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...

Properties of zirconium carbide for nuclear fuel applications

Journal of nuclear materials, 2013-10, Vol.441 (1-3), p.718-742

2013

Volltextzugriff (PDF)

Radiation tolerance of neutron-irradiated model Fe–Cr–Al alloys

Journal of nuclear materials, 2015-10, Vol.465, p.746-755

2015

Volltextzugriff (PDF)

Continuous SiC fiber, CVI SiC matrix composites for nuclear applications: Properties and irradiation effects

Journal of nuclear materials, 2014-05, Vol.448 (1-3), p.448-476

2014

Volltextzugriff (PDF)

Radiation effects in SiC for nuclear structural applications

Current opinion in solid state & materials science, 2012-06, Vol.16 (3), p.143-152

2012

Volltextzugriff (PDF)

Silicon Carbide Oxidation in Steam up to 2 MPa

Journal of the American Ceramic Society, 2014-08, Vol.97 (8), p.2331-2352

2014

Volltextzugriff (PDF)

Defect evolution in single crystalline tungsten following low temperature and low dose neutron irradiation

Journal of nuclear materials, 2016-03, Vol.470, p.278-289

2016

Volltextzugriff (PDF)

Handbook of SiC properties for fuel performance modeling

Journal of nuclear materials, 2007-09, Vol.371 (1), p.329-377

2007

Volltextzugriff (PDF)

Recent advances in modeling and simulation of the exposure and response of tungsten to fusion energy conditions

Nuclear fusion, 2017-06, Vol.57 (9), p.92008

2017

Volltextzugriff (PDF)

Silicon carbide and its composites for nuclear applications – Historical overview

Journal of nuclear materials, 2019-12, Vol.526 (C), p.151849, Article 151849

2019

Volltextzugriff (PDF)

Deformation behavior of laser welds in high temperature oxidation resistant Fe–Cr–Al alloys for fuel cladding applications

Journal of nuclear materials, 2014-11, Vol.454 (1-3), p.352-358

2014

Volltextzugriff (PDF)

Radiation-tolerant joining technologies for silicon carbide ceramics and composites

Journal of nuclear materials, 2014-05, Vol.448 (1-3), p.497-511

2014

Volltextzugriff (PDF)

Effects of fast neutron irradiation on zirconium carbide

Journal of nuclear materials, 2010-04, Vol.399 (2), p.200-207

2010

Volltextzugriff (PDF)

Thermophysical and mechanical properties of near-stoichiometric fiber CVI SiC/SiC composites after neutron irradiation at elevated temperatures

Journal of nuclear materials, 2010-08, Vol.403 (1), p.48-61

2010

Volltextzugriff (PDF)

Observation and possible mechanism of irradiation induced creep in ceramics

Journal of nuclear materials, 2013-03, Vol.434 (1-3), p.141-151

2013

Volltextzugriff (PDF)

Mechanical properties of advanced SiC fiber composites irradiated at very high temperatures

Journal of nuclear materials, 2011-10, Vol.417 (1-3), p.416-420

2011

Volltextzugriff (PDF)

Development and potential of composite moderators for elevated temperature nuclear applications

Journal of Asian Ceramic Societies, 2022-01, Vol.10 (1), p.9-32

2022

Volltextzugriff (PDF)

The effect of neutron irradiation damage on the properties of grade NBG-10 graphite

Journal of nuclear materials, 2007-09, Vol.371 (1), p.18-27

2007

Volltextzugriff (PDF)

Microencapsulated fuel technology for commercial light water and advanced reactor application

Journal of nuclear materials, 2012-08, Vol.427 (1-3), p.209-224

2012

Volltextzugriff (PDF)

Silicon Carbide and Silicon Carbide Composites for Fusion Reactor Application

Materials transactions, 2013-01, Vol.54 (4), p.472-476

2013

Volltextzugriff (PDF)

Dimensional stability and anisotropy of SiC and SiC-based composites in transition swelling regime

Journal of nuclear materials, 2018-02, Vol.499 (C), p.471-479

2018

Volltextzugriff (PDF)

Mechanical property degradation of high crystalline SiC fiber–reinforced SiC matrix composite neutron irradiated to ∼100 displacements per atom

