UB Paderborn / Katalog / Suche / in CDI

Sortiert nach

Einfacher Volltextzugriff von (fast) überall

Installieren Sie die LibKey Nomad-Browsererweiterung und erhalten Sie von vielen Webseiten einfachen Zugriff auf lizenzierte Volltexte oder Open Access Publikationen. Mehr erfahren...

Corrosion of Zirconium Alloys Used for Nuclear Fuel Cladding

Annual review of materials research, 2015-07, Vol.45 (1), p.311-343

2015

Volltextzugriff (PDF)

Oxidation behavior of ferritic–martensitic and ODS steels in supercritical water

Journal of nuclear materials, 2012-05, Vol.424 (1-3), p.261-276

2012

Volltextzugriff (PDF)

A phase-field model for hydride formation in polycrystalline metals: Application to δ-hydride in zirconium alloys

Acta materialia, 2019-12, Vol.181 (C), p.262-277

2019

Volltextzugriff (PDF)

Modeling and simulation of hydrogen behavior in Zircaloy-4 fuel cladding

Journal of nuclear materials, 2014-09, Vol.452 (1-3), p.311-320

2014

Volltextzugriff (PDF)

Corrosion of ferritic–martensitic steels in steam and supercritical water

Journal of nuclear materials, 2013-10, Vol.441 (1-3), p.604-611

2013

Volltextzugriff (PDF)

Hydrogen in zirconium alloys: A review

Journal of nuclear materials, 2019-05, Vol.518 (1), p.440-460

2019

Volltextzugriff (PDF)

Hydrogen pickup measurements in zirconium alloys: Relation to oxidation kinetics

Journal of nuclear materials, 2014-08, Vol.451 (1-3), p.1-13

2014

Volltextzugriff (PDF)

Transmission electron microscopy characterization of Zircaloy-4 and ZIRLO™ oxide layers

Journal of nuclear materials, 2015-01, Vol.456 (C), p.272-280

2015

Volltextzugriff (PDF)

Implementation and Validation of the Hydride Nucleation-Growth-Dissolution (HNGD) model in BISON

Journal of nuclear materials, 2021-02, Vol.544 (C), p.152683, Article 152683

2021

Volltextzugriff (PDF)

EFTEM and EELS analysis of the oxide layer formed on HCM12A exposed to SCW

Journal of nuclear materials, 2012-11, Vol.430 (1-3), p.171-180

2012

Volltextzugriff (PDF)

In-situ electrochemical impedance spectroscopy measurements of zirconium alloy oxide conductivity: Relationship to hydrogen pickup

Corrosion science, 2017-05, Vol.119, p.1-13

2017

Volltextzugriff (PDF)

Atom probe tomography study of alloying element distributions in Zr alloys and their oxides

Journal of nuclear materials, 2013-11, Vol.442 (1-3), p.270-281

2013

Volltextzugriff (PDF)

Predicting the hydride rim by improving the solubility limits in the Hydride Nucleation-Growth-Dissolution (HNGD) model

Journal of nuclear materials, 2022-01, Vol.558 (C), p.153363, Article 153363

2022

Volltextzugriff (PDF)

Waterside corrosion in zirconium alloys

JOM (1989), 2011-08, Vol.63 (8), p.59-63

Motta, Arthur T.

2011

Volltextzugriff (PDF)

Hydride Formation in Zirconium Alloys

JOM (1989), 2012-12, Vol.64 (12), p.1403-1408

2012

Volltextzugriff (PDF)

Microbeam X-ray Absorption Near-Edge Spectroscopy study of the oxidation of Fe and Nb in zirconium alloy oxide layers

Journal of nuclear materials, 2014-09, Vol.452 (1-3), p.614-627

2014

Volltextzugriff (PDF)

EELS and atom probe tomography study of the evolution of the metal/oxide interface during zirconium alloy oxidation

Journal of nuclear materials, 2015-07, Vol.462 (C), p.304-309

2015

Volltextzugriff (PDF)

Characterization of faulted dislocation loops and cavities in ion irradiated alloy 800H

Journal of nuclear materials, 2018-01, Vol.498 (C), p.458-467

2018

Volltextzugriff (PDF)

In situ transmission electron microscopy and ion irradiation of ferritic materials

