P. Efsing

发表

Radiation Induced Solute Clustering in High-Ni Reactor Pressure Vessel Steel

N. Castin, G. Bonny, L. Malerba, 2019, Acta Materialia.

Radiation Induced Solute Clustering in High-Ni Reactor Pressure Vessel Steel

N. Castin, G. Bonny, L. Malerba, 2019, SSRN Electronic Journal.

Analysis of thermal embrittlement of a low alloy steel weldment using fracture toughness and microstructural investigations

M. Thuvander, K. Lindgren, J. Faleskog, 2022, Engineering Fracture Mechanics.

Extended Mechanical Testing of RPV Surveillance Materials Using Reconstitution Technique for Small Sized Specimen to Assist Long Term Operation

P. Efsing, J. May, J. Roudén, 2014 .

An experimental-numerical screening method for assessing environmentally assisted degradation in high strength steels

A. Halilović, J. Faleskog, P. Efsing, 2021 .

Nano-cavities observed in a 316SS PWR flux thimble tube irradiated to 33 and 70 dpa

F. Garner, D. Edwards, S. Bruemmer, 2009 .

On the Analysis of Clustering in an Irradiated Low Alloy Reactor Pressure Vessel Steel Weld

K. Stiller, M. Thuvander, K. Lindgren, 2017, Microscopy and Microanalysis.

A generalized probabilistic model for cleavage fracture with a length scale – Influence of stress state and application to surface cracked experiments

J. Faleskog, P. Efsing, Magnus Boåsen, 2019, Engineering Fracture Mechanics.

Experimental and Theoretical Investigation of Three Alloy 690 Mockup Components: Base Metal and Welding Induced Changes

P. Efsing, B. Kaplan, Rickard Shen, 2014 .

Cluster formation in in-service thermally aged pressurizer welds

K. Stiller, M. Thuvander, K. Lindgren, 2018, Journal of Nuclear Materials.

Electrochemical investigation of in-service thermal aging in two CF8M cast stainless steels

U. Ehrnstén, P. Efsing, M. Ivanchenko, 2019, Journal of Nuclear Materials.

Brittle fracture initiation in decommissioned boiling water reactor pressure vessel head weld

M. Lindroos, Z. Que, P. Efsing, 2022, Journal of Nuclear Materials.

On flux effects in a low alloy steel from a Swedish reactor pressure vessel

U. Ehrnstén, P. Efsing, Magnus Boåsen, 2017 .

Post-irradiation annealing of Ni–Mn–Si-enriched clusters in a neutron-irradiated RPV steel weld using Atom Probe Tomography

M. G. Burke, D. Parfitt, P. Efsing, 2015 .

Atom probe tomography characterizations of high nickel, low copper surveillance RPV welds irradiated to high fluences

R. Nanstad, P. Efsing, M. K. Miller, 2013 .

Post-Irradiation Annealing of High Flux Irradiated and Surveillance Material Reactor Pressure Vessel Weld Metal

K. Stiller, M. Thuvander, Z. Que, 2022, Journal of Nuclear Materials.

Materials for Sustainable Nuclear Energy: A European Strategic Research and Innovation Agenda for All Reactor Generations

M. Cologna, L. Malerba, M. Rabung, 2022, Energies.

Effect of weld microstructure on brittle fracture initiation in the thermally-aged boiling water reactor pressure vessel head weld metal

Z. Que, U. Ehrnstén, P. Efsing, 2021, International Journal of Minerals, Metallurgy and Materials.

A weakest link model for multiple mechanism brittle fracture — Model development and application

J. Faleskog, P. Efsing, Magnus Boåsen, 2021, Journal of the Mechanics and Physics of Solids.

Analysis of a Defected Dissimilar Metal Weld in a PWR Power Plant

Pål Efsing, J. Lagerström, P. Efsing, 2002 .

CHARACTERIZATION OF DEFECTS IN ALLOY 152, 52 AND 52M WELDS

M. Olszta, S. Bruemmer, M. Toloczko, 2009 .

A duplex oxide cohesive zone model to simulate intergranular stress corrosion cracking

B. Alfredsson, P. Efsing, M. Sedlak, 2020 .

Overcoming the drawbacks of plastic strain estimation based on KAM.

P. Efsing, Rickard Shen, 2018, Ultramicroscopy.

Baseline Examinations and Autoclave Tests of 65 and 100 dpa Flux Thimble Tube O-Ring Specimens

A. Toivonen, P. Efsing, W. Karlsen, 2021 .

Simulation of Slip-Oxidation Process by Mesh Adaptivity in a Cohesive Zone Framework

B. Alfredsson, P. Efsing, M. Sedlak Mosesson, 2021, Materials.

Integrated effect of thermal ageing and low flux irradiation on microstructural evolution of the ferrite of welded austenitic stainless steels

M. Thuvander, K. Lindgren, P. Efsing, 2021, Journal of Nuclear Materials.

Delayed Hydride Cracking in Irradiated Zircaloy Cladding

K. Pettersson, P. Efsing, 2000 .

The Influence of Temperature and Yield Strength on Delayed Hydride Cracking in Hydrided Zircaloy-2

K. Pettersson, P. Efsing, 1996 .

Delayed hydride cracking in irradiated zircaloy

P. Efsing, 1998 .

Round-Robin Testing of Fracture Toughness Characteristics of Thin-Walled Tubing

R. Kuo, R. Adamson, P. Efsing, 2008 .

Spatial correlation between local misorientations and nanoindentation hardness in nickel-base alloy 690

V. Ström, P. Efsing, Rickard Shen, 2016 .

Evolution of precipitation in reactor pressure vessel steel welds under neutron irradiation

K. Stiller, M. Thuvander, K. Lindgren, 2017 .

A cohesive element with degradation controlled shape of the traction separation curve for simulating stress corrosion and irradiation cracking

B. Alfredsson, P. Efsing, M. Sedlak, 2018 .

A sensitivity study using maximum entropy to interpret SANS data from the Ringhals Unit 3 NPP

N. Riddle, P. Efsing, J. Hyde, 2018, Journal of Nuclear Materials.

MICROSTRUCTURAL EVOLUTION IN NEUTRON-IRRADIATED STAINLESS STEELS: COMPARISON OF LWR AND FAST-REACTOR IRRADIATIONS

Pål Efsing, E. Simonen, D. Edwards, 2005 .

Elemental distribution in a decommissioned high Ni and Mn reactor pressure vessel weld metal from a boiling water reactor

M. Thuvander, K. Lindgren, P. Efsing, 2023, Nuclear Materials and Energy.

Mechanical behavior of high-Ni/high-Mn Barsebäck 2 reactor pressure vessel welds after 28 years of operation

Siddharth Suman, P. Efsing, P. Nevasmaa, 2023, Journal of Nuclear Materials.

Flux Effects on Radiation Induced Aging Behaviour of Low Alloy Steel Weld Material with High Nickel and Manganese Content

P. Nilsson, P. Efsing, J. Roudén, 2014 .

Analysis of the Ductile-to-Brittle Transition Temperature Shift in a Commercial Power Plant With High Nickel Containing Weld Material

Christer Jansson, Pål Efsing, C. Jansson, 2007 .

Studies on Delayed Hydride Cracking of Zircaloy Cladding

K. Pettersson, P. Efsing, K. Kese, 2013 .

A coupled diffusion and cohesive zone model for intergranular stress corrosion cracking in 316L stainless steel exposed to cold work in primary water conditions

B. Alfredsson, P. Efsing, M. Sedlak, 2019, Engineering Fracture Mechanics.

Modelling of IG-SCC mechanism at LWR conditions through coupling of a potential-based cohesive model and Fick’s second law

B. Alfredsson, P. Efsing, M. Sedlak, 2015 .

Study of Fusion Boundary Microstructure and Local Mismatch of SA508/Alloy 52 Dissimilar Metal Weld with Buttering

I. Virkkunen, P. Efsing, P. Nevasmaa, 2023, Journal of Nuclear Materials.