UB Paderborn / Katalog / Suche / in CDI

1 – 25 von 49

Sortiert nach

Constitutive modeling of δ-phase zircaloy hydride based on strain rate dependent nanoindentation and nano-scale impact dataset

International journal of plasticity, 2020-10, Vol.133 (C), p.102787, Article 102787

2020

Volltextzugriff (PDF)

Microstructure dependent thermal conductivity measurement of Zircaloy-4 using an extended Raman thermometry method

Journal of nuclear materials, 2020-10, Vol.539 (C), p.152338, Article 152338

2020

Volltextzugriff (PDF)

The application of synchrotron micro-computed tomography to characterize the three-dimensional microstructure in irradiated nuclear fuel

Journal of nuclear materials, 2020-08, Vol.537 (C), p.152161, Article 152161

2020

Volltextzugriff (PDF)

4D evolution of Cr23C6 precipitates in neutron-irradiated and annealed HT-UPS steel observed via synchrotron micro-computed tomography

Journal of materials research, 2022-01, Vol.37 (1), p.208-224

2022

Volltextzugriff (PDF)

Atom probe study of irradiation-enhanced α′ precipitation in neutron-irradiated Fe–Cr model alloys

Journal of nuclear materials, 2015-07, Vol.462 (C), p.242-249

2015

Volltextzugriff (PDF)

Helium bubble nucleation in bcc iron studied by kinetic Monte Carlo simulations

Journal of nuclear materials, 2007-04, Vol.361 (2-3), p.141-148

2007

Volltextzugriff (PDF)

Revealing the chemical environment of Cr, Fe, and Ni in high temperature-ultrafine precipitate strengthened steel subjected to low fluence neutron irradiation

Journal of nuclear materials, 2021-10, Vol.554 (C), p.153056, Article 153056

2021

Volltextzugriff (PDF)

Multimodal Characterization of Porosity in Advanced Manufactured and Welded Nuclear Structural Alloys

Microscopy and microanalysis, 2023-07, Vol.29 (Supplement_1), p.1536-1537

2023

Volltextzugriff (PDF)

Defect structures induced by high-energy displacement cascades in γ uranium

Journal of nuclear materials, 2015-01, Vol.456 (C), p.1-6

2015

Volltextzugriff (PDF)

Computational determination of a primary diffusion mode in γU-10Mo under irradiation

Journal of nuclear materials, 2023-02, Vol.574, p.154137, Article 154137

2023

Volltextzugriff (PDF)

An atomistic study of defect energetics and diffusion with respect to composition and temperature in γU and γU-Mo alloys

Journal of nuclear materials, 2021-08, Vol.552 (C), p.152970, Article 152970

2021

Volltextzugriff (PDF)

Computational determination of a primary diffusion mode in γU-10Mo under irradiation

Journal of nuclear materials, 2022-11, Vol.574

2022

Volltextzugriff (PDF)

Positron annihilation spectroscopy of proton irradiated single crystal BCC iron

Journal of nuclear materials, 2006-06, Vol.351 (1), p.149-154

2006

Volltextzugriff (PDF)

Phase transformations and thermal expansion coefficients of unirradiated U-X wt.% Zr (X = 6, 10, 20, 30) measured via neutron diffraction

Journal of nuclear materials, 2023-03, Vol.579 (-)

2023

Volltextzugriff (PDF)

Nuclear Reactor Pressure Vessel Welds: A Critical and Historical Review of Microstructures, Mechanical Properties, Irradiation Effects, and Future Opportunities

Materials & design, 2024-07, p.113134, Article 113134

2024

Volltextzugriff (PDF)

Neutron irradiation effects in Fe and Fe-Cr at 300 °C

Acta materialia, 2016-06, Vol.111 (C), p.407-416

2016

Volltextzugriff (PDF)

First-principles investigation of lanthanides diffusion in HCP zirconium via vacancy-mediated transport

Journal of nuclear materials, 2024-12, Vol.601 (C), p.155310, Article 155310

2024

Volltextzugriff (PDF)

Synchrotron micro-computed tomography analysis of neutron-irradiated U-Mo fuel

Journal of nuclear materials, 2024-08, Vol.597 (C), p.155132, Article 155132

2024

Volltextzugriff (PDF)

Constitutive modeling of δ-phase zircaloy hydride based on strain rate dependent nanoindentation and nano-scale impact dataset

International journal of plasticity, 2020-06, Vol.133 (C)

2020

Volltextzugriff (PDF)

Transmission electron microscopy investigation of phase transformation and fuel constituent redistribution in neutron irradiated U-10wt.%Zr fuel

Journal of nuclear materials, 2023-08, Vol.581, p.154443, Article 154443

2023

Volltextzugriff (PDF)

Small-angle X-ray scattering measurements of helium-bubble formation in borosilicate glass

Journal of applied crystallography, 2006-10, Vol.39 (5), p.647-651

2006

Volltextzugriff (PDF)

The effects of helium on irradiation damage in single crystal iron

Journal of nuclear materials, 2007-08, Vol.367, p.451-456

2007

Volltextzugriff (PDF)

Mechanical characteristics of SiC coating layer in TRISO fuel particles

Journal of nuclear materials, 2013-11, Vol.442 (1-3), p.133-142

2013

Volltextzugriff (PDF)

Neutron diffraction measurement of residual stresses, dislocation density and texture in Zr-bonded U-10Mo “mini” fuel foils and plates

Journal of nuclear materials, 2016-12, Vol.482 (C), p.63-74

2016

Volltextzugriff (PDF)

Revealing the chemical environment of Cr, Fe, and Ni in high temperature-ultrafine precipitate strengthened steel subjected to low fluence neutron irradiation

Journal of nuclear materials, 2021-05, Vol.554

2021

Volltextzugriff (PDF)

1 – 25 von 49

Suche als RSS-Feed

Suchergebnisse filtern

Filter anzeigen

Nur zeigen

Geprüft (Peer-Review)
(44)
Mit Volltextzugriff
(44)

Publikationsform

Sprache

Englisch
(49)
Japanisch
(3)

Erscheinungsjahr

n.n

Neu hinzugefügt

... seit 30 Tagen
(1)
... seit 90 Tagen
(2)

Menü

Weitere Dienste

Einstellungen

Constitutive modeling of δ-phase zircaloy hydride based on strain rate dependent nanoindentation and nano-scale impact dataset

Microstructure dependent thermal conductivity measurement of Zircaloy-4 using an extended Raman thermometry method

The application of synchrotron micro-computed tomography to characterize the three-dimensional microstructure in irradiated nuclear fuel

4D evolution of Cr23C6 precipitates in neutron-irradiated and annealed HT-UPS steel observed via synchrotron micro-computed tomography

Atom probe study of irradiation-enhanced α′ precipitation in neutron-irradiated Fe–Cr model alloys

Helium bubble nucleation in bcc iron studied by kinetic Monte Carlo simulations

Revealing the chemical environment of Cr, Fe, and Ni in high temperature-ultrafine precipitate strengthened steel subjected to low fluence neutron irradiation

Multimodal Characterization of Porosity in Advanced Manufactured and Welded Nuclear Structural Alloys

Defect structures induced by high-energy displacement cascades in γ uranium

Computational determination of a primary diffusion mode in γU-10Mo under irradiation

An atomistic study of defect energetics and diffusion with respect to composition and temperature in γU and γU-Mo alloys

Computational determination of a primary diffusion mode in γU-10Mo under irradiation

Positron annihilation spectroscopy of proton irradiated single crystal BCC iron

Phase transformations and thermal expansion coefficients of unirradiated U-X wt.% Zr (X = 6, 10, 20, 30) measured via neutron diffraction

Nuclear Reactor Pressure Vessel Welds: A Critical and Historical Review of Microstructures, Mechanical Properties, Irradiation Effects, and Future Opportunities

Neutron irradiation effects in Fe and Fe-Cr at 300 °C

First-principles investigation of lanthanides diffusion in HCP zirconium via vacancy-mediated transport

Synchrotron micro-computed tomography analysis of neutron-irradiated U-Mo fuel

Constitutive modeling of δ-phase zircaloy hydride based on strain rate dependent nanoindentation and nano-scale impact dataset

Transmission electron microscopy investigation of phase transformation and fuel constituent redistribution in neutron irradiated U-10wt.%Zr fuel

Small-angle X-ray scattering measurements of helium-bubble formation in borosilicate glass

The effects of helium on irradiation damage in single crystal iron

Mechanical characteristics of SiC coating layer in TRISO fuel particles

Neutron diffraction measurement of residual stresses, dislocation density and texture in Zr-bonded U-10Mo “mini” fuel foils and plates

Revealing the chemical environment of Cr, Fe, and Ni in high temperature-ultrafine precipitate strengthened steel subjected to low fluence neutron irradiation

Suchergebnisse filtern