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Using genetic programming and the stress equilibrium method to obtain the un-stressed lattice parameter for calculating residual stresses

Journal of materials research and technology, 2023-03, Vol.23, p.1543-1558

2023

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Plastic strain characterization in austenitic stainless steels and nickel alloys by electron backscatter diffraction

Journal of nuclear materials, 2011-09, Vol.416 (1), p.75-79

2011

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European Research Program on Supercritical Water-Cooled Reactor

Journal of nuclear engineering and radiation science, 2021-04, Vol.7 (2)

2021

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Surface Characterization and Electrochemical Behavior of AISI 316l Stainless Steel Machined with Green Supercritical CO2 Coolant

Journal of materials engineering and performance, 2024-04, Vol.33 (8), p.3811-3826

2024

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The reproducibility of corrosion testing in supercritical water—Results of a second international interlaboratory comparison exercise

Journal of nuclear materials, 2022-07, Vol.565, p.153759, Article 153759

2022

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Oxidation of austenitic and ferritic/martensitic alloys in supercritical water

The Journal of supercritical fluids, 2013-06, Vol.78, p.103-113

2013

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Stress corrosion cracking behavior of annealed and cold worked 316L stainless steel in supercritical water

Nuclear engineering and design, 2016-10, Vol.307, p.30-38

2016

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The reproducibility of corrosion testing in supercritical water—Results of an international interlaboratory comparison exercise

Corrosion science, 2016-05, Vol.106, p.147-156

2016

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AES characterization of oxide films formed on nickel-base alloys at Supercritical Water Reactor (SCWR) conditions

Surface and interface analysis, 2016-07, Vol.48 (7), p.680-684

2016

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Prediction of microscopic residual stresses using genetic programming

Applications in engineering science, 2023-09, Vol.15, p.100141, Article 100141

2023

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Effect of surface machining on the environmentally-assisted cracking of Alloy 182 and 316L stainless steel in light water reactor environments: results of the collaborative project MEACTOS

Corrosion reviews, 2023-10, Vol.41 (5), p.545-564

2023

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Special Issue: Behavior of Materials (Alloys, Coatings) in Conditions Specific to Gen IV Nuclear Reactors

Coatings (Basel), 2023-01, Vol.13 (1), p.58

2023

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Microstructure Study of NiCrAlY and FeCrAlY Exposed to Superheated Steam at 800 °C

Journal of nuclear engineering and radiation science, 2018-01, Vol.4 (1)

2018

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Influence of Changes in Pressure and Temperature of Supercritical Water on the Susceptibility to Stress Corrosion Cracking of 316L Austenitic Stainless Steel

Journal of nuclear engineering and radiation science, 2017-01, Vol.3 (1)

2017

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Using Genetic Programing and the Stress Equilibrium Method to Obtainthe Un-Stressed Lattice Parameter for Calculating Residual Stresses

SSRN Electronic Journal

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Using genetic programming and the stress equilibrium method to obtain the un-stressed lattice parameter for calculating residual stresses

Plastic strain characterization in austenitic stainless steels and nickel alloys by electron backscatter diffraction

European Research Program on Supercritical Water-Cooled Reactor

Surface Characterization and Electrochemical Behavior of AISI 316l Stainless Steel Machined with Green Supercritical CO2 Coolant

The reproducibility of corrosion testing in supercritical water—Results of a second international interlaboratory comparison exercise

Oxidation of austenitic and ferritic/martensitic alloys in supercritical water

Stress corrosion cracking behavior of annealed and cold worked 316L stainless steel in supercritical water

The reproducibility of corrosion testing in supercritical water—Results of an international interlaboratory comparison exercise

AES characterization of oxide films formed on nickel-base alloys at Supercritical Water Reactor (SCWR) conditions

Prediction of microscopic residual stresses using genetic programming

Effect of surface machining on the environmentally-assisted cracking of Alloy 182 and 316L stainless steel in light water reactor environments: results of the collaborative project MEACTOS

Special Issue: Behavior of Materials (Alloys, Coatings) in Conditions Specific to Gen IV Nuclear Reactors

Microstructure Study of NiCrAlY and FeCrAlY Exposed to Superheated Steam at 800 °C

Influence of Changes in Pressure and Temperature of Supercritical Water on the Susceptibility to Stress Corrosion Cracking of 316L Austenitic Stainless Steel

Using Genetic Programing and the Stress Equilibrium Method to Obtainthe Un-Stressed Lattice Parameter for Calculating Residual Stresses

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