.064
  • Investigations of the hydrogen diffusion and distribution in Zirconium by means of Neutron Imaging Grosse M, Santisteban JR, Bertsch J, Schillinger B, Kaestner A, Daymond MR, Kardjilov N
    KERNTECHNIK 83, 495 (2018).
    DOI: 10.3139/124.110946
  • Meactos - Mitigation of EAC through the Optimisation of Surface Condition Lopez FJP, Ehrnsten U, Burke MG, Hojna A, Killian R, Dinu A, Burger E, Novotny R, Ritter S, Stoddart D, Vankeerberghen M, Zajec B, Chatterton M, Slugen V, Veron P, Sanchez L
    Fontevraud 9, September 17-20, Avignon, France , (2018).
  • Mechanical Properties of Advanced Gas-Cooled Reactor Stainless Steel Cladding After Irradiation Degueldre C, Fahy J, Kolosov O, Wilbraham Richard J, Döbeli M, Renevier N, Ball J, Ritter S
    JOURNAL OF MATERIALS ENGINEERING AND PERFORMANCE 27, 2081 (2018).
    DOI: 10.1007/s11665-018-3323-9
  • Multiple slip dislocation patterning in a dislocation-based crystal plasticity finite element method Grilli N, Janssens KGF, Nellessen J, Sandlöbes S, Raabe D
    INTERNATIONAL JOURNAL OF PLASTICITY 100, 104 (2018).
    DOI: 10.1016/j.ijplas.2017.09.015
  • Non-Destructive Ways to Characterize Local and Spatial Distributions of Platinum Nanoparticles on Boiling Water Reactor Materials Rowthu S, Grundler PV, Ritter S
    Nuclear Plant Chemistry Conference (NPC), EPRI, September 9-14, San Francisco, CA, USA , (2018).
  • OXIDATION AND HYDROGEN PICKUP PROPERTIES OF ZIRCALOY CLADDING UPON DEPOSITION OF PLATINUM NANOPARTICLES IN BOILING WATER REACTOR ENVIRONMENT Rowthu S, Grundler PV, Ritter S, Helmersson B, Oliver L
    Proceedings of TopFuel Reactor Fuel Performance conference, September 30 - October 4, Prague, Czech Republic Paper ID: A0138, (2018).
  • Observation of the out-of-plane magnetization in a mesoscopic ferromagnetic structure superjacent to a superconductor Suszka Anna K, Gliga S, Warnicke P, Wintz S, Saha S, Charipar Kristin M, Kim H, Wohlhüter P, Kirk E, Finizio S, Raabe J, Witt James DS, Heyderman Laura J, Bingham Nicholas S
    APPLIED PHYSICS LETTERS 113, 162601 (2018).
    DOI: 10.1063/1.5051653
  • On the temperature independence of statistical model parameters for cleavage fracture in ferritic steels Qian G, Lei W, Niffenegger M, González-Albuixech VF
    PHILOSOPHICAL MAGAZINE 98, 959 (2018).
    DOI: 10.1080/14786435.2018.1425011
  • Oxidation Behaviors of SiCf/SiC Composites Tested at High Temperature in Air by an Ablation Method Park J, Kim D, Lee H, Kim W, Pouchon M
    Journal of the Korean Ceramic Society 55, 498 (2018).
    DOI: 10.4191/kcers.2018.55.5.03
  • Positron annihilation spectroscopy studies of irradiated Fe-based alloys using different radioisotope sources Krsjak V, Degmova J, Lauko R, Snopek J, Saro M, Sedlackova K, Sojak S, Petriska M, Farkas G, Dai Y, Slugen V
    Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms 434, 73 (2018).
    DOI: 10.1016/j.nimb.2018.08.031
  • Positron lifetime calculation of vacancy clusters in tantalum containing hydrogen and helium Xu Q, Popov E, Troev T, Zhang J, Dai Y
    JOURNAL OF NUCLEAR MATERIALS 506, 71 (2018).
    DOI: 10.1016/j.jnucmat.2017.06.011
  • Preparation of UC ceramic nuclear fuel microspheres by combination of an improved microwave-assisted rapid internal gelation with carbothermic reduction process Tian W, Guo H, Chen D, Pouchon MA, Horwege A, Yin X, Huang Q, Wang J, Cao S, Chen D, Bai J, Tan C, Fan F, Wu X, Shen T, Qin Z
    CERAMICS INTERNATIONAL 44, 17945 (2018).
    DOI: 10.1016/j.ceramint.2018.06.270
  • Proportionally and non-proportionally perturbed fatigue of stainless steel Janssens KGF
    INTERNATIONAL JOURNAL OF FATIGUE 110, 42 (2018).
    DOI: 10.1016/j.ijfatigue.2017.12.013
  • Safe Long-Term Operation in the Context of Environmental Effects on Fracture, Fatigue and Environmentally-Assisted Cracking - Final Report of the Safe-II Project Seifert HP, Ritter S, Spaetig P, Bai J, Chen W, Rao GS, Que Z
    PSI Report, October, Paul Scherrer Institut, Villigen, Switzerland No. 18-03, (2018).
  • Size, Constraint and dk/da Effects on EAC Crack Growth in Low-Alloy RPV Steels Seifert HP, Ritter S
    Annual Meeting of the Int. Cooperative Group on Environmentally-Assisted Cracking of Water Reactor Materials, ICG-EAC, N.P.O., April 15-20, Knoxville, TN, USA CD-ROM, Paper No. LA03 (2018).
  • Stress corrosion cracking initiation and short crack growth behaviour in Alloy 182 weld metal under simulated boiling water reactor hydrogen water chemistry conditions Bai J, Ritter S, Seifert H, Virtanen S
    CORROSION SCIENCE 131, 208 (2018).
    DOI: 10.1016/j.corsci.2017.11.021
  • Thermal diffusivity of tungsten irradiated with protons up to 5.8 dpa Habainy J, Dai Y, Lee Y, Iyengar S
    JOURNAL OF NUCLEAR MATERIALS 509, 152 (2018).
    DOI: 10.1016/j.jnucmat.2018.06.041
  • Transmission Electron Microscopy Examinations of Metal-Oxide Interface of Zirconium-Based Alloys Irradiated in Halden Reactor-IFA-638 Abolhassani S, Proff C, Veleva L, Karlsen TM, Bennett P, Oberländer B, Espeland M, Jenssen H, Hallstadius L, Garde AM
    ASTM INTERNATIONAL CUSTOMER SERVICE STP1597, 1 (2018).
