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...

An evaluation of tri-valent oxide (Cr2O3) as a grain enlarging dopant for UO2 nuclear fuels fabricated under reducing environment

Journal of nuclear materials, 2021-09, Vol.553, p.153053, Article 153053

2021

Volltextzugriff (PDF)

Structure and properties of amorphous uranium dioxide

Acta materialia, 2021-01, Vol.202, p.366-375

2021

Volltextzugriff (PDF)

The lattice contraction of UO2 from Cr doping as determined via high resolution synchrotron X-ray powder diffraction

Journal of nuclear materials, 2024-07, Vol.595, p.155046, Article 155046

2024

Volltextzugriff (PDF)

Modelling the thermal conductivity of (UxTh1−x)O2 and (UxPu1−x)O2

Journal of nuclear materials, 2015-11, Vol.466 (C), p.29-35

2015

Volltextzugriff (PDF)

Bayesian calibration with summary statistics for the prediction of xenon diffusion in UO2 nuclear fuel

Computational materials science, 2023-06, Vol.225, p.112184, Article 112184

2023

Volltextzugriff (PDF)

Very high burnup spent fuel corrosion & leaching under hydrogen conditions

Journal of nuclear materials, 2022-12, Vol.572, p.154027, Article 154027

2022

Volltextzugriff (PDF)

Thermal-shock experiments for separate-effects validation of UO2 fuel fracture models

Journal of nuclear materials, 2022-12, Vol.572, Article 154035

2022

Volltextzugriff (PDF)

Thermodynamic modeling of the U3O8-x solid solution phase

Journal of nuclear materials, 2019-10, Vol.530 (C)

2019

Volltextzugriff (PDF)

Compositional design of an amphoteric chemical trap for the capturing of gaseous cesium and iodine in UO2 nuclear fuel

Journal of the European Ceramic Society, 2021-04, Vol.41 (4), p.2892-2897

2021

Volltextzugriff (PDF)

Charge Optimized Many Body (COMB) potentials for simulation of nuclear fuel and clad

Computational materials science, 2018-06, Vol.148 (C), p.231-241

2018

Volltextzugriff (PDF)

In-situ synthesized nanocrystalline UO2/SiC composite with superior thermal conductivity

Ceramics international, 2021-11, Vol.47 (22), p.31160-31167

2021

Volltextzugriff (PDF)

An improved internal gelation process without cooling the solution for preparing uranium dioxide ceramic microspheres

Ceramics international, 2018-02, Vol.44 (2), p.2524-2528

2018

Volltextzugriff (PDF)

Thermophysical properties of urania-zirconia (U,Zr)O2 mixed oxides by molecular dynamics

Journal of nuclear materials, 2020-01, Vol.528, p.151876, Article 151876

2020

Volltextzugriff (PDF)

UO2–Y2O3 ceramic nuclear fuel: SPS fabrication, physico-chemical investigation and neutron absorption evaluation

Journal of alloys and compounds, 2021-10, Vol.877, p.160266, Article 160266

2021

Volltextzugriff (PDF)

Modelling explicit fracture of nuclear fuel pellets using peridynamics

Journal of nuclear materials, 2015-12, Vol.467 (Part 1), p.58-67

2015

Volltextzugriff (PDF)

UO2-liquid metal suspension fuel concept for enhanced passive safety of LWRs: A heat pipe case study

Nuclear engineering and design, 2022-11, Vol.398 (1), p.111972, Article 111972

Greenquist, Ian

2022

Volltextzugriff (PDF)

Thermodynamic modeling of the U3O8-x solid solution phase

Journal of nuclear materials, 2020-03, Vol.530 (C), p.151844, Article 151844

2020

Volltextzugriff (PDF)

EBSD studies on microstructure and crystallographic orientation of UO2-Mo composite fuels

Nuclear engineering and technology, 2021-12, Vol.53 (12), p.4052-4059

2021

Volltextzugriff (PDF)

Thermochemistry of UO2 – ThO2 and UO2 – ZrO2 fluorite solid solutions

The Journal of chemical thermodynamics, 2017-11, Vol.114 (C), p.48-54

2017

Volltextzugriff (PDF)

Simulation of reactivity-initiated accident transients on UO2-M5® fuel rods with ALCYONE V1.4 fuel performance code

Nuclear engineering and technology, 2018-03, Vol.50 (2), p.268-279

2018

Volltextzugriff (PDF)

Thermal–mechanical performance modeling of thorium–plutonium oxide fuel and comparison with on-line irradiation data

Journal of nuclear materials, 2015-12, Vol.467 (Part 2), p.876-885

2015

Volltextzugriff (PDF)

Molecular dynamics simulation of Xe bubble nucleation in nanocrystalline UO2 nuclear fuel

Journal of nuclear materials, 2011-12, Vol.419 (1-3), p.140-144

2011

Volltextzugriff (PDF)

Nonlinear dynamical behavior of Xenon atoms along dislocation lines in UO2＋x nuclear fuel

Science China. Physics, mechanics & astronomy, 2015-05, Vol.58 (5), p.82-87

2015

Volltextzugriff (PDF)

Growth mechanisms of interstitial loops in α-doped UO2 samples

Nuclear instruments & methods in physics research. Section B, Beam interactions with materials and atoms, 2008-06, Vol.266 (12-13), p.3008-3012

2008

Volltextzugriff (PDF)

Atomistic modelling of actinide oxides for nuclear fuel applications

Physica status solidi. C, 2013-02, Vol.10 (2), p.197-201

2013

Volltextzugriff (PDF)

1 – 25 von 31

Suche als RSS-Feed

Aktive Filter

ThemaNuclear Fuel

Suchergebnisse filtern

Filter anzeigen

Nur zeigen

Geprüft (Peer-Review)
(28)
Mit Volltextzugriff
(28)

Publikationsform

Sprache

Englisch
(31)

Erscheinungsjahr

n.n

Thema

Science & Technology
(23)
Uo2
(22)
Technology
(21)
Materials Science
(17)
Materials Science, Multidisciplinary
(13)
Nuclear Science & Technology
(13)
Nuclear Fuel Cycle And Fuel Materials
(9)
Nuclear Fuels
(9)
Uranium Dioxide
(8)
Fuels
(5)
Physical Sciences
(5)
Physics
(5)
Thermal Conductivity
(5)
Molecular Dynamics
(4)
Mox
(4)
Oxides
(4)
Defects
(3)
Kernbrennstoff
(3)
Materials Science, Ceramics
(3)

14 weitere anzeigen...

Weniger anzeigen...

Menü

Weitere Dienste

Einstellungen

An evaluation of tri-valent oxide (Cr2O3) as a grain enlarging dopant for UO2 nuclear fuels fabricated under reducing environment

Structure and properties of amorphous uranium dioxide

The lattice contraction of UO2 from Cr doping as determined via high resolution synchrotron X-ray powder diffraction

Modelling the thermal conductivity of (UxTh1−x)O2 and (UxPu1−x)O2

Bayesian calibration with summary statistics for the prediction of xenon diffusion in UO2 nuclear fuel

Very high burnup spent fuel corrosion & leaching under hydrogen conditions

Thermal-shock experiments for separate-effects validation of UO2 fuel fracture models

Thermodynamic modeling of the U3O8-x solid solution phase

Compositional design of an amphoteric chemical trap for the capturing of gaseous cesium and iodine in UO2 nuclear fuel

Charge Optimized Many Body (COMB) potentials for simulation of nuclear fuel and clad

In-situ synthesized nanocrystalline UO2/SiC composite with superior thermal conductivity

An improved internal gelation process without cooling the solution for preparing uranium dioxide ceramic microspheres

Thermophysical properties of urania-zirconia (U,Zr)O2 mixed oxides by molecular dynamics

UO2–Y2O3 ceramic nuclear fuel: SPS fabrication, physico-chemical investigation and neutron absorption evaluation

Modelling explicit fracture of nuclear fuel pellets using peridynamics

UO2-liquid metal suspension fuel concept for enhanced passive safety of LWRs: A heat pipe case study

Thermodynamic modeling of the U3O8-x solid solution phase

EBSD studies on microstructure and crystallographic orientation of UO2-Mo composite fuels

Thermochemistry of UO2 – ThO2 and UO2 – ZrO2 fluorite solid solutions

Simulation of reactivity-initiated accident transients on UO2-M5® fuel rods with ALCYONE V1.4 fuel performance code

Thermal–mechanical performance modeling of thorium–plutonium oxide fuel and comparison with on-line irradiation data

Molecular dynamics simulation of Xe bubble nucleation in nanocrystalline UO2 nuclear fuel

Nonlinear dynamical behavior of Xenon atoms along dislocation lines in UO2＋x nuclear fuel

Growth mechanisms of interstitial loops in α-doped UO2 samples

Atomistic modelling of actinide oxides for nuclear fuel applications

Aktive Filter

Suchergebnisse filtern