Journal of the European Ceramic Society, 2018-04, Vol.38 (4), p.1087-1094

2018

Volltextzugriff (PDF)

Method for analyzing passive silicon carbide thermometry with a continuous dilatometer to determine irradiation temperature

Nuclear instruments & methods in physics research. Section B, Beam interactions with materials and atoms, 2016-03, Vol.370 (C), p.49-58

2016

Volltextzugriff (PDF)

Irradiation hardening of pure tungsten exposed to neutron irradiation

Journal of nuclear materials, 2016-11, Vol.480, p.235-243

2016

Volltextzugriff (PDF)

Stored energy release in neutron irradiated silicon carbide

Journal of nuclear materials, 2019-02, Vol.514 (C), p.181-188

2019

Volltextzugriff (PDF)

Irradiation stability and thermo-mechanical properties of NITE-SiC irradiated to 10 dpa

Journal of nuclear materials, 2018-02, Vol.499, p.242-247

2018

Volltextzugriff (PDF)

1 – 25 von 191

Suche als RSS-Feed

Suchergebnisse filtern

Filter anzeigen

Nur zeigen

Geprüft (Peer-Review)
(171)
Mit Volltextzugriff
(173)

Publikationsform

Sprache

Erscheinungsjahr

n.n

Thema

Science & Technology
(134)
Technology
(129)
Materials Science
(115)
Nuclear Science & Technology
(103)
Materials Science, Multidisciplinary
(92)
Exact Sciences And Technology
(53)
Applied Sciences
(52)
Energy
(50)
Energy. Thermal Use Of Fuels
(45)
Installations For Energy Generation And Conversion: Thermal And Electrical Energy
(45)
Fuels
(42)
Silicon Carbide
(40)
Controled Nuclear Fusion Plants
(39)
Fission Nuclear Power Plants
(39)
Irradiation
(39)
Nuclear Fuels
(39)
Neutron Irradiation
(25)
70 Plasma Physics And Fusion Technology
(17)
Neutrons
(16)
Silicon Carbides
(15)

15 weitere anzeigen...

Weniger anzeigen...

Menü

Weitere Dienste

Einstellungen

Properties of zirconium carbide for nuclear fuel applications

Radiation tolerance of neutron-irradiated model Fe–Cr–Al alloys

Continuous SiC fiber, CVI SiC matrix composites for nuclear applications: Properties and irradiation effects

Radiation effects in SiC for nuclear structural applications

Silicon Carbide Oxidation in Steam up to 2 MPa

Defect evolution in single crystalline tungsten following low temperature and low dose neutron irradiation

Handbook of SiC properties for fuel performance modeling

Recent advances in modeling and simulation of the exposure and response of tungsten to fusion energy conditions

Silicon carbide and its composites for nuclear applications – Historical overview

Deformation behavior of laser welds in high temperature oxidation resistant Fe–Cr–Al alloys for fuel cladding applications

Radiation-tolerant joining technologies for silicon carbide ceramics and composites

Effects of fast neutron irradiation on zirconium carbide

Thermophysical and mechanical properties of near-stoichiometric fiber CVI SiC/SiC composites after neutron irradiation at elevated temperatures

Observation and possible mechanism of irradiation induced creep in ceramics

Mechanical properties of advanced SiC fiber composites irradiated at very high temperatures

Development and potential of composite moderators for elevated temperature nuclear applications

The effect of neutron irradiation damage on the properties of grade NBG-10 graphite

Microencapsulated fuel technology for commercial light water and advanced reactor application

Silicon Carbide and Silicon Carbide Composites for Fusion Reactor Application

Dimensional stability and anisotropy of SiC and SiC-based composites in transition swelling regime

Mechanical property degradation of high crystalline SiC fiber–reinforced SiC matrix composite neutron irradiated to ∼100 displacements per atom

Method for analyzing passive silicon carbide thermometry with a continuous dilatometer to determine irradiation temperature

Irradiation hardening of pure tungsten exposed to neutron irradiation

Stored energy release in neutron irradiated silicon carbide

Irradiation stability and thermo-mechanical properties of NITE-SiC irradiated to 10 dpa

Suchergebnisse filtern