    DOI: 10.1520/STP159720160039
  • Unexpected field-induced dynamics in magnetostrictive microstructured elements under isotropic strain Finizio S, Wintz S, Gliga S, Kirk E, Suszka A, Wohlhüter P, Zeissler K, Raabe J
    Journal of Physics: Condensed Matter 30, 314001 (2018).
    DOI: 10.1088/1361-648X/aacddd
  • Updated Evaluation of Stress Corrosion Crack Growth in Low-Alloy Steel Vessel Materials in BWR Environment Carter R, Pathania R, Ranganath S, Seifert HP, Ritter S
    Annual Meeting of the Int. Cooperative Group on Environmentally-Assisted Cracking of Water Reactor Materials, ICG-EAC, N.P.O., April 15-20, Knoxville, TN, USA CD-ROM, Paper No. LA02 (2018).
  • Zirconium Liner Cladding Materials: Hydrogen Diffusion to the Liner under Cooling/Stress Gradient Duarte LI, Gong W, Zubler R, Trtik P, Bertsch J
    2018 MRS Spring Meeting, April 2-6, Phoenix, Arizona, USA -, - (2018).

2017

  • A radial heat flow apparatus for thermal conductivity characterisation of cylindrical samples Fave L, Pouchon Manuel A, Hébert C
    JOURNAL OF THERMAL ANALYSIS AND CALORIMETRY 130, 1855 (2017).
    DOI: 10.1007/s10973-017-6578-8
  • Analysis of the U L-3-edge X-ray absorption spectra in UO2 using molecular dynamics simulations Bocharov Dmitry, Chollet Melanie, Krack Matthias, Bertsch Johannes, Grolimund Daniel, Martin Matthias, Kuzmin Alexei, Purans Juris, Kotomin Eugene
    PROGRESS IN NUCLEAR ENERGY 94, 187-193 (2017).
    DOI: 10.1016/j.pnucene.2016.07.017
  • Application of hysteresis energy criterion in a microstructure-based model for fatigue crack initiation and evolution in austenitic stainless steel Herrera-Solaz V, Niffenegger M
    INTERNATIONAL JOURNAL OF FATIGUE 100, 84 (2017).
    DOI: 10.1016/j.ijfatigue.2017.03.014
  • Assessment of the platinum deposition behaviour on stainless steel surfaces in a boiling water reactor plant Ritter S, Grundler Pascal V, Veleva L, Ledergerber G, Pathania R
    Corrosion Engineering, Science and Technology 52, 578 (2017).
    DOI: 10.1080/1478422X.2017.1357959
  • Behavior of solute Ni in the corrosion layer of irradiated Zircaloy-2 cladding: A hydrogen uptake perspective Kuri G, Ramanantoanina H, Martin M, Bertsch J
    2017 Water Reactor Fuel Performance Meeting, September 10-14, Jeju, Korea -, - (2017).
  • Calibration of a new local approach to cleavage fracture of ferritic steels Qian G, Lei W, Niffenegger M
    Materials Science and Engineering: A 694, 10 (2017).
    DOI: 10.1016/j.msea.2017.03.111
  • Challenge and Reward of Flat, Tapered Specimen Testing in High-Temperature Water Vankeerberghen M, Bai J, Ritter S, Seifert HP
    Annual Meeting of the Int. Cooperative Group on Environmentally-Assisted Cracking of Water Reactor Materials, ICG-EAC, N.P.O., May 7-12, Chester, UK Paper No GO03 CD-ROM, (2017).
  • Constraint Assessment for Specimens Tested Under Uniaxial and Biaxial Loading Conditions Cao Y, Qian G, He Y, Chao Yuh J, Niffenegger M
    Volume 6A: Materials and Fabrication , (2017).
    DOI: 10.1115/PVP2017-65979
  • EAC of Carbon & Low-Alloy Steels in Light Water Reactors, Invited Talk Seifert HP, Ritter S
    EUROCORR & ICC 2017, 50 Years WP4 Jubilee Workshop, September 3-7, Prague, Chech Republic , (2017).
  • Editorial for the special issue on Corrosion of Nuclear Materials Ritter S, Feron D
    Corrosion Engineering, Science and Technology 52, 557 (2017).
    DOI: 10.1080/1478422X.2017.1388591
  • Effect of Dynamic Strain Ageing and Steel Sulphur Content on Hydrogen Embrittlement in Low-Alloy RPV Steels Rao GS, Que Z, Seifert HP, Spaetig P, Ritter S
    14th Int. Conference on Fracture (IFC 14), June 18-23, Rhodes, Greece CD-ROM/USB, (2017).
  • Effect of High-Temperature Water Environment on the Fracture Behaviour of Low-alloy RPV Steels, in Que Z, Seifert HP, Spaetig P, Rao GS, Ritter S
    18th Int. Conference on Environmental Degradation of Materials in Nuclear Systems - Water Reactor, August 13-17, Portland, OR, USA CD-ROM, (2017).
  • Effect of residual stresses on notch toughness of the tempered martensitic steel F82H-MOD Ilchuk N, Davydov V, Spätig P, Seifert H
    THEORETICAL AND APPLIED FRACTURE MECHANICS 90, 244 (2017).
    DOI: 10.1016/j.tafmec.2017.05.023
  • Effects of High-Temperature Water Environments on the Fracture Behaviour of Low-Alloy RPV Steels Que Z, Seifert HP, Spaetig P, Ritter S, Rao GS
    Annual Meeting of the Int. Cooperative Group on Environmentally-Assisted Cracking of Water Reactor Materials, ICG-EAC, N.P.O., May 7-12, Chester, UK Paper No LA01 CD-ROM, (2017).
  • Fatigue Behavior of 316L Austenitic Steel in Air and LWR Environment with and without Mean Stress Chen W, Spaetig P, Seifert HP
    14th Int. Conference on Fracture (IFC 14), June 18-23, Rhodes, Greece , (2017).
  • Formation and deposition of platinum nanoparticles under boiling water reactor conditions Grundler Pascal V, Veleva L, Ritter S
    JOURNAL OF NUCLEAR MATERIALS 494, 200 (2017).
    DOI: 10.1016/j.jnucmat.2017.07.018
  • Fracture Mechanics Analyses of Embedded Cracks Under PTS and Effects of Residual Stresses Qian G, González-Albuixech VF, Niffenegger M
    Volume 6A: Materials and Fabrication , (2017).
