LNM Publication List (since 2012)

2017

  • 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
  • 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
  • Nonlinear Electron-Phonon Coupling in Doped Manganites Esposito V, Fechner M, Mankowsky R, Lemke H, Chollet M, Glownia J M, Nakamura M, Kawasaki M, Tokura Y, Staub U, Beaud P, Foerst M
    PHYSICAL REVIEW LETTERS 118, 247601 (2017).
    DOI: 10.1103/PhysRevLett.118.247601
  • 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

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 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).
  • 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
  • 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
  • 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).
Top

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
  • 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
  • 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) 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) , 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) , (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
  • 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
Top

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 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
  • Deterministic and probabilistic analysis of a reactor pressure vessel subjected to pressurized thermal shocks Qian Guian, Niffenegger Markus
    NUCLEAR ENGINEERING AND DESIGN 273, 381-395 (2014).
    DOI: 10.1016/j.nucengdes.2014.03.032
  • Effect of Chloride on EAC Initiation of Low-Alloy Steel in Simulated BWR Environment Ritter S, Seifert HP
    Annual Meeting of the Int. Cooperative Group on Environmetally Assisted Cracking Of Water Reactor Materials, April 6-11,Prague, Czech Republic CD-ROM (L03), (2014).
  • Effect of Dissolved Hydrogen Content on SCC Initiation and Short Crack Growth Behavior in Alloy 182 under BWR Conditions: A New Project Bai J, Ritter S, Seifert HP, Virtanen S
    Annual Meeting of the Int. Cooperative Group on Environmetally Assisted Cracking Of Water Reactor Materials, April 6-11,Prague, Czech Republic CD-ROM (Wp1), (2014).
  • Electron energy loss spectroscopy investigations through nano-ablated actinide dioxide samples Degueldre Claude, Veleva Lyubomira
    PROGRESS IN NUCLEAR ENERGY 72, 96-100 (2014).
    DOI: 10.1016/j.pnucene.2013.11.016
  • Energy-selective neutron imaging with high spatial resolution and its impact on the study of crystalline-structured materials Lehmann E H, Peetermans S, Josic L, Leber H, van Swygenhoven H
    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT 735, 102-109 (2014).
    DOI: 10.1016/j.nima.2013.08.065
  • Environmental Assisted Fracture of Reactor Pressure Vessel Steel: First Results Roychowdhury S, Seifert HP, Spaetig P, Ritter S
    Annual Meeting of the Int. Cooperative Group on Environmetally Assisted Cracking Of Water Reactor Materials, April 6-11,Prague, Czech Republic CD-ROM (Ls1), (2014).
  • Environmental Effects on Fracture Behavior of a Reactor Pressure Vessel Steel Roychowdhury S, Seifert HP, Spaetig P
    Fontevraud 8, SFEN, September 14-18, Avignon, France CD-ROM (O-T01-028), (2014).
  • Environmental-Assisted Fatigue in Austenitic Stainless Steels under Light Water Reactor Condition Seifert HP, Ritter S, Spaetig P
    Fontevraud 8, SFEN, September 14-18, Avignon, France CD-ROM, O-T03-029 (2014).
  • Experimental study of irradiation induced swelling in commercial and experimental ODS steels implanted with helium ions Fave L, Pouchon MA, Doebeli M, Schulte Borschers M, Kimura A
    ENC 2014, May 11-14, Marseille, France , (2014).
  • Gallium sorption on montmorillonite and illite colloids: Experimental study and modelling by ionic exchange and surface complexation Benedicto Ana, Degueldre Claude, Missana Tiziana
    APPLIED GEOCHEMISTRY 40, 43-50 (2014).
    DOI: 10.1016/j.apgeochem.2013.10.015
  • Geochemical evolution of the L/ILW near field Kosakowski G, Berner U, Wieland E, Glaus M, Degueldre C
    Nagra NTB 14-11, 1 (2014).
  • Ground water colloid properties from the Bangombe system Degueldre Claude, Laaksoharju Marcus
    APPLIED GEOCHEMISTRY 45, 130-143 (2014).
    DOI: 10.1016/j.apgeochem.2014.03.004
  • Helium effects on creep properties of Fe-14CrWTi ODS steel at 650 degrees C Chen J, Jung P, Rebac T, Duval F, Sauvage T, de Carlan Y, Barthe M F
    JOURNAL OF NUCLEAR MATERIALS 453, 253-258 (2014).
    DOI: 10.1016/j.jnucmat.2014.07.010
  • Helium ion irradiation induced swelling and hardening in commercial and experimental ODS steels Fave Loic, Pouchon Manuel A, Doebeli Max, Schulte-Borchers Martina, Kimura Akihiro
    JOURNAL OF NUCLEAR MATERIALS 445, 235-240 (2014).
    DOI: 10.1016/j.jnucmat.2013.11.004
  • In-plane and out-of-plane constraint effects under pressurized thermal shocks Qian Guian, Gonzalez-Albuixech V F, Niffenegger Markus
    INTERNATIONAL JOURNAL OF SOLIDS AND STRUCTURES 51, 1311-1321 (2014).
    DOI: 10.1016/j.ijsolstr.2013.12.021
  • In-situ biaxial mechanical testing at the neutron time-of-flight diffractometer POLDI Repper Julia, Niffenegger Markus, Van Petegem Steven, Wagner Werner, Van Swygenhoven Helena
    INTERNATIONAL CONFERENCE ON RESIDUAL STRESSES 9 (ICRS 9) 768-769, 60-65 (2014).
    DOI: 10.4028/www.scientific.net/MSF.768-769.60
  • Integrity analysis of a reactor pressure vessel with quasi laminar flaws subjected to pressurized thermal shocks Gonzalez-Albuixech Vicente Francisco, Qian Guian, Niffenegger Markus
    NUCLEAR ENGINEERING AND DESIGN 280, 464-472 (2014).
    DOI: 10.1016/j.nucengdes.2014.09.035
  • Integrity analysis of reactor pressure vessels subjected to pressurized thermal shocks by XFEM Gonzalez-Albuixech V F, Qian G, Niffenegger M
    NUCLEAR ENGINEERING AND DESIGN 275, 336-343 (2014).
    DOI: 10.1016/j.nucengdes.2014.04.038
  • Investigation of microstructure and microhardness of pure W and W-2Y2O3 materials before and after ion-irradiation Battabyal M, Spaetig P, Murty BS, Baluc N
    International Journal of Refractory Metals and Hard Materials 46, 168 (2014).
    DOI: 10.1016/j.ijrmhm.2014.06.004
  • Investigation on Constraint Effect of a Reactor Pressure Vessel Subjected to Pressurized Thermal Shocks Qian Guian, Niffenegger Markus
    JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME 137, 011204 (2014).
    DOI: 10.1115/1.4028017
  • Irradiation effects and micro-structural changes in large grain uranium dioxide fuel investigated by micro-beam X-ray diffraction Mieszczynski C, Kuri G, Degueldre C, Martin M, Bertsch J, Borca C N, Grolimund D, Delafoy Ch, Simoni E
    JOURNAL OF NUCLEAR MATERIALS 444, 274-282 (2014).
    DOI: 10.1016/j.jnucmat.2013.09.054
  • Irradiation response of ODS ferritic steels to high-energy Ne ions at HIRFL Zhang CH, Yang YT, Song Y, Chen J, Zhang LQ, Jang J, Kumura A
    JOURNAL OF NUCLEAR MATERIALS 455, 61 (2014).
    DOI: 10.1016/j.jnucmat.2014.04.015
  • Irradiation-induced evolution of mechanical properties and microstructure of Eurofer 97 Zhang T, Vieh C, Wang K, Dai Y
    JOURNAL OF NUCLEAR MATERIALS 450, 48-53 (2014).
    DOI: 10.1016/j.jnucmat.2013.12.007
  • Local atomic structure of chromium bearing precipitates in chromia doped uranium dioxide investigated by combined micro-beam X-ray diffraction and absorption spectroscopy Kuri G, Mieszczynski C, Martin M, Bertsch J, Borca C, Delafoy Ch
    JOURNAL OF NUCLEAR MATERIALS 449, 158-167 (2014).
    DOI: 10.1016/j.jnucmat.2014.03.017
  • Measurement of residual stresses around the notch of tensile specimens of the high-Cr tempered martensitic steel F82H-mod Ilchuk Nazar, Spaetig Philippe, Davydov Vadim, Van Petegem Steven
    MATERIALS STRUCTURE & MICROMECHANICS OF FRACTURE VII 592-593, 295-298 (2014).
    DOI: 10.4028/www.scientific.net/KEM.592-593.295
  • Mechanical properties of tungsten in the transition temperature range Krsjak V, Wei S H, Antusch S, Dai Y
    JOURNAL OF NUCLEAR MATERIALS 450, 81-87 (2014).
    DOI: 10.1016/j.jnucmat.2013.11.019
  • Methodology and warm prestressing effect for pressurized thermal shock analysis in nuclear power plant Qian G, Niffenegger M
    International Symposium on Structural Integrity, August 20-24, Lanzhou, China , 20-24 (2014).
  • Microbeam X-ray Diffraction to Study Radiation Damage in Irradiated Uranium Dioxide Nuclear Fuel Kuri G, Martin M, Bertsch J, Ledergerber G
    WRFPM 2014 Proceedings, Sendai, Japan CD-ROM, 100043 (2014).
  • Microbeam x-ray absorption spectroscopy study of chromium in large-grain uranium dioxide fuel Mieszczynski C, Kuri G, Bertsch J, Martin M, Borca C N, Delafoy Ch, Simoni E
    JOURNAL OF PHYSICS-CONDENSED MATTER 26, 355009 (2014).
    DOI: 10.1088/0953-8984/26/35/355009
  • Microstructure of Pt Nanoparticles Deposited on Stainless Steel in Simulated Boiling Water Reactor Environment Veleva L, Grundler PV, Ramar A, Ritter S
    18th Int. Microscopy Congress, September 7-12, Prague, Czech Republic , (2014).
  • Multiaxial fatigue behavior of AISI 316L subjected to strain-controlled Facheris G, Janssens KGF, Foletti S
    INTERNATIONAL JOURNAL OF FATIGUE 68, 195 (2014).
    DOI: 10.1016/j.ijfatigue.2014.05.003
  • Noble Metal Chemical Addition to BWRs for Stress Corrosion Cracking Mitigation: Theoretical Insights and Applications Grundler PV, Ritter S
    POWER PLANT CHEMISTRY- The Journal of All Power Plant Chemistry Areas 16 (2), 76 (2014).
  • Positron annihilation spectroscopy of ferritic/martensitic steels F82H and T91 irradiated with protons and neutrons at PSI Sato K, Kawamoto S, Ikemura K, Krsjak V, Vieh C, Brun R, Xu Q, Yoshiie T, Dai Y
    JOURNAL OF NUCLEAR MATERIALS 450, 59-63 (2014).
    DOI: 10.1016/j.jnucmat.2013.09.009
  • Prediction of damage-growth based fatigue life of polycrystalline materials using a microstructural modeling approach Sistaninia M, Niffenegger M
    INTERNATIONAL JOURNAL OF FATIGUE 66, 118 (2014).
  • Probabilistic assessment of a reactor pressure vessel subjected to pressurized thermal shocks by using crack distributions Qian Guian, Gonzalez-Albuixech V F, Niffenegger Markus
    NUCLEAR ENGINEERING AND DESIGN 270, 312-324 (2014).
    DOI: 10.1016/j.nucengdes.2013.12.062
  • Probabilistic pressurized thermal shocks analysis for a reactor pressure vessel Qian G, Niffenegger M
    ASME 2014 Pressure Vessels & Piping Conference PVP, July 20-24, Anaheim, California, USA , 2014-28765 (2014).
  • Production and segregation of transmutation elements Ca, Ti, Sc in the F82H steel under mixed spectrum irradiation of high energy protons and spallation neutrons Kuksenko Viacheslav, Pareige Cristelle, Pareige Philippe, Dai Yong
    JOURNAL OF NUCLEAR MATERIALS 447, 189-196 (2014).
    DOI: 10.1016/j.jnucmat.2014.01.013
  • Proton-induced Polonium Production in Lead Lorenz T, Dai Y, Schumann D, Tuerler A
    NUCLEAR DATA SHEETS 119, 284 (2014).
    DOI: 10.1016/j.nds.2014.08.078
  • Pt Deposition Behaviour on Stainless Steel under Simulated BWR Conditions: Lab Results of the NORA Project Ritter S, Grundler PV, Veleva L, Ramar A
    Annual Meeting of the Int. Cooperative Group on Environmetally Assisted Cracking Of Water Reactor Materials, April 6-11,Prague, Czech Republic CD-ROM (Gp5), (2014).
  • Pt: Key to Improved SCC Mitigation Grundler PV, Veleva L, Ritter S
    NUCLEAR ENGINEERING INTERNATIONAL , 33 (2014).
  • Redox state of plutonium in irradiated mixed oxide fuels Degueldre C, Pin S, Poonoosamy J, Kulik D A
    JOURNAL OF PHYSICS AND CHEMISTRY OF SOLIDS 75, 358-365 (2014).
    DOI: 10.1016/j.jpcs.2013.11.001
  • Reliability of electrochemical noise measurements: Results of round-robin testing on electrochemical noise Bosch Rik-Wouter, Cottis Robert A, Csecs Kinga, Dorsch Thomas, Dunbar Lucia, Heyn Andreas, Huet Francois, Hyokyvirta Outi, Kerner Zsolt, Kobzova Alena, Macak Jan, Novotny Radek, Oijerholm Johan, Piippo Juha, Richner Roy, Ritter Stefan, Sanchez-Amaya Jose M, Somogyi Andras, Vaisanen Saija, Zhang Wenzhong
    ELECTROCHIMICA ACTA 120, 379-389 (2014).
    DOI: 10.1016/j.electacta.2013.12.093
  • SCC Mitigation in BWRs by Platinum Addition: Effect of Environment and Injection Rate Ritter S, Grundler PV, Veleva L, Ramar A
    Fontevraud 8, SFEN, September 14-18, Avignon, France CD-ROM, O-T03-190 (2014).
  • Selenium redox speciation and coordination in high-burnup UO2 fuel: Consequences for the release of Se-79 in a deep underground repository Curti Enzo, Froideval-Zumbiehl Annick, Guenther-Leopold Ines, Martin Matthias, Bullemer Andrej, Linder Hanspeter, Borca Camelia N, Grolimund Daniel
    JOURNAL OF NUCLEAR MATERIALS 453, 98-106 (2014).
    DOI: 10.1016/j.jnucmat.2014.07.003
  • Tensile properties and microstructure of EC316LN irradiated in STIP-II Li B S, Dai Y
    JOURNAL OF NUCLEAR MATERIALS 450, 42-47 (2014).
    DOI: 10.1016/j.jnucmat.2014.02.009
  • The Scientific Basis of the Nuclear Fuel Cycle Degueldre Claude, Grimes Robin, Rondinella Vincenzo, Poinssot Christophe, Bosbach Dirk
    PROGRESS IN NUCLEAR ENERGY 72, 3-4 (2014).
    DOI: 10.1016/j.pnucene.2013.10.010
  • The benefit of the European User Community from transnational access to national radiation facilities Barrier Elise, Braz Fernandes Francisco Manuel, Bujan Maya, Feiters Martin C, Froideval Annick, Ghijsen Jacques, Hase Thomas, Hough Michael A, Jergel Matej, Jimenez Ignacio, Kajander Tommi, Kikas Arvo, Kokkinidis Michael, Kover Laszlo, Larsen Helge B, Lawson David Mark, Lawniczak-Jablonska Krystyna, Mariani Carlo, Mikulik Petr, Monnier Judith, Morera Solange, McGuinness Cormac, Mueller-Buschbaum Peter, Nielson Martin Meedom, Pietsch Ullrich, Tromp Moniek, Simon Marc, Stangl Julian, Zanotti Giuseppe
    JOURNAL OF SYNCHROTRON RADIATION 21, 638-639 (2014).
    DOI: 10.1107/S1600577514007619
  • The first Symposium on the Scientific Basis of the Nuclear Fuel Cycle Symposium E @ EMRS 13 Editorial note Degueldre Claude, Grimes Robin, Rondinella Vincenzo, Poinssot Christophe, Bosbach Dirk
    PROGRESS IN NUCLEAR ENERGY 72, 1-2 (2014).
    DOI: 10.1016/j.pnucene.2014.02.017
  • X-ray absorption in plutonium uranium mixed oxide fuel: Thorium characterization Cozzo C, Orlov A, Borca C, Degueldre C
    PROGRESS IN NUCLEAR ENERGY 72, 91-95 (2014).
    DOI: 10.1016/j.pnucene.2013.09.009
  • X-ray fluorescence and absorption analysis of krypton in irradiated nuclear fuel Degueldre Claude, Mieszczynski Cyprian, Borca Camelia, Grolimund Daniel, Martin Matthias, Bertsch Johannes
    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS 336, 116-122 (2014).
    DOI: 10.1016/j.nimb.2014.06.021
Top

2013

  • A new mechanism of loop formation and transformation in bcc iron without dislocation reaction Chen J, Gao N, Jung P, Sauvage T
    JOURNAL OF NUCLEAR MATERIALS 441, 216-221 (2013).
    DOI: 10.1016/j.jnucmat.2013.05.074
  • Americium characterization by X-ray fluorescence and absorption spectroscopy in plutonium uranium mixed oxide Degueldre Claude, Cozzo Cedric, Martin Matthias, Grolimund Daniel, Mieszczynski Cyprian
    JOURNAL OF SOLID STATE CHEMISTRY 202, 315-319 (2013).
    DOI: 10.1016/j.jssc.2013.03.048
  • Analysis of long-lived radionuclides produced by proton irradiation in lead targets - gamma-measurements Lorenz T, Dai Y, Schumann D
    RADIOCHIMICA ACTA 101, 661-666 (2013).
    DOI: 10.1524/ract.2013.2067
  • Analysis of the magnetic corrosion product deposits on a boiling water reactor cladding Orlov Andrey, Degueldre Claude, Kaufmann Wilfried
    JOURNAL OF SOLID STATE CHEMISTRY 197, 460-465 (2013).
    DOI: 10.1016/j.jssc.2012.08.030
  • Characterisation of Pt Nanoparticles on Oxide Substrate by Replica Technique in TEM Veleva L, Grundler PV, Abolhassani-Dadras S, Ritter S
    Int. Multidisciplinary Microscopy Congress (InterM 2013), October 10-13, Antalya, Turkey , (2013).
  • Characterization method of dielectric properties of free falling drops in a microwave processing cavity and its application in microwave internal gelation Cabanes-Sempere M, Catala-Civera J M, Penaranda-Foix F L, Cozzo C, Vaucher S, Pouchon M A
    MEASUREMENT SCIENCE & TECHNOLOGY 24, 095009 (2013).
    DOI: 10.1088/0957-0233/24/9/095009
  • Corrosion and Hydrogen Uptake in Zirconium Claddings Irradiated in Light Water Reactors Abolhassani S, Bart G, Bertsch J, Degueldre C, 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 HH
    ASTM 17th International Symposium on Zirconium in the Nuclear Industry, February 3-7, Hyderabad, India , (2013).
  • Crack Initiation in Austenitic Stainless Steel due to Cyclic Thermal Shocks and Biaxial Preload Niffenegger M, Niceno B, Sharabi M, Janssens K, Reichlin K
    SMiRT-22, August 18-23, San Francisco, California, USA , (2013).
  • Curium analysis in plutonium uranium mixed oxide by x-ray fluorescence and absorption fine structure spectroscopy Degueldre C, Borca C, Cozzo C
    TALANTA 115, 986-991 (2013).
    DOI: 10.1016/j.talanta.2013.06.021
  • Current Measurements During Scratching of Low-Alloy Steel in Simulated BWR Environment Ritter S, Seifert HP
    Annual Meeting of the European Cooperative Group on Corrosion Monitoring of Nuclear Materials, June 10-11, Paris, France CD-ROM, (2013).
  • Cyclic deformation response of AISI 316L at room temperature: Mechanical behaviour, microstructural evolution, physically-based evolutionary constitutive modelling Pham M S, Holdsworth S R, Janssens K G F, Mazza E
    INTERNATIONAL JOURNAL OF PLASTICITY 47, 143-164 (2013).
    DOI: 10.1016/j.ijplas.2013.01.017
  • Cyclic mechanical behavior of 316L: Uniaxial LCF and strain-controlled ratcheting tests Facheris G, Janssens K G F
    NUCLEAR ENGINEERING AND DESIGN 257, 100-108 (2013).
    DOI: 10.1016/j.nucengdes.2013.01.010
  • Detection of SCC initiation in austenitic stainless steel by electrochemical noise measurements Ritter S, Seifert H -P
    MATERIALS AND CORROSION-WERKSTOFFE UND KORROSION 64, 683-690 (2013).
    DOI: 10.1002/maco.201206700
  • Determination of the critical resolved shear stress and the friction stress in austenitic stainless steels by compression of pillars extracted from single grains Monnet Ghiath, Pouchon Manuel A
    MATERIALS LETTERS 98, 128-130 (2013).
    DOI: 10.1016/j.matlet.2013.01.118
  • Direct Observation of Thermal Relaxation in Artificial Spin Ice Farhan A, Derlet PM, Kleibert A, Balan A, Chopdekar R, Wyss A, Perron J, Scholl A, Nolting F, Heyderman LJ
    PHYSICAL REVIEW LETTERS 111, 057204 (2013).
    DOI: 10.1103/PhysRevLett.111.057204
  • Effect of Flow and Surface Structure on the Pt Deposition on Stainless Steel During Simulated Noble Metal Applications Grundler PV, Ramar A, Veleva L, Guenther-Leopold I, Ritter S
    16th Int. Conference on Environmental Degradation of Materials in Nuclear Systems - Water Reactors, NACE/TMS/ANS, August 11-15, Asheville, NC, USA , (2013).
  • Effect of correlated input parameters on the failure probability of pipelines with corrosion defects by using FITNET FFS procedure Qian Guian, Niffenegger Markus, Zhou Wenxing, Li Shuxin
    INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING 105, 19-27 (2013).
    DOI: 10.1016/j.ijpvp.2013.02.004
  • Effect of ion-irradiation on the microstructure and microhardness of the W-2Y(2)O(3) composite materials fabricated by sintering and hot forging Battabyal M, Spaetig P, Baluc N
    FUSION ENGINEERING AND DESIGN 88, 1668-1672 (2013).
    DOI: 10.1016/j.fusengdes.2013.03.060
  • Effect of warm pre-stressing on fracture toughness of Eurofer97 steel Ilchuk N, Commin L, Spaetig P, Odette G R
    FUSION ENGINEERING AND DESIGN 88, 644-647 (2013).
    DOI: 10.1016/j.fusengdes.2013.05.056
  • Electron energy loss spectroscopy investigation through a nano ablated uranium dioxide sample Degueldre Claude, Schaeublin Robin, Krbanjevic Julijana, Minikus Eugenia
    TALANTA 106, 408-413 (2013).
    DOI: 10.1016/j.talanta.2013.01.023
  • Environmental Assisted Fatigue in Austenitic Stainless Steels under BWR/HWC & PWR Conditions Seifert HP, Ritter S, Leber HJ, Schachermayer M
    Annual Meeting of the Int. Cooperative Group on Environmentally Assisted Cracking of Water Reactor Materials, May 19-24, Karuizawa, Japan CD-ROM, (2013).
  • Fracture toughness characterization in the lower transition of neutron irradiated Eurofer97 steel Ilchuk N, Spaetig P, Odette G R
    JOURNAL OF NUCLEAR MATERIALS 442, S58-S61 (2013).
    DOI: 10.1016/j.jnucmat.2013.01.002
  • From Safe Design to Residual Life Assessments Hoffelner W
    MATERIALS FOR NUCLEAR PLANTS , (2013).
    DOI: 10.1007/978-1-4471-2915-8
  • Helium embrittlement of a lamellar titanium aluminide Magnusson P, Chen J, Jung P, Sauvage T, Hoffelner W, Spaetig Ph
    JOURNAL OF NUCLEAR MATERIALS 434, 252-258 (2013).
    DOI: 10.1016/j.jnucmat.2012.11.031
  • Improved Thermoelectric Diagnostics of Material Embrittlement Niffenegger M
    IGRDM 17 Meeting , (2013).
  • In-situ bi-axial mechanical testing at POLDI Repper J, Niffenegger M, Van Petegem S, Wagner W, Van Swygenhoven H
    ICNS 2013, July 9-12, Edingburgh, GB , (2013).
  • In-situ multi-axial mechanical testing at POLDI Repper J, Niffenegger M, Van Petegem S, Wagner W, Van Swygenhoven H
    EUROMAT 2013, September 8-13, Sevilla, Spain , (2013).
  • Influence of reference electrode distance and hydrogen content on electrochemical potential noise during SCC in high purity, high temperature water Ritter S, Seifert H -P
    CORROSION ENGINEERING SCIENCE AND TECHNOLOGY 48, 199-206 (2013).
    DOI: 10.1179/1743278212Y.0000000061
  • Integrity analysis of a reactor pressure vessel subjected to pressurized thermal shocks by considering constraint effect Qian Guian, Niffenegger Markus
    ENGINEERING FRACTURE MECHANICS 112, 14-25 (2013).
    DOI: 10.1016/j.engfracmech.2013.09.009
  • Irradiation creep and microstructural changes of ODS steels of different Cr-contents during helium implantation under stress Chen J, Jung P, Henry J, de Carlan Y, Sauvage T, Duval F, Barthe M F, Hoffelner W
    JOURNAL OF NUCLEAR MATERIALS 437, 432-437 (2013).
    DOI: 10.1016/j.jnucmat.2013.02.071
  • Irradiation creep of candidate materials for advanced nuclear plants Chen J, Jung P, Hoffelner W
    JOURNAL OF NUCLEAR MATERIALS 441, 688-694 (2013).
    DOI: 10.1016/j.jnucmat.2013.04.024
  • Methods of advanced waste conditioning by microwave internal gelation: Set-up development and modelling Cozzo C, Cabanes-Sempere M, Pouchon MA
    Product Partitioning and Transmutation, September 24-27, 2012, Prague, Czech Republic , 245 (2013).
  • Microscopic analysis of the influence of ratcheting on the evolution of dislocation structures observed in AISI 316L stainless steel during low cycle fatigue Facheris G, Pham M -S, Janssens K G F, Holdsworth S R
    MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING 587, 1-11 (2013).
    DOI: 10.1016/j.msea.2013.08.041
  • Microstructure and mechanical properties of a W-2wt.%Y2O3 composite produced by sintering and hot forging Battabyal M, Schaeublin R, Spaetig P, Walter M, Rieth M, Baluc N
    JOURNAL OF NUCLEAR MATERIALS 442, S225-S228 (2013).
    DOI: 10.1016/j.jnucmat.2013.01.301
  • Neutron Imaging Investigations of the Hydrogen Related Degradation of the Mechanical Properties of Zircaloy-4 Cladding Tubes Grosse M, Valance S, Stuckert J, Steinbrueck M, Walter M, Kaestner A, Hartmann S, Santisteban J
    MRS Meeting 1528, mrsf12-1528-vv07-05 (2013).
    DOI: 10.1557/opl.2013.364
  • On determination of the constitutive behavior of tempered martensitic steels from micro-indentations: Application to Eurofer97 steel Spaetig P, Ilchuk N
    JOURNAL OF NUCLEAR MATERIALS 442, S869-S872 (2013).
    DOI: 10.1016/j.jnucmat.2013.01.003
  • Oxidation behaviour of zirconium alloys and their precipitates - A mechanistic study Proff C, Abolhassani S, Lemaignan C
    JOURNAL OF NUCLEAR MATERIALS 432, 222-238 (2013).
    DOI: 10.1016/j.jnucmat.2012.06.026
  • Platinum Deposition on Boiling Water Reactor Components: Qualification of Lab-Scale Tests with Plant Data Ritter S, Grundler PV, Ramar A, Ledergerber G, Kaufmann W
    EUROCORR, EFC, September 1-5, Estoril, Portugal CD-ROM, (2013).
  • Power and thermal study of a single drop heated while passing through a TE10p rectangular cavity Cabanes-Sempere M, Canos AJ, Catala-Civera JM, Penaranda-Foix FL, Cozzo C, Pouchon MA
    International Microwave Symposium (IMS 2013), Seattle, WA, USA , 1 (2013).
    DOI: 10.1109/MWSYM.2013.6697661
  • Predictions of TiO2-driven migration of Se(IV) based on an integrated study of TiO2 colloid stability and Se(IV) surface adsorption Benedicto Ana, Missana Tiziana, Degueldre Claude
    SCIENCE OF THE TOTAL ENVIRONMENT 449, 214-222 (2013).
    DOI: 10.1016/j.scitotenv.2013.01.058
  • Probabilistic leak-before-break analysis with correlated input parameters Qian Guian, Niffenegger Markus, Karanki Durga Rao, Li Shuxin
    NUCLEAR ENGINEERING AND DESIGN 254, 266-271 (2013).
    DOI: 10.1016/j.nucengdes.2012.10.005
  • Procedures, methods and computer codes for the probabilistic assessment of reactor pressure vessels subjected to pressurized thermal shocks Qian Guian, Niffenegger Markus
    NUCLEAR ENGINEERING AND DESIGN 258, 35-50 (2013).
    DOI: 10.1016/j.nucengdes.2013.01.030
  • Pt Deposition Behaviour on Stainless Steel under BWR Conditions - Part I: Lab Results & Part II: Results from Specimens Exposed in KKL Ritter S, Grundler PV, Ramar A, Veleva L, Guenther-Leopold I, Seifert HP
    Annual Meeting of the Int. Cooperative Group on Environmentally Assisted Cracking of Water Reactor Materials, May 19-24, Karuizawa, Japan CD-ROM, (2013).
  • Recent progress of R&D activities on reduced activation ferritic/martensitic steels Huang Q, Baluc N, Dai Y, Jitsukawa S, Kimura A, Konys J, Kurtz R J, Lindau R, Muroga T, Odette G R, Raj B, Stoller R E, Tan L, Tanigawa H, Tavassoli A -A F, Yamamoto T, Wan F, Wu Y
    JOURNAL OF NUCLEAR MATERIALS 442, S2-S8 (2013).
    DOI: 10.1016/j.jnucmat.2012.12.039
  • SCC 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
    16th Int. Conference on Environmental Degradation of Materials in Nuclear Systems - Water Reactors, NACE/TMS/ANS, August 11-15, Asheville, NC, USA , (2013).
  • SCC Behaviour 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
    Annual Meeting of the Int. Cooperative Group on Environmentally Assisted Cracking of Water Reactor Materials, May 19-24, Karuizawa, Japan CD-ROM, (2013).
  • Suggestion of a novel failure tolerant fuel element Pouchon MA, Chen J
    Increased Accident Tolerance of Fuels for Light Water Reactors, December 10-12, 2012, Issy-les-Moulineaux, France NEA/NSC/DOC(2013)9, 35 (2013).
  • The investigation of materials related to nuclear technologies by means of neutron imaging methods Lehmann EH, Vontobel P, Grosse M, Bertsch J, Valance S, Zboray Z
    ESS Symposium: "Neutrons for Futures Energy Strategies" , (2013).
  • The proto-Earth geo-reactor: a thorium reactor? Degueldre C, Fiorina C
    ThEC13: Thorium Energy Conference, October 27-31, 2013, CERN, Geneva, Switzerland , (2013).
  • Thermo-Mechanical and Isothermal Low-Cycle Fatigue Behavior of Type 316L Stainless Steel in High-Temperature Water and Air Leber Hans J, Ritter Stefan, Seifert Hans-Peter
    CORROSION 69, 000179 (2013).
    DOI: 10.5006/0875
  • Very high Temperature Reactor (VHTR) System Fu L, Futterer M, de Groot S, Sadhankar R, Carre F, Tachibana Y, Kim YW, Pouchon MA, Sink C
    GIF Symposium, November 14-15, 2012, San Diego, CA, USA 7141, 57 (2013).
  • XFEM applications for integrity analysis of Reactor Pressure Vessels cracked walls Gonzalez Albuixech VF, Qian G, Niffenegger M
    2nd International Workshop on Physics-Based Modeling of Material Properties and Experimental Observations with special focus on Fracture and Damage Mechanics, May 15-17, Antalya, Turkey , (2013).
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2012

  • 5.06 - Corrosion and Environmentally-Assisted Cracking of Carbon and Low-Alloy Steels Seifert HP, Hickling J, Lister D
    In: Konings R.J.M., (ed.) Comprehensive Nuclear Materials, Amsterdam: Elsevier, 5, 105 (2012).
    DOI: 10.1016/B978-0-08-056033-5.00081-1
  • A comparative study on the compatibility of liquid lead-gold eutectic and liquid lead-bismuth eutectic with T91 and SS 316LN steels Dai Y, Gao W, Zhang T, Platacis E, Heinitz S, Thomsen K
    JOURNAL OF NUCLEAR MATERIALS 431, 113-119 (2012).
    DOI: 10.1016/j.jnucmat.2012.04.015
  • A non-local formulation for level-set modelling Valance S
    European Journal of Computational Mechanics 21, 385 (2012).
    DOI: 10.1080/17797179.2012.740588
  • A numerical setup for the study of configurational forces driven interfaces Valance S
    ECCOMAS, September 10-14, Vienna, Austria CD-ROM, (2012).
  • Application of electrochemical noise to monitor stress corrosion cracking of stainless steel in tetrathionate solution under constant load Breimesser Mathias, Ritter Stefan, Seifert Hans-Peter, Suter Thomas, Virtanen Sannakaisa
    CORROSION SCIENCE 63, 129-139 (2012).
    DOI: 10.1016/j.corsci.2012.05.017
  • Application of the electrochemical microcapillary technique to study intergranular stress corrosion cracking of austenitic stainless steel on the micrometre scale Breimesser Mathias, Ritter Stefan, Seifert Hans-Peter, Virtanen Sannakaisa, Suter Thomas
    CORROSION SCIENCE 55, 126-132 (2012).
    DOI: 10.1016/j.corsci.2011.10.011
  • Colloid generation during water flow transients Degueldre Claude, Benedicto Ana
    APPLIED GEOCHEMISTRY 27, 1220-1225 (2012).
    DOI: 10.1016/j.apgeochem.2012.01.017
  • Comparison of Micro- and Macroscopic EN Measurements to Detect Ig SCC in Austenitic Stainless Steel: Final Results Breimesser M, Ritter S, Seifert HP
    Annual Meeting of the European Cooperative Group on Corrosion Monitoring of Nuclear Materials, June 18-19, Petten, The Netherlands CD-ROM, (2012).
  • Comparison of Micro- and Macroscopic Electrochemical Noise Measurements During SCC of Austenitic Stainless Steel Breimesser M, Ritter S, Seifert HP, Suter T, Virtanen S
    10th Symp. on Electrochemical Methods in Corrosion Research, November 18-23, Maragogi-AI, Brazil , (2012).
  • Corrosion fatigue crack growth behaviour of austenitic stainless steels under light water reactor conditions Seifert H P, Ritter S, Leber N J
    CORROSION SCIENCE 55, 61-75 (2012).
    DOI: 10.1016/j.corsci.2011.10.005
  • Corrosion fatigue initiation and short crack growth behaviour of austenitic stainless steels under light water reactor conditions Seifert H P, Ritter S, Leber H J
    CORROSION SCIENCE 59, 20-34 (2012).
    DOI: 10.1016/j.corsci.2012.02.008
  • Corrosion monitoring in nuclear systems Ritter Stefan, Molander Anders
    CORROSION ENGINEERING SCIENCE AND TECHNOLOGY 47, 473-473 (2012).
    DOI: 10.1179/1478422X12Z.00000000089
  • Corrosion monitoring techniques for detection of crack initiation under simulated light water reactor conditions Ritter S, Horner D A, Bosch R-W
    CORROSION ENGINEERING SCIENCE AND TECHNOLOGY 47, 251-264 (2012).
    DOI: 10.1179/1743278212Y.0000000008
  • Delayed hydride cracking in Zircaloy-2 fuel cladding tubes Namburi HK, Valance S, Bertsch J
    TopFuel 2012: Reactor Fuel Performance , (2012).
  • Deterministic and Probabilistic Analysis of a Reactor Pressure Vessel (RPV) subjected to Pressurized Thermal Shocks (PTS) Qian G, Niffenegger M
    5th International Conference on Engineering Failure Analysis, July 1-4, The Hague, The Netherlands , (2012).
  • Effect of Injection Rate on Platinum Deposition Behaviour on Stainless Steel under Simulated BWR Conditions Grundler PV, Ramar A, Karastoyanov V, Abolhassani-Dadras S, Guenther-Leopold I, Kivel N, Ritter S
    Nuclear Plant Chemistry (NPC) Conference 2012, SFEN, September 24-28, Paris, France CD-ROM, Paper Nr. 116 P1-46 (2012).
  • Effect of Load Ratio ("Mean Stress") on Corrosion Fatigue Initiation & Short Crack Growth from Sharply Notched Specimens in Austenitic SS under BWR/HWC Conditions Siefert HP, Ritter S, Leber HJ
    Annual Meeting of the Int. Cooperative Group on Environmentally Assisted Cracking of Water Reactor Materials, May 13-18, Quebec City, Canada CD-ROM, (2012).
  • Effect of Pt injection rate on corrosion potential and Pt distribution on stainless steel under simulated boiling water reactor conditions Ramar A, Grundler P V, Karastoyanov V, Guenther-Leopold I, Abolhassani-Dadras S, Kivel N, Ritter S
    CORROSION ENGINEERING SCIENCE AND TECHNOLOGY 47, 489-497 (2012).
    DOI: 10.1179/1743278212Y.0000000031
  • FeCrAlY and TiN coatings on T91 steel after irradiation with 72 MeV protons in flowing LBE Dai Y, Boutellier V, Gavillet D, Glasbrenner H, Weisenburger A, Wagner W
    JOURNAL OF NUCLEAR MATERIALS 431, 66-76 (2012).
    DOI: 10.1016/j.jnucmat.2011.11.006
  • General dislocation image stress of anisotropic cubic thin film Wu W, Schaeublin R, Chen J
    JOURNAL OF APPLIED PHYSICS 112, 093522 (2012).
    DOI: 10.1063/1.4764341
  • Guideline for an assessment of electrochemical noise measurement devices Ritter S, Huet F, Cottis R A
    MATERIALS AND CORROSION-WERKSTOFFE UND KORROSION 63, 297-302 (2012).
    DOI: 10.1002/maco.201005839
  • Hydrides re-orientation and metallography analysis of 6 cycles irradiated fuelcaldding samples Zubler R, Valance S, Urech A
    HOTLAB Conference, September 24-26, Marcoule, France , (2012).
  • Influence of Reference Electrode Distance on the Electrochemical Potential Noise During SCC in High-Purity, High-Temperature Water Ritter S, Seifert HP
    EUROCORR, EFC, September 9-13, Istanbul, Turkey CD-ROM, (2012).
  • Innovative production of nuclear fuel by microwave internal gelation: Heat transfer model of falling droplets Cabanes-Sempere M, Cozzo C, Vaucher S, Catala-Civera J M, Pouchon M A
    PROGRESS IN NUCLEAR ENERGY 57, 111-116 (2012).
    DOI: 10.1016/j.pnucene.2011.12.011
  • Investigation of fuel crud by means of ICP-MS and TEM Guenther Leopold I, Krois M, Kobler Waldis J, Linder H P, Abolhassani S
    PROCEDIA CHEMISTRY 7, 673 (2012).
    DOI: 10.1016/j.proche.2012.10.102
  • Investigation of irradiated uranium-plutonium mixed oxide fuel by synchrotron based micro X-ray diffraction Mieszczynski C, Degueldre C, Kuri G, Bertsch J, Borca C N
    PROGRESS IN NUCLEAR ENERGY 57, 130-137 (2012).
    DOI: 10.1016/j.pnucene.2011.11.012
  • Investigation of liquid LBE embrittlement effects on irradiated ferritic/martensitic steels by slow-strain-rate tensile tests Long B, Dai Y, Baluc N
    JOURNAL OF NUCLEAR MATERIALS 431, 85-90 (2012).
    DOI: 10.1016/j.jnucmat.2011.11.036
  • Meso-scale analysis of the creep behavior of hydrogenated Zircaloy-4 Mallipudi VenkatRao, Valance Stephane, Bertsch Johannes
    MECHANICS OF MATERIALS 51, 15-28 (2012).
    DOI: 10.1016/j.mechmat.2012.03.003
  • Modeling of Sphere-Pac Fuel Pouchon MA, Nordstroem LA, Hellwig C
    In: Konings R.J.M., (ed.) Comprehensive Nuclear Materials, Amsterdam: Elsevier, 3, 789-817 (2012).
    DOI: 10.1016/B978-0-08-056033-5.00129-4
  • Multi-axial in-situ mechanical testing on the time-of-flight neutron strain scanner POLDI Repper J, Niffenegger M
    MSE 2012, September 25-27, Darmstadt, Germany , (2012).
  • Nanocomposites of carbon nanotubes embedded in a (Ti,Al)N coated film Marot L, de los Arcos T, Buenzli A M, Waeckerlin C, Steiner R, Oelhafen P, Meyer E, Mathys D, Spaetig P, Covarel G
    SURFACE & COATINGS TECHNOLOGY 212, 223-228 (2012).
    DOI: 10.1016/j.surfcoat.2012.09.053
  • Noble Metal Deposition Behavior in BWRs - the NORA Research Project and Preliminary Results Ramar A, Karastoyanov V, Ritter S, Grundler PV, Guenther-Leopold I, Kivel N, Abolhassani-Dadras S
    3D Symposium of the Swiss Society for Optics and Microscopy SSOM, March 5-8, Les Diablerets, Switzerland , (2012).
  • On-Line NobleChemTM - Operating Experience and Lab Investigations Ledergerber G, Ritter S, Kaufmann W, Grundler PV, Ramar A
    Int. Boiling Water Reactor and Pressurized Water Reactor Materials Reliability Program Conference and Exhibition, 2012, EPRI, July 16-19, Maryland, USA , (2012).
  • Platinum Deposition Behavour on Stainless Steel under Varying Water Chemistry in Simulated BWR Conditions Ramar A, Grundler PV, Karastoyanov V, Abolhassani-Dadras S, Guenther-Leopold I, Kivel N, Ritter S
    Nuclear Plant Chemistry (NPC) Conference 2012, SFEN, September 24-28, Paris, France CD-ROM, Paper No. 116 P1-45 (2012).
  • Positron annihilation lifetime measurements of austenitic stainless and ferritic/martensitic steels irradiated in the SINQ target irradiation program Sato K, Xu Q, Yoshiie T, Dai Y, Kikuchi K
    JOURNAL OF NUCLEAR MATERIALS 431, 52-56 (2012).
    DOI: 10.1016/j.jnucmat.2011.11.015
  • Probabilistic assessment of pipelines containing corrosion defects with correlated input parameters based on FITNET FFS procedure Qian G, Niffenegger M
    1st International Conference of the International Journal of Structural Integrity, June 25-28, Porto Portugal CD-ROM, (2012).
  • Pt Nanoparticles to Mitigate Stress Corrosion Cracking in Boiling Water Reactors Grundler PV, Ramar A, Abolhassani-Dadras S, Guenther-Leopold I, Ritter S
    2012 Fall Meeting of the Swiss Chemical Society, September 13, Zuerich, Switzerland , (2012).
  • Sphere-Pac and VIPAC Fuel Pouchon MA, Ledergerber G, Ingold F, Bakker K
    In: Konings R.J.M., (ed.) Comprehensive Nuclear Materials, Amsterdam: Elsevier, 3, 275-312 (2012).
    DOI: 10.1016/B978-0-08-056033-5.00059-8
  • Tensile mechanical properties of a stainless steel irradiated up to 19 dpa in the Swiss spallation neutron source Saito Shigeru, Kikuchi Kenji, Hamaguchi Dai, Usami Kouji, Endo Shinya, Ono Katsuto, Matsui Hiroki, Kawai Masayoshi, Dai Yong
    JOURNAL OF NUCLEAR MATERIALS 431, 44-51 (2012).
    DOI: 10.1016/j.jnucmat.2011.11.028
  • Tensile strained Ge quantum wells on Si substrate: Post-growth annealing versus low temperature re-growth Suess MJ, Carroll L, Sigg H, Diaz A, Chrastina D, Isella G, Muller E, Spolenak R
    MATERIALS SCIENCE AND ENGINEERING B-ADVANCED FUNCTIONAL SOLID-STATE MATERIALS 177, 696-699 (2012).
    DOI: 10.1016/j.mseb.2011.10.009
  • The Effects of Helium in Irradiated Structural Alloys Dai Y, Odette G R, Yamamoto T
    In: Konings R.J.M., (ed.) Comprehensive Nuclear Materials, Amsterdam: Elsevier, 1, 141 (2012).
    DOI: 10.1016/B978-0-08-056033-5.00006-9
  • The fourth SINQ Target Irradiation Program, STIP-IV Dai Y, Brun R, Gao W, Geissmann K, Hahl S, Hou H, Huang Y, Linder H P, Long B, Spahr A, Vontobel P, Wagner W, Wang H L, Zanini L
    JOURNAL OF NUCLEAR MATERIALS 431, 2-9 (2012).
    DOI: 10.1016/j.jnucmat.2011.11.004
  • The influence of Cr-composition on the local magnetic structure of FeCr alloys Idhil A, Borca C N, Uldry A -C, Zema N, Turchini S, Catone D, Foelske A, Grolimund D, Samaras M
    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS 284, 1-5 (2012).
    DOI: 10.1016/j.nimb.2011.08.071
  • The proper use of thermal expansion coefficients in finite element calculations Niffenegger Markus, Reichlin Klaus
    NUCLEAR ENGINEERING AND DESIGN 243, 356-359 (2012).
    DOI: 10.1016/j.nucengdes.2011.12.006
  • Thermodynamic modeling of the processes in a boiling water reactor to buildup the magnetic corrosion product deposits Orlov Andrey, Kulik Dmitrii A, Degueldre Claude, Oliver Lena
    CORROSION SCIENCE 64, 28-36 (2012).
    DOI: 10.1016/j.corsci.2012.06.022
  • Ti-44, Al-26 and Mn-53 samples for nuclear astrophysics: the needs, the possibilities and the sources Dressler R, Ayranov M, Bemmerer D, Bunka M, Dai Y, Lederer C, Fallis J, Murphy A StJ, Pignatari M, Schumann D, Stora T, Stowasser T, Thielemann F-K, Woods P J
    JOURNAL OF PHYSICS G-NUCLEAR AND PARTICLE PHYSICS 39, 105201 (2012).
    DOI: 10.1088/0954-3899/39/10/105201
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