Microscopy research and technique, 2009-03, Vol.72 (3), p.182-186

2009

Volltextzugriff (PDF)

Investigation of δ zirconium hydride morphology in a single crystal using quantitative phase field simulations supported by experiments

Journal of nuclear materials, 2021-12, Vol.557, p.153303, Article 153303

2021

Volltextzugriff (PDF)

Sensitivity analysis for characterizing the impact of HNGD model on the prediction of hydrogen redistribution in Zircaloy cladding using BISON code

Nuclear engineering and design, 2022-07, Vol.393 (C), p.111813, Article 111813

2022

Volltextzugriff (PDF)

Transmission electron microscopy examination of oxide layers formed on Zr alloys

Journal of nuclear materials, 2006-03, Vol.349 (3), p.265-281

2006

Volltextzugriff (PDF)

Effect of thermo-mechanical cycling on zirconium hydride reorientation studied in situ with synchrotron X-ray diffraction

Journal of nuclear materials, 2013-09, Vol.440 (1-3), p.586-595

2013

Volltextzugriff (PDF)

Microbeam synchrotron radiation diffraction and fluorescence of oxide layers formed on zirconium alloys at different corrosion temperatures

Journal of nuclear materials, 2019-12, Vol.526 (C), p.151779, Article 151779

2019

Volltextzugriff (PDF)

Hydride precipitation kinetics in Zircaloy-4 studied using synchrotron X-ray diffraction

Journal of nuclear materials, 2015-06, Vol.461, p.180-185

2015

Volltextzugriff (PDF)

1 – 25 von 259

Suche als RSS-Feed

Suchergebnisse filtern

Filter anzeigen

Nur zeigen

Geprüft (Peer-Review)
(212)
Mit Volltextzugriff
(220)

Publikationsform

Sprache

Erscheinungsjahr

n.n

Neu hinzugefügt

... seit 30 Tagen
(1)
... seit 90 Tagen
(6)

Menü

Weitere Dienste

Einstellungen

Corrosion of Zirconium Alloys Used for Nuclear Fuel Cladding

Oxidation behavior of ferritic–martensitic and ODS steels in supercritical water

A phase-field model for hydride formation in polycrystalline metals: Application to δ-hydride in zirconium alloys

Modeling and simulation of hydrogen behavior in Zircaloy-4 fuel cladding

Corrosion of ferritic–martensitic steels in steam and supercritical water

Hydrogen in zirconium alloys: A review

Hydrogen pickup measurements in zirconium alloys: Relation to oxidation kinetics

Transmission electron microscopy characterization of Zircaloy-4 and ZIRLO™ oxide layers

Implementation and Validation of the Hydride Nucleation-Growth-Dissolution (HNGD) model in BISON

EFTEM and EELS analysis of the oxide layer formed on HCM12A exposed to SCW

In-situ electrochemical impedance spectroscopy measurements of zirconium alloy oxide conductivity: Relationship to hydrogen pickup

Atom probe tomography study of alloying element distributions in Zr alloys and their oxides

Predicting the hydride rim by improving the solubility limits in the Hydride Nucleation-Growth-Dissolution (HNGD) model

Waterside corrosion in zirconium alloys

Hydride Formation in Zirconium Alloys

Microbeam X-ray Absorption Near-Edge Spectroscopy study of the oxidation of Fe and Nb in zirconium alloy oxide layers

EELS and atom probe tomography study of the evolution of the metal/oxide interface during zirconium alloy oxidation

Characterization of faulted dislocation loops and cavities in ion irradiated alloy 800H

In situ transmission electron microscopy and ion irradiation of ferritic materials

Investigation of δ zirconium hydride morphology in a single crystal using quantitative phase field simulations supported by experiments

Sensitivity analysis for characterizing the impact of HNGD model on the prediction of hydrogen redistribution in Zircaloy cladding using BISON code

Transmission electron microscopy examination of oxide layers formed on Zr alloys

Effect of thermo-mechanical cycling on zirconium hydride reorientation studied in situ with synchrotron X-ray diffraction

Microbeam synchrotron radiation diffraction and fluorescence of oxide layers formed on zirconium alloys at different corrosion temperatures

Hydride precipitation kinetics in Zircaloy-4 studied using synchrotron X-ray diffraction

Suchergebnisse filtern