    DOI: 10.1115/PVP2017-66202
  • Helium effects on IASCC susceptibility in as-implanted solution annealed, cold-worked and post-implantation annealed 316L steel Villacampa I, Chen JC, Spätig P, Seifert HP, Duval F
    Corrosion Engineering, Science and Technology 52, 567 (2017).
    DOI: 10.1080/1478422X.2017.1323709
  • Laue micro-diffraction and crystal plasticity finite element simulations to reveal a vein structure in fatigued Cu Irastorza-Landa A, Grilli N, Van Swygenhoven H
    JOURNAL OF THE MECHANICS AND PHYSICS OF SOLIDS 104, 157 (2017).
    DOI: 10.1016/j.jmps.2017.04.010
  • Leak-Before-Break assessment of a welded piping based on 3D finite element method Chen M, Yu W, Chen Z, Qian G, Lu F, Xue F
    ANNALS OF NUCLEAR ENERGY 105, 196 (2017).
    DOI: 10.1016/j.anucene.2017.03.020
  • MODELING OF HIGH CYCLE FATIGUE CRACK INITIATION AND Niffenegger M, Herrera-Solaz V
    SMiRT-24, August 20-25. BEXCO, Busan, Korea Paper ID 01-06-06, Div. 01-51, Doc 650 (2017).
  • Mean Stress Effect on Environmental Assisted Fatigue of 316L Austenitic Steel in LWR Environment Chen W, Spaetig P, Seifert HP
    International Workshop on Materials Resistant to Extreme Conditions for Future Energy Systems, June 12-14, Kiev, Ukraine , (2017).
  • NEW INSIGHTS IN THE FUEL GRAIN SUBDIVISION DURING IN-PLANT IRRADIATION UP TO HIGH BURN-UP Chollet M, Cozzo C, Bertsch J, Martin M, Grolimund D, Samson VA
    2017 Water Reactor Fuel Performance Meeting, September 10-14, Jeju, Korea -, - (2017).
  • New understanding of nano-scale interstitial dislocation loops in BCC iron Gao N, Chen J, Kurtz R, Wang Z, Zhang R, Gao F
    Journal of Physics: Condensed Matter 29, 455301 (2017).
    DOI: 10.1088/1361-648X/aa8a47
  • Observation of crack microstructure in oxides and its correlation to oxidation and hydrogen-uptake by 3D FIB Tomography?case of Zr-ZrO2 in reactor Baris A, Abolhassani S, Chiu YL, Evans HE
    10th International Conference on Microscopy of Oxidation, April 3-5, Loughborough University, UK -, - (2017).
    DOI: 10.1080/09603409.2017.1392412
  • On the calculation of multiplet energies of three-open-shell 4f 13 5f n 6d 1 electron configuration by LFDFT: modeling the optical spectra of 4f core-electron excitation in actinide compounds Ramanantoanina H
    PHYSICAL CHEMISTRY CHEMICAL PHYSICS 19, 32481 (2017).
    DOI: 10.1039/C7CP06198F
  • Pt Deposition on Stainless Steel in Laminar, Mixed and Turbulent High-Temperature Water Flow Regimes Using Customized Rotating Disk Experiments Rowthu S, Grundler PV, Veleva L, Ritter S
    EUROCORR 2017, EFC, September 3-7, Prague, Czech Republic PNo 99156 CD-ROM/USB, - (2017).
  • Quantifying the stress field of hydride precipitation by mu-XRD tomography Chollet M, Gong W, Sanchez Ferreira D, Samson VA, Bertsch J
    2017 Water Reactor Fuel Performance Meeting, September 10-14, Jeju, Korea , (2017).
  • SCC mitigation in boiling water reactors: Platinum deposition and durability on structural materials Grundler PV, Ritter S, Veleva L
    18th Int. Conference on Environmental Degradation of Materials in Nuclear Systems - Water Reactor, August 13-17, Portland, OR, USA CD-ROM, (2017).
    DOI: 10.1007/978-3-319-68454-3_37
  • SiC CLADDING BEHAVIOR: EXPERIMENTS AND MODELLING AT PSI Cozzo C, Bertsch J, Fave L, Rahman S, Dokhane A, Krack M, Pouchon M, Dai Y, Chen J C, Pytel M
    2017 Water Reactor Fuel Performance Meeting, September 10-14, Jeju, Korea 2017, 1 (2017).
  • Statistical assessment of notch toughness against cleavage fracture of ferritic steels Qian G, Lei WS, Peng L, Yu Z, Niffenegger M
    FATIGUE & FRACTURE OF ENGINEERING MATERIALS & STRUCTURES 41, 1120 (2017).
    DOI: 10.1111/ffe.12756
  • Stress Corrosion Crack Initiation and Short Crack Growth Behaviour in Alloy 182 Weld Metal under BWR/HWC Condition Bai J, Ritter S, Seifert HP, Virtanen S
    Annual Meeting of the Int. Cooperative Group on Environmentally-Assisted Cracking of Water Reactor Materials, ICG-EAC, N.P.O., May 7-12, Chester, UK Paper No WE09 CD-ROM, (2017).
  • Stress induced hydrogen redistribution in Zircaloy measured by high-resolution neutron imaging Gong W, Trtik P, Zubler R, Bertsch J
    2017 Water Reactor Fuel Performance Meeting, September 10-14, Jeju, Korea , (2017).
  • Synchrotron X-ray diffraction investigations on strains in the oxide layer of an irradiated Zircaloy fuel cladding Chollet M, Valance S, Abolhassani S, Stein G, Grolimund D, Martin M, Bertsch J
    JOURNAL OF NUCLEAR MATERIALS 488, 181 (2017).
    DOI: 10.1016/j.jnucmat.2017.03.010
  • The use of tapered specimens to evaluate the SCC initiation susceptibility in Alloy 182 in BWR and PWR environments Bai J, Ritter S, Seifert HP, Vankeerberghen M, Bosch RW
    18th Int. Conference on Environmental Degradation of Materials in Nuclear Systems - Water Reactor, August 13-17, Portland, OR, USA CD-ROM, (2017).
  • Tunable magnetic vortex resonance in a potential well Warnicke P, Wohlhüter P, Suszka AK, Stevenson SE, Heyderman LJ, Raabe J
    PHYSICAL REVIEW B 96, 174402 (2017).
    DOI: 10.1103/PhysRevB.96.174402
  • Using tapered specimens to study the effect of hydrogen and surface finish on SCC initiation in Alloy 182 under boiling water reactor conditions Bai J, Ritter S, Seifert H, Virtanen S
    Corrosion Engineering, Science and Technology 52, 558 (2017).
    DOI: 10.1080/1478422X.2017.1340245

2016

  • An inverse method based on finite element model to derive the plastic flow properties from non-standard tensile specimens of Eurofer97 steel Knitel S, Spätig P, Seifert HP
    Nuclear Materials and Energy 9, 311 (2016).
    DOI: 10.1016/j.nme.2016.06.017
  • Analysis of a reactor pressure vessel subjected to pressurized thermal shocks Niffenegger M, Qian G, Gonzalez-Albuixech VF, Sharabi M, Lafferty N
    International Journal of Computational Methods and Experimental Measurements 4, 288 (2016).
    DOI: 10.2495/CMEM-V4-N3-288-300
  • Analysis of effects of pellet-cladding bonding on trapping of the released fission gases in high burnup KKL BWR fuels Brankov Vladimir, Khvostov Grigori, Mikityuk Konstantin, Pautz Andreas, Restani Renato, Abolhassani Sousan, Ledergerber Guido, Wiesenack Wolfgang
    NUCLEAR ENGINEERING AND DESIGN 305, 559-568 (2016).
    DOI: 10.1016/j.nucengdes.2016.06.021
  • Comparison of KI calculation methods Qian G, González-Albuixech VF, Niffenegger M, Giner E
    ENGINEERING FRACTURE MECHANICS 156, 52 (2016).
    DOI: 10.1016/j.engfracmech.2016.02.014
  • Computational fluid dynamics study of pressurized thermal shock phenomena in the reactor pressure vessel Sharabi M, Gonzalez-Albuixech V F, Lafferty N, Niceno B, Niffenegger M
    NUCLEAR ENGINEERING AND DESIGN 299, 136-145 (2016).
    DOI: 10.1016/j.nucengdes.2015.10.014
  • Computational study of platinum nanoparticle deposition on the surfaces of crevices Gu HF, Niceno B, Grundler PV, Sharabi M, Veleva L, Ritter S
    NUCLEAR ENGINEERING AND DESIGN 304, 84 (2016).
    DOI: 10.1016/j.nucengdes.2016.04.020
  • Core electron excitations in U 4+ : modelling of the nd 10 5f 2 -> nd 9 5f 3 transitions with n = 3, 4 and 5 by ligand field tools and density functional theory Ramanantoanina H, Kuri G, Daul C, Bertsch J
    Phys. Chem. Chem. Phys. 18, 19020 (2016).
    DOI: 10.1039/c6cp01395c
  • Correlation between dislocation structures and mechanical fatigue Heczko M, Spätig P, Seifert HP, Kruml T
    SOLID STATE PHENOMENA 258, 534 (2016).
    DOI: 10.4028/www.scientific.net/SSP.258.534
  • Corrosion and Corrosion Fatigue Behavior of Low Nickel High Nitrogen Austenitic Stainless Steel G SR, Singh V, Singhal LK
    17th Asian Pacific Corrosion Control Conference (APCCC17), January 27-30, IIT Bombay, Mumbai, India , Paper No 17064 (2016).
  • Coupled RELAP5, 3D CFD and FEM analysis of postulated cracks in RPVs subjected to PTS loading González-Albuixech VF, Qian G, Sharabi M, Niffenegger M, Niceno B, Lafferty N
    NUCLEAR ENGINEERING AND DESIGN 297, 111 (2016).
    DOI: 10.1016/j.nucengdes.2015.11.032
  • Crack Growth Testing of Low-Alloy Steels in Simulated BWR Environment - PSI Experience Ritter S, Seifert HP
    Annual Meeting of the Int. Cooperative Group on Environmentally-Assisted Cracking of Water Reactor Materials, ICG-EAC, N.P.O., May 15-20, Qingdao, China CD-ROM, Paper No TU03 (2016).
  • Defect structures of F82H irradiated at SINQ using positron annihilation spectroscopy Sato K, Ikemura K, Krsjak V, Vieh C, Brun R, Xu Q, Yoshiie T, Dai Y
    JOURNAL OF NUCLEAR MATERIALS 468, 281 (2016).
    DOI: 10.1016/j.jnucmat.2015.03.055
  • Deterministic and Probabilistic PTS study for a reactor pressure vessel considering plume cooling effects Qian G, Niffenegger M, Sharabi M, Lafferty N
    ASME 2016 Pressure Vessels & Piping Conference PVP2016, July 17-21, Vancouver, BC, Canada , 2016-63869 (2016).
  • Developing an in situ EXAFS experiment of microwave-induced gelation Cozzo C, Ishizaki K, Pouchon MA, Vaucher S
    JOURNAL OF SOL-GEL SCIENCE AND TECHNOLOGY 78, 507 (2016).
    DOI: 10.1007/s10971-016-3992-5
  • Effect of Pt Pre-Treatment of Fresh Stainless Steel Surfaces on the 60Co Build-up During BWR Power Operation Ritter S, Grundler PV, Veleva L, Kaufmann W
    Nuclear Plant Chemistry (NPC) Conference, October 2-7, Brighton, UK CD-ROM/USB, Paper No 104 (2016).
  • Effect of dynamic strain aging on cyclic stress response and deformation behavior of Zircaloy-2 G SR, Verma P, Chakravartty JK, Nudurupati S, Mahobia GS, NC SS, Singh V
    7th International Conference on Creep, Fatigue and Creep-Fatigue Interaction (CF-7), January 19-22, Indira Gandhi Centre for Atomic Research, Kalpakkam, Tamil Nadu, India , (2016).
  • Effect of high-temperature water and hydrogen on the fracture behavior of a low-alloy reactor pressure vessel steel Roychowdhury S, Seifert HP, Spätig P, Que Z
    JOURNAL OF NUCLEAR MATERIALS 478, 343 (2016).
    DOI: 10.1016/j.jnucmat.2016.05.033
  • Effect of hydrogen on tensile behavior of low alloy steel in the regime of dynamic strain ageing Rao G, Seifert H, Ritter S, Spätig P, Que Z
    Procedia Structural Integrity 2, 3399 (2016).
    DOI: 10.1016/j.prostr.2016.06.424
  • Effects of High-Temperature Water and Hydrogen on the Fracture Behaviour of Low-Alloy RPV Steels Que Z, Seifert HP, Spaetig P
    Annual Meeting of the Int. Cooperative Group on Environmentally-Assisted Cracking of Water Reactor Materials, ICG-EAC, N.P.O., May 15-20, Qingdao, China CD-ROM, Paper No LA02 (2016).
  • Feasibility Study on the Detection of Crack Initiation by Electrochemical Noise in Ni-Base Alloy and Stainless Steel in BWR Hydrogen Water Chemistry Bai J, Ritter S, Seifert HP
    Annual Meeting of the European Cooperative Group on Corrosion Monitoring of Nuclear Materials, June 13-14, Mol, Belgium CD-ROM, WG2-2 (2016).
  • Following dislocation patterning during fatigue Irastorza-Landa A, Van Swygenhoven H, Van Petegem S, Grilli N, Bollhalder A, Brandstetter S, Grolimund D
    ACTA MATERIALIA 112, 184 (2016).
    DOI: 10.1016/j.actamat.2016.04.011
  • Fracture mechanics assessment of thermal aged nuclear piping based on the Leak-Before-Break concept Chen M, Yu W, Qian G, Wang R, Lu F, Zhang G, Xue F, Chen Z
    NUCLEAR ENGINEERING AND DESIGN 301, 333 (2016).
    DOI: 10.1016/j.nucengdes.2016.03.025
  • Helium Effects on 316L Austenitic Stainless Steel Fracture Mechanism Villacampa I, Chen J, Spätig P, Seifert H, Duval F
    KEY ENGINEERING MATERIALS 713, 228 (2016).
    DOI: 10.4028/www.scientific.net/KEM.713.228
  • High-Temperature Water Effects on the Fracture Behaviour of Low-Alloy RPV Steels Que Z, Seifert HP, Spaetig P, Ritter S, Rao GS
    EUROCORR, EFC, September 11-15, Montpellier, France CD-ROM/USB, Paper No 52357 (2016).
  • Homogenized Helium Effects on IASCC Susceptibility Villacampa I, Chen JC, Spaetig P, Seifert HP, Duval F
    EUROCORR, EFC, September 11-15, Montpellier, France CD-ROM/USB, Paper No 60057 (2016).
  • Influence of Pt Deposition on the Behaviour of Zircaloy Cladding under Boiling Conditions in Simulated BWR Environment Grundler PV, Ritter S, Veleva L, Oliver L, Helmerson B, Allner S, Ledergerber G
    Nuclear Plant Chemistry (NPC) Conference, October 2-7, Brighton, UK CD/ROM/USB, Paper No 30 (2016).
  • Integrity analysis of a reactor pressure vessel subjected to a realistic pressurized thermal shock considering the cooling plume and constraint effects González-Albuixech VF, Qian G, Sharabi M, Niffenegger M, Niceno B, Lafferty N
    ENGINEERING FRACTURE MECHANICS 162, 201 (2016).
    DOI: 10.1016/j.engfracmech.2016.05.010
  • Interpretation of the U L-3-edge EXAFS in uranium dioxide using molecular dynamics and density functional theory simulations Bocharov Dmitry, Chollet Melanie, Krack Matthias, Bertsch Johannes, Grolimund Daniel, Martin Matthias, Kuzmin Alexei, Purans Juris, Kotomin Eugene
    16TH INTERNATIONAL CONFERENCE ON X-RAY ABSORPTION FINE STRUCTURE (XAFS16) 712, (2016).
    DOI: 10.1088/1742-6596/712/1/012091
  • Investigation of the Platinum Deposition Behavior on Stainless Steel Surfaces in a Boiling Water Reactor Plant Grundler PV, Ritter S, Veleva L, Ledergerber G, Pathania RS
    Int. LWR Materials Reliability Conference and Exhibition 2016, EPRI, August 1-4, Chicago, IL, USA USB-Stick, Paper No 51 (2016).
  • Literature Survey on the Effect of Hydrogen on Stress Corrosion Cracking Behaviour in Ni-Base Alloys under Light Water Reactor Conditions Bai J, Ritter S, Seifert HP
    PowerPlant Chemistry 18 (3), 130 (2016).
  • Microstructure & mechanical fatigue response of 316L steel loaded with/without mean stress at high temperature in air and water environment Heczko M, Spaetig P, Seifert HP, Kruml T
    27th Colloquium on Fatigue Mechanisms, March 22-23, Vienna, Austria , (2016).
  • Microstructure and microhardness of CLAM steel irradiated up to 20.8 dpa in STIP-V Peng L, Ge H, Dai Y, Huang Q, Ye M
    JOURNAL OF NUCLEAR MATERIALS 468, 255 (2016).
    DOI: 10.1016/j.jnucmat.2015.11.023
  • Microstructure and tensile properties of ODS ferritic steels mechanically alloyed with Fe2Y Macías-Delgado J, Leguey T, de Castro V, Auger MA, Monge MA, Spätig P, Baluc N, Pareja R
    Nuclear Materials and Energy 9, 372 (2016).
    DOI: 10.1016/j.nme.2016.09.019
  • Microstructure and tensile properties of tungsten at elevated temperatures Shen T, Dai Y, Lee Y
    JOURNAL OF NUCLEAR MATERIALS 468, 348 (2016).
    DOI: 10.1016/j.jnucmat.2015.09.057
  • Mitigation of Crack Initiation in LWRs (Micrin+) Berger S, Kilian R, Ritter S, Ehrnsten U, Bosch RW, Perosanz FJ
    EUROCORR, EFC, September 11-15, Montpellier, France CD-ROM/USB, Paper No 65952 (2016).
  • Mitigation of the core shroud cracking in nuclear power plant Mühleberg from a regulator's perspective Germerdonk K, Seifert HP, Ritter S
    Annual Meeting of the Int. Cooperative Group on Environmentally-Assisted Cracking of Water Reactor Materials, ICG-EAC, N.P.O., May 15-20, Qingdao, China CD-ROM, (2016).
  • Neptunium characterization in uranium dioxide fuel: Combining a XAFS and a thermodynamic approach Chollet M, Martin P, Degueldre C, Poonoosamy J, Belin R C, Hennig C
    JOURNAL OF ALLOYS AND COMPOUNDS 662, 448-454 (2016).
    DOI: 10.1016/j.jallcom.2015.12.005
  • Non-destructive testing of the MEGAPIE target Dai Y, Wohlmuther M, Boutellier V, Hahl S, Lagotzki A, Leu H, Linder HP, Schwarz R, Spahr A, Zanini L, Kuster D, Gavillet D, Wagner W
    JOURNAL OF NUCLEAR MATERIALS 468, 221 (2016).
    DOI: 10.1016/j.jnucmat.2015.08.026
  • On the condition of UO 2 nuclear fuel irradiated in a PWR to a burn-up in excess of 110 MWd/kgHM Restani R, Horvath M, Goll W, Bertsch J, Gavillet D, Hermann A, Martin M, Walker CT
    JOURNAL OF NUCLEAR MATERIALS 481, 88 (2016).
    DOI: 10.1016/j.jnucmat.2016.08.023
  • Positron annihilation spectroscopy study of lattice defects in non-irradiated doped and un-doped fuels Chollet M, Krsjak V, Cozzo C, Bertsch J
    EPJ Nuclear Sci. Technol. 3, 3 (2016).
    DOI: 10.1051/epjn/2016040
  • Post irradiation examination of nuclear fuel: Toward a complete analysis Degueldre C, Bertsch J, Martin M
    PROGRESS IN NUCLEAR ENERGY 92, 242 (2016).
    DOI: 10.1016/j.pnucene.2016.03.025
  • Probabilistic Pressurized Thermal Shock Analysis for a Reactor Pressure Vessel Considering Plume Cooling Effect Qian G, González-Albuixech VF, Niffenegger M, Sharabi M
    Journal of Pressure Vessel Technology 138, 041204 (2016).
    DOI: 10.1115/1.4032197
  • Probabilistic ageing and risk analysis tools for nuclear piping Qian G, Chou H, Niffenegger M, Huang C
    NUCLEAR ENGINEERING AND DESIGN 300, 541 (2016).
    DOI: 10.1016/j.nucengdes.2016.02.033
  • Ratcheting fatigue behavior of Zircaloy-2 at room temperature Rajpurohit RS, Sudhakar Rao G, Chattopadhyay K, Santhi Srinivas NC, Singh V
    JOURNAL OF NUCLEAR MATERIALS 477, 67 (2016).
    DOI: 10.1016/j.jnucmat.2016.05.014
  • Review of Integrity analyses of the Reactor Pressure Vessels in Taiwan and Switzerland (PSI) Chou H, Qian G, Huang C, Niffenegger M
    11th International Workshop on the Integrity of Nuclear Components, April 11 - 13, Nagasaki, Japan , (2016).
  • Stress Corrosion Cracking Initiation and Short Crack Growth Behavior in Alloy 182 Weld Metal under Simulated BWR/HWC Conditions Bai J, Ritter S, Seifert HP, Virtanen S
    Annual Meeting of the Int. Cooperative Group on Environmentally-Assisted Cracking of Water Reactor Materials, ICG-EAC, N.P.O., May 15-20, Qingdao, China CD-ROM, Paper No WE01 (2016).
  • Stress Fields Induced by Dislocation Loops in Isotropic CuNb Film- Substrate System Wu W, Qian G, Cui X
    Journal of Applied Mechanical Engineering 5, 205 (2016).
    DOI: 10.4172/2168-9873.1000205
  • Synchrotron XRD Analysis of Irradiated UO2 Fuel at Various Burn-up Chollet M, Kuri G, Grolimund D, Martin M, Bertsch J
    TopFuel 2016: LWR Fuels with Enhanced Safety and Performance (Sep 11-16, 2016, Boise, Idaho, U.S.A.) -, - (2016).
  • Temperature and Loading-Rate Dependence on a Local Criterion for Cleavage Fracture in the Transition Region of the Tempered Martensitic Steel Eurofer97. Knitel S, Spätig P, Seifert HP
    Procedia Structural Integrity 2, 1684 (2016).
    DOI: 10.1016/j.prostr.2016.06.213
  • Tensile properties of CLAM steel irradiated up to 20.1 dpa in STIP-V Ge H, Peng L, Dai Y, Huang Q, Ye M
    JOURNAL OF NUCLEAR MATERIALS 468, 240 (2016).
    DOI: 10.1016/j.jnucmat.2015.10.040
  • The influence of ppb levels of chloride impurities on the stain-induced corrosion cracking and corrosion fatigue crack growth behavior of low-alloy steels under simulated boling water reactor conditions Seifert HP, Ritter S
    CORROSION SCIENCE 108, 148 (2016).
    DOI: 10.1016/j.corsci.2016.03.010
  • The influence of ppb levels of chloride impurities on the stress corrosion crack growth behaviour of low-alloy steels under simulated boiling water reactor conditions Seifert HP, Ritter S
    CORROSION SCIENCE 108, 134 (2016).
    DOI: 10.1016/j.corsci.2016.03.001
  • Using Tapered Specimens to Study the Effect of Hydrogen on SCC Initiation in Alloy 182 under BWR Conditions Bai J, Ritter S, Seifert HP, Virtanen S
    EUROCORR, EFC, September 11-15, Montpellier, France CD-ROM/USB, Paper No 50507 (2016).

2015

  • (High) burn-up microstructural changes Bertsch J, Chollet M, Degueldre C, Grolimund D, Kuri G, Mieszczynski C
    Joint HRP-NEA WGFS LOCA workshop on Fuel Fragmentation, Relocation and Dispersal (FFRD) ? experimental basis, mechanisms and modelling approaches, hosted by IRSN, May 20-21, 2015, Aix-en-Provence, Fra , (2015).
  • (Multielectrode-) EN Measurements in Simulated BWR-NWC and -HWC Environments – First Preliminary Results Ritter S, Bai J, Seifert HP
    Annual Meeting of the European Cooperative Group on Corrosion Monitoring of Nuclear Materials, June 15-16, Prague, Czech Republic CD-ROM, WG2-6 (2015).
  • A fixed point in the Coffin?Manson law Tirbonod B
    INTERNATIONAL JOURNAL OF FATIGUE 81, 143 (2015).
    DOI: 10.1016/j.ijfatigue.2015.06.011
  • Calibration of Beremin model with the Master Curve Qian G, Gonzalez-Albuixech VF, Niffenegger M
    ENGINEERING FRACTURE MECHANICS 136, 15 (2015).
    DOI: 10.1016/j.engfracmech.2015.02.003
  • Coincidence Doppler broadening study of Eurofer 97 irradiated in spallation environment Sabelova V, Krsjak V, Kuriplach J, Dai Y, Slugen V
    JOURNAL OF NUCLEAR MATERIALS 458, 350-354 (2015).
    DOI: 10.1016/j.jnucmat.2014.12.053
  • Comparison of PTS analyses of RPVs based on 3D-CFD and RELAP5 González-Albuixech VF, Qian G, Sharabi M, Niffenegger M, Niceno B, Lafferty N
    NUCLEAR ENGINEERING AND DESIGN 291, 168 (2015).
    DOI: 10.1016/j.nucengdes.2015.05.025
  • Crystal plasticity finite element modelling of low cycle fatigue in fcc metals Grilli N, Janssens KGF, Van Swygenhoven H
    JOURNAL OF THE MECHANICS AND PHYSICS OF SOLIDS 84, 424 (2015).
    DOI: 10.1016/j.jmps.2015.08.007
  • Edge-on dislocation loop in anisotropic hcp zirconium thin foil Wu W, Xia R, Qian G, Xu S, Zhang J
    JOURNAL OF NUCLEAR MATERIALS 465, 212 (2015).
    DOI: 10.1016/j.jnucmat.2015.05.019
  • Effect of Dissolved Hydrogen Content on SCC Initiation and Short Crack Growth Behavior in Alloy 182 under BWR Conditions Bai J, Ritter S, Seifert HP, Virtanen S
    Annual Meeting of the Int. Cooperative Group on Environmentally Assisted Cracking of Water Reactor Materials, May 17-22, Ann Arbor, MI, USA CD-ROM, Paper No. Wp1 (2015).
  • Effect of Flow Conditions on the Deposition of Platinum Nanoparticles on Stainless Steel Surfaces Grundler PV, Veleva L, Ramar A, Ritter S
    CORROSION 71(1), 101 (2015).
    DOI: 10.5006/1263
  • Effect of High-Temperature Water and Hydrogen on the Fracture Behaviour of a Low-Alloy Reactor Pressure Vessel Steel Roychowdhury S, Seifert HP, Spaetig P, Que Z, Ritter S
    17th Int. Conference on Environmental Degradation of Materials in Nuclear Systems - Water Reactors, August 9-13, Ottawa, Canada CD-ROM, Paper No 34 (2015).
  • Elastic field of approaching dislocation loop in isotropic bimaterial Wu W, Xia R, Xu S, Qian G, Zhang J
    MODELLING AND SIMULATION IN MATERIALS SCIENCE AND ENGINEERING 23, 075006 (2015).
    DOI: 10.1088/0965-0393/23/7/075006
  • Evolution of the atomic-scale structure from a pristine to high burn-up UO2 fuel by X-ray absorption spectroscopy Chollet M, Bertsch J, Grolimund D, Martin M
    E-MRS 2015 , May 11-15, Lille, France -, - (2015).
  • Fatigue crack initiation and crystallographic growth in 316L stainless steel, International Journal of Fatigue Sistaninia M, Niffenegger M
    INTERNATIONAL JOURNAL OF FATIGUE 70, 163 (2015).
    DOI: 10.1016/j.ijfatigue.2014.09.010
  • Fractal characteristics of fracture morphology of steels irradiated with high-energy ions Xian Y, Liu J, Zhang C, Chen J, Yang Y, Zhang L
    JOURNAL OF NUCLEAR MATERIALS 461, 171 (2015).
    DOI: 10.1016/j.jnucmat.2015.03.022
  • Gelation and other innovative conversion processes for aqueous-based reprocessing and recycling of spent nuclear fuels in Pouchon MA
    Reprocessing and Recycling of Spent Nuclear Fuel , 353-369 (2015).
    DOI: 10.1016/b978-1-78242-212-9.00014-9
  • Helium behavior in ferritic/martensitic steels irradiated in spallation target Krsjak Vladimir, Kuriplach Jan, Shen Tielong, Sabelova Veronika, Sato Koichi, Dai Yong
    JOURNAL OF NUCLEAR MATERIALS 456, 382-388 (2015).
    DOI: 10.1016/j.jnucmat.2014.10.014
  • High-Temperature Water and Hydrogen Effects on the Fracture Behaviour of a Low-Alloy RPV Steel Roychowdhury S, Seifert HP, Spaetig P, Ritter S
    Annual Meeting of the Int. Cooperative Group on Environmentally Assisted Cracking of Water Reactor Materials, May 17-22, Ann Arbor, MI, USA CD-ROM, Paper No L05 (2015).
  • Hydrides Reorientation Investigation of High Burn-up PWR Fuel Cladding Valance S, Bertsch J
    JOURNAL OF NUCLEAR MATERIALS 464, 371 (2015).
    DOI: 10.1016/j.jnucmat.2015.05.003
  • Hydrogen relocation kinetics within Zircaloy cladding tubes Valance S, Zemek M, Bertsch J, Hellwig Ch
    TopFuel 2015: Reactor Fuel Performance (Sep 13-17, 2015, Zuerich, Switzerland) http://www.euronuclear.org/events/topfuel/topfuel2015/transactions.htm paper A0168, - (2015).
  • Influence of the temperature on the tension behaviour of EUROFER97 alloy at high strain rate Cadoni E, Dotta M, Forni D, Spaetig P
    EUROPEAN PHYSICAL JOURNAL - WEB OF CONFERENCES 94, 01022 (2015).
    DOI: 10.1051/epjconf/20159401022
  • Investigation of constraint and warm prestressing effects by means of a local approach to fracture Qian G, Niffenegger M
    ENGINEERING FRACTURE MECHANICS 136, 26 (2015).
    DOI: 10.1016/j.engfracmech.2015.01.031
  • Manufacturing of a New Type of Nde Test Samples with Laboratory-Grown Intergranular SCC Cracks in a Nickel-Base Weld – Comparison of Various Nde-Techniques Applied to a Challenging Crack Morphology Germerdonk K, Seifert HP, Ernst H, Nussbaum D, Ritter S
    11th Int. Conference on Non-Destructive Evaluation, May 19-21, Jeju Island, Korea CD-ROM, (2015).
  • Mean stress effect on fatigue life of 316L austenitic steel in air and simulated boiling water reactor hydrogen water chemistry environment Spaetig P, Seifert HP
    17th Int. Conference on Environmental Degradation of Materials in Nuclear Systems - Water Reactors, August 9-13, Ottawa, Canada CD-ROM, Paper No 83 (2015).
  • Methodology and Warm Prestressing Effect for Pressurized Thermal Shock Analysis in Nuclear Power Plant Qian G, Niffenegger M
    APPLIED MECHANICS AND MATERIALS 750, 104 (2015).
    DOI: 10.4028/www.scientific.net/AMM.750.104
  • Microstructure and fracture behavior of F82H steel under different irradiation and tensile test conditions Wang K, Dai Y, Spaetig P
    JOURNAL OF NUCLEAR MATERIALS , (2015).
    DOI: 10.1016/j.jnucmat.2015.09.031
  • Modeling of Axial Distribution of Released Fission Gas in KKL BWR Fuel Rods during Base Irradiation Brankov V, Khvostov G, Mikityuk K, Pautz A, Restani R, Abolhassani S
    TopFuel 2015: Reactor Fuel Performance (Sep 13-17, 2015, Zuerich, Switzerland) http://www.euronuclear.org/events/topfuel/topfuel2015/transactions.htm 1, 609 (2015).
  • Noble Metal Applications for SCC Mitigation in BWRs: Platinum Nanoparticle Penetration into Crevices and Cracks under Controlled Flow Conditions Grundler PV, Veleva L, Gu H, Allner S, Niceno B, Ritter S
    17th Int. Conference on Environmental Degradation of Materials in Nuclear Systems - Water Reactors, August 9-13, Ottawa, Canada CD-ROM, Paper No 96 (2015).
  • Platinum Deposition Behaviour on Stainless Steel Surfaces in a Boiling Water Reactor Plant Ritter S, Grundler PV, Veleva L, Ledergerber G
    EUROCORR, EFC, September 6-10, Graz, Austria CD-ROM, Paper No 870 (2015).
  • Platinum Deposition on a Boiling Stainless Steel Surface (Simulating a Fuel Rod) Veleva L, Grundler PV, Streit M, Ritter S
    TopFuel 2015: Reactor Fuel Performance (Sep 13-17, 2015, Zuerich, Switzerland) http://www.euronuclear.org/events/topfuel/topfuel2015/transactions.htm , Paper No. A0232 (2015).
  • Positron annihilation spectroscopy study of lattice defects in non-irradiated doped and un-doped fuels Chollet M, Krsjak V, Cozzo C, Bertsch J
    TopFuel 2015: Reactor Fuel Performance (Sep 13-17, 2015, Zuerich, Switzerland) http://www.euronuclear.org/events/topfuel/topfuel2015/transactions.htm Paper A0109, (2015).
  • Probabilistic Pressurized Thermal Shocks Analyses for a Reactor Pressure Vessel Qian G, Niffenegger M
    ASME Journal of Pressure Vessel Technology 137, 061206 (2015).
    DOI: 10.1115/1.4030299
  • Probabilistic pressurized thermal shocks analysis for a reactor pressure vessel by considering plume effect Qian G, Gonzalez-Albuixech VF, Niffenegger M, Sharabi M
    ASME Pressure Vessel and Piping Division Conference, July 19-23, Boston, Massachusetts, USA , 2015-45963 (2015).
  • Pt Deposition Behaviour on Stainless Steel under BWR Conditions: Plant Results of the NORA Project Ritter S, Grundler PV, Veleva L, Ramar A
    Annual Meeting of the Int. Cooperative Group on Environmentally Assisted Cracking of Water Reactor Materials, May 17-22, Ann Arbor, MI, USA CD-ROM, Paper No Gp1 (2015).
  • Stress Corrosion Cracking Behavior in the Transition Region of Alloy 182/Low-Alloy Reactor Pressure Vessel Steel Dissimilar Metal Weld Joints in Light Water Reactor Environments Seifert HP, Ritter S, Leber HJ, Roychowdhury S
    CORROSION 71, Issue 4, 433 (2015).
    DOI: 10.5006/1400
  • Theoretical modelling of pristine and chromium-doped UO2 Bocharov D, Chollet M, Krack M, Kuzmin A, Bertsch J, Grolimund D, Martin M
    E-MRS 2015 , May 11-15, Lille, France -, - (2015).
  • Uranium trioxide behavior during electron energy loss spectroscopy analysis Degueldre C, Evgeny VA
    RADIATION PHYSICS AND CHEMISTRY 108, 7 (2015).
    DOI: 10.1016/j.radphyschem.2014.10.012

2014

  • A Comprehensive Investigation of the Platinum Application to BWRs to Mitigate Stress Corrosion Cracking Grundler PV, Veleva L, Ramar A, Ritter S
    Nuclear Plant Chemistry (NPC) Conference, AESJ, October 26-31, Sapporo, Japan CD-ROM, 10128 (2014).
  • An internal variable dependent constitutive cyclic plastic material description including ratcheting calibrated for AISI 316L Facheris G, Janssens KGF
    COMPUTATIONAL MATERIALS SCIENCE 87, 160-171 (2014).
    DOI: 10.1016/j.commatsci.2014.02.026
  • Analytical determination of the constitutive behavior from micro-pillar testing, Application to a tempered martensitic steel Ilchuk N, Spaetig P, Seifert HP
    AIP Advances 4, 047126 (2014).
    DOI: 10.1063/1.4873155
  • Assessing some effects of irradiation on the yield and post-yield constitutive properties of structural alloys for nuclear energy applications (key note lecture) Spaetig P, Yamamoto Y, Odette GR, Ilchuk N
    Symposium International Plasticity 2014, January 2-9, Freeport, Bahamas , (2014).
  • Characterization of helium implanted Fe-Cr alloys by means of positron annihilation methods Sabelova V, Krsjak V, Kuriplach J, Petriska M, Slugen V, Veternikova J Simeg
    JOURNAL OF NUCLEAR MATERIALS 450, 54-58 (2014).
    DOI: 10.1016/j.jnucmat.2013.10.039
  • Computational Analyses of the Thermal Stress Induced by Coolant Mixing in a T-Joint Janssens KGF, Niffenegger M, Sharabi M
    Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues , (2014).
    DOI: 10.1115/ICONE22-30218
  • Computational Fluid Dynamics of Pressurized Thermal Shock Phenomena in the Reactor Pressure Vessel Sharabi M, Niceno B, Gonzalez-Albuixech V, Niffenegger M
    CFD4NRS-5: Proceedings of the OECD/NEA & IAEA Workshop on Computational Fluid Dynamics for Nuclear Safety Research, ETH Zuerich, Switzerland, Sep. 9-11, 2014 , (2014).
  • Constraint effects for a reactor pressure vessel subjected to pressurized thermal shock (Procedia Materials Science) Qian G, Gonzalez-Albuixech VF, Niffenegger M
    20th European Conference on Fracture (ECF20), June 30-July 4, Trondheim, Norway 3, 1687-1693 (2014).
  • Corrosion and Hydrogen Uptake in Zirconium Claddings Irradiated in Light Water Reactors Abolhassani S, Bart G, Bertsch J, Grosse M, Hallstadius L, Hermann A, Kuri G, Ledergerber G, Lemaignan C, Martin M, Portier S, Proff C, Restani R, Valance S, Valizadeh S, Wiese H
    ASTM INTERNATIONAL CUSTOMER SERVICE STP1543, 1 (2014).
    DOI: 10.1520/STP154320130007
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