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...

Determination of the activation energy of tritium diffusion in ceramic breeders by reactor power variation

Fusion engineering and design, 2021-11, Vol.172, p.112783, Article 112783

2021

Volltextzugriff (PDF)

Modeling of hydrogen isotopes release from lithium ceramics Li2TiO3 during in-situ experiments using vacuum extraction method

Fusion engineering and design, 2021-09, Vol.170, p.112705, Article 112705

2021

Volltextzugriff (PDF)

Radiation Resistance of Single-Mode Optical Fibers at λ = 1.55 μm Under Irradiation at IVG.1M Nuclear Reactor

IEEE transactions on nuclear science, 2020-10, Vol.67 (10), p.2162-2171

2020

Volltextzugriff (PDF)

Radiation resistance of single-mode optical fibres with view to in-reactor applications

Nuclear materials and energy, 2021-06, Vol.27, p.100981, Article 100981

2021

Volltextzugriff (PDF)

Radiation Resistance of Fiber Bragg Gratings under Intense Reactor Irradiation

Bulletin of the Lebedev Physics Institute, 2023-09, Vol.50 (Suppl 3), p.S322-S328

2023

Volltextzugriff (PDF)

Effect of low-temperature neutron irradiation on the properties of titanium beryllide

Nuclear materials and energy, 2024-03, Vol.38, p.101582, Article 101582

2024

Volltextzugriff (PDF)

Tritium migration in the materials proposed for fusion reactors: Li2TiO3 and beryllium

Journal of nuclear materials, 2013-11, Vol.442 (1-3), p.S740-S745

2013

Volltextzugriff (PDF)

Reactor studies of tritium release from lead-lithium eutectic Li15.7Pb with deuterium over the sample

Nuclear materials and energy, 2020-12, Vol.25, p.100868, Article 100868

2020

Volltextzugriff (PDF)

Investigation of hydrogen isotopes interaction with lithium CPS under reactor irradiation

Fusion engineering and design, 2017-11, Vol.124, p.324-327

2017

Volltextzugriff (PDF)

Experimental facility for reactor experiments on study of spectral-luminescent characteristics of nuclear-excited plasma

Journal of physics. Conference series, 2016-09, Vol.747 (1), p.12012

2016

Volltextzugriff (PDF)

Development of the reactor lithium ampoule device for research of spectral-luminescent characteristics of nuclear-excited plasma

Fusion engineering and design, 2017-04, Vol.117, p.204-207

2017

Volltextzugriff (PDF)

Investigation of hydrogen isotope permeation through F82H steel with and without a ceramic coating of Cr2O3-SiO2 including CrPO4 (out-of-pile tests)

Fusion engineering and design, 2006-02, Vol.81 (1-7), p.701-705

2006

Volltextzugriff (PDF)

Study of Li2TiO3 + 5 mol% TiO2 lithium ceramics after long-term neutron irradiation

Journal of nuclear materials, 2009-04, Vol.386-88, p.286-289

2009

Volltextzugriff (PDF)

Tritium accumulation and release from Li2TiО3 during long-term irradiation in the WWR-K reactor

Journal of nuclear materials, 2011-10, Vol.417 (1-3), p.748-752

2011

Volltextzugriff (PDF)

Studies of reactor irradiation effect on hydrogen isotope release from vanadium alloy V4Cr4Ti

Journal of nuclear materials, 2007-08, Vol.367, p.844-847

2007

Volltextzugriff (PDF)

Experiments on tritium generation and yield from lithium ceramics during neutron irradiation

International journal of hydrogen energy, 2021-02, Vol.46 (13), p.9186-9192

2021

Volltextzugriff (PDF)

Material science activities for fusion reactors in Kazakhstan

Journal of nuclear materials, 2009-04, Vol.386, p.15-18

2009

Volltextzugriff (PDF)

Reactor experiments on irradiation of two-phase lithium ceramics Li2TiO3/Li4SiO4 of various ratios

Fusion engineering and design, 2023-12, Vol.197, p.114035, Article 114035

2023

Volltextzugriff (PDF)

Measurement system for in-pile tritium monitoring from Li2TiO3 ceramics at WWRK reactor

Journal of nuclear materials, 2007-08, Vol.367-370, p.1028-1032

2007

Volltextzugriff (PDF)

In-pile tritium permeation through F82H steel with and without a ceramic coating of Cr2O3-SiO2 including CrPO4

Fusion engineering and design, 2007-10, Vol.82 (15-24), p.2246-2251

2007

Volltextzugriff (PDF)

Analysis of reactor experiments to study the transfer processes of generated tritium in lithium cps (capillary-porous system)

International journal of hydrogen energy, 2022-02, Vol.47 (11), p.7368-7378

2022

Volltextzugriff (PDF)

The temperature-time dependence of the amount and type of niobium beryllides formed during the synthesis of the binary intermetallic compound NbBe3

Intermetallics, 2023-12, Vol.163, p.108065, Article 108065

2023

Volltextzugriff (PDF)

Study of interaction of hydrogen isