Overcoming the drawbacks of plastic strain estimation based on KAM von Shen, Rickard R., Efsing, Pål

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Elemental distribution in a decommissioned high Ni and Mn reactor pressure vessel weld metal from a boiling water reactor von Lindgren, Kristina, Efsing, Pal, Thuvander, Mattias

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An experimental fracture mechanics study of the combined effect of hydrogen embrittlement and loss of constraint von Halilović, Armin E., Faleskog, Jonas, Efsing, Pål

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Brittle fracture initiation in decommissioned boiling water reactor pressure vessel head weld von Que, Zaiqing, Lindroos, Matti, Lydman, Jari, Hytönen, Noora, Lindqvist, Sebastian, Efsing, Pål, Nevasmaa, Pekka, Arffman, Pentti

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Materials for Sustainable Nuclear Energy: A European Strategic Research and Innovation Agenda for All Reactor Generations von Malerba, Lorenzo, Al Mazouzi, Abderrahim, Bertolus, Marjorie, Cologna, Marco, Efsing, Pål, Jianu, Adrian, Kinnunen, Petri, Nilsson, Karl-Fredrik, Rabung, Madalina, Tarantino, Mariano

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Post-irradiation annealing of high flux irradiated and surveillance material reactor pressure vessel weld metal von Lindgren, Kristina, Boåsen, Magnus, Que, Zaiqing, Stiller, Krystyna, Efsing, Pål, Thuvander, Mattias

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Analysis of thermal embrittlement of a low alloy steel weldment using fracture toughness and microstructural investigations von Boåsen, Magnus, Lindgren, Kristina, Öberg, Martin, Thuvander, Mattias, Faleskog, Jonas, Efsing, Pål

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A weakest link model for multiple mechanism brittle fracture — Model development and application von Boåsen, Magnus, Dahlberg, Carl F.O., Efsing, Pål, Faleskog, Jonas

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Cluster formation in in-service thermally aged pressurizer welds von Lindgren, Kristina, Boåsen, Magnus, Stiller, Krystyna, Efsing, Pål, Thuvander, Mattias

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A generalized probabilistic model for cleavage fracture with a length scale – Influence of stress state and application to surface cracked experiments von Boåsen, Magnus, Stec, Mateusz, Efsing, Pål, Faleskog, Jonas

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Simulation of Slip-Oxidation Process by Mesh Adaptivity in a Cohesive Zone Framework von Sedlak Mosesson, Michal, Alfredsson, Bo, Efsing, Pål

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Atom probe tomography characterizations of high nickel, low copper surveillance RPV welds irradiated to high fluences von Miller, M.K., Powers, K.A., Nanstad, R.K., Efsing, P.

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Baseline Examinations and Autoclave Tests of 65 and 100 dpa Flux Thimble Tube O-Ring Specimens von Karlsen, Wade, Toivonen, Aki, Efsing, Pål

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An experimental-numerical screening method for assessing environmentally assisted degradation in high strength steels von Halilović, Armin E., Faleskog, Jonas, Boåsen, Magnus, Efsing, Pål

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On flux effects in a low alloy steel from a Swedish reactor pressure vessel von Boåsen, Magnus, Efsing, Pål, Ehrnstén, Ulla

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On the Analysis of Clustering in an Irradiated Low Alloy Reactor Pressure Vessel Steel Weld von Lindgren, Kristina, Stiller, Krystyna, Efsing, Pål, Thuvander, Mattias

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Effect of weld microstructure on brittle fracture initiation in the thermally-aged boiling water reactor pressure vessel head weld metal von Hytönen, Noora, Que, Zai-qing, Arffman, Pentti, Lydman, Jari, Nevasmaa, Pekka, Ehrnstén, Ulla, Efsing, Pål

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Spatial correlation between local misorientations and nanoindentation hardness in nickel-base alloy 690 von Shen, Rickard R., Ström, Valter, Efsing, Pål

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Nano-cavities observed in a 316SS PWR flux thimble tube irradiated to 33 and 70 dpa von Edwards, D.J., Garner, F.A., Bruemmer, S.M., Efsing, Pål

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Evolution of precipitation in reactor pressure vessel steel welds under neutron irradiation von Lindgren, Kristina, Boåsen, Magnus, Stiller, Krystyna, Efsing, Pål, Thuvander, Mattias

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