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

[1]  Siddharth Suman,et al.  Mechanical behavior of high-Ni/high-Mn Barsebäck 2 reactor pressure vessel welds after 28 years of operation , 2023, Journal of Nuclear Materials.

[2]  M. Lindroos,et al.  Brittle fracture initiation in decommissioned boiling water reactor pressure vessel head weld , 2022, Journal of Nuclear Materials.

[3]  K. Frisk,et al.  Atom probe tomography characterisation of powder forged connecting rods alloyed with vanadium and copper , 2022, Philosophical Magazine.

[4]  K. Stiller,et al.  Post-Irradiation Annealing of High Flux Irradiated and Surveillance Material Reactor Pressure Vessel Weld Metal , 2022, Journal of Nuclear Materials.

[5]  M. Thuvander,et al.  Analysis of thermal embrittlement of a low alloy steel weldment using fracture toughness and microstructural investigations , 2022, Engineering Fracture Mechanics.

[6]  A. Kimura,et al.  Radiation embrittlement of clad-HAZ of RPV of a decommissioned BWR plant , 2021, Journal of Nuclear Materials.

[7]  Z. Que,et al.  Effect of weld microstructure on brittle fracture initiation in the thermally-aged boiling water reactor pressure vessel head weld metal , 2021, International Journal of Minerals, Metallurgy and Materials.

[8]  M. Kirk,et al.  Development of new embrittlement trend curve based on Japanese surveillance and atom probe tomography data , 2021 .

[9]  M. Thuvander,et al.  Integrated effect of thermal ageing and low flux irradiation on microstructural evolution of the ferrite of welded austenitic stainless steels , 2021, Journal of Nuclear Materials.

[10]  Kenta Murakami.  Influence of copper precipitates on clustering behavior of alloying elements observed in Japanese reactor pressure vessel surveillance materials using atom probe tomography , 2020 .

[11]  D. Morgan,et al.  On the Elevated Temperature Thermal Stability of Nanoscale Mn-Ni-Si Precipitates Formed at Lower Temperature in Highly Irradiated Reactor Pressure Vessel Steels , 2019, Scientific Reports.

[12]  E. Kuleshova,et al.  Radiation-Induced Phase Formation in Steels of VVER Reactor Pressure Vessels Containing ~0.3–1.3 wt % Nickel , 2019, Physics of Metals and Metallography.

[13]  N. Castin,et al.  Radiation Induced Solute Clustering in High-Ni Reactor Pressure Vessel Steel , 2019, Acta Materialia.

[14]  Dierk Raabe,et al.  Parameter free quantitative analysis of atom probe data by correlation functions: Application to the precipitation in Al-Zn-Mg-Cu , 2018, Scripta Materialia.

[15]  K. Stiller,et al.  Cluster formation in in-service thermally aged pressurizer welds , 2018, Journal of Nuclear Materials.

[16]  K. Stiller,et al.  Evolution of precipitation in reactor pressure vessel steel welds under neutron irradiation , 2017 .

[17]  U. Ehrnstén,et al.  On flux effects in a low alloy steel from a Swedish reactor pressure vessel , 2017 .

[18]  Gabriel Meric de Bellefon,et al.  60th Anniversary of electricity production from light water reactors: Historical review of the contribution of materials science to the safety of the pressure vessel , 2017 .

[19]  M. G. Burke,et al.  Post-irradiation annealing of Ni–Mn–Si-enriched clusters in a neutron-irradiated RPV steel weld using Atom Probe Tomography , 2015 .

[20]  P. Nilsson,et al.  Flux Effects on Radiation Induced Aging Behaviour of Low Alloy Steel Weld Material with High Nickel and Manganese Content , 2014 .

[21]  R. Chaouadi,et al.  Confirmatory investigations on the flux effect and associated unstable matrix damage in RPV materials exposed to high neutron fluence , 2013 .

[22]  R. Nanstad,et al.  Atom probe tomography characterizations of high nickel, low copper surveillance RPV welds irradiated to high fluences , 2013 .

[23]  M. Thuvander,et al.  Quantitative Evaluation of Spinodal Decomposition in Fe-Cr by Atom Probe Tomography and Radial Distribution Function Analysis , 2013, Microscopy and Microanalysis.

[24]  R. Chaouadi,et al.  Neutron flux and annealing effects on irradiation hardening of RPV materials , 2011 .

[25]  F. Bergner,et al.  Small-angle neutron scattering investigation of as-irradiated, annealed and reirradiated reactor pressure vessel weld material of decommissioned reactor , 2011 .

[26]  A. Ballesteros,et al.  Irradiation temperature, flux and spectrum effects , 2011 .

[27]  B. Radiguet,et al.  Irradiation-Induced Solute Clustering in a Low Nickel FeMnNi Ferritic Alloy , 2011 .

[28]  F. Bergner,et al.  Characterization of neutron-irradiated ferritic model alloys and a RPV steel from combined APT, SANS, TEM and PAS analyses , 2010 .

[29]  Kunio Onizawa,et al.  Effects of chemical composition and dose on microstructure evolution and hardening of neutron-irradiated reactor pressure vessel steels , 2010 .

[30]  Emmanuelle A. Marquis,et al.  Nuclear reactor materials at the atomic scale , 2009 .

[31]  J. Konheiser,et al.  RPV material investigations of the former VVER-440 Greifswald NPP , 2009 .

[32]  F. Bergner,et al.  Flux dependence of cluster formation in neutron-irradiated weld material , 2008, 2008 IEEE Nuclear Science Symposium Conference Record.

[33]  Michael K Miller,et al.  Embrittlement of RPV steels: An atom probe tomography perspective , 2007 .

[34]  Christer Jansson,et al.  Analysis of the Ductile-to-Brittle Transition Temperature Shift in a Commercial Power Plant With High Nickel Containing Weld Material , 2007 .

[35]  Mikhail A. Sokolov,et al.  APT characterization of high nickel RPV steels , 2006 .

[36]  G. D. Smith,et al.  Comparison of the number densities of nanosized Cu-rich precipitates in ferritic alloys measured using EELS and EDX mapping, HREM and 3DAP , 2006 .

[37]  B. Radiguet,et al.  Three‐dimensional atom probe study of irradiated, annealed and re‐irradiated VVER 440 weld metals , 2004 .

[38]  Jonathan M. Hyde,et al.  Microstructural evolution in medium copper low alloy steels irradiated in a pressurized water reactor and a material test reactor , 2003 .

[39]  M. G. Burke,et al.  Microstructural Aspects of Irradiation Damage in A508 Gr 4N Forging Steel: Composition and Flux Effects , 2002 .

[40]  G. E. Lucas,et al.  Recent progress in understanding reactor pressure vessel steel embrittlement , 1998 .

[41]  M. G. Hetherington,et al.  An Analysis of Small Clusters Formed in Thermally Aged and Irradiated FeCu and FeCuNi Model Alloys , 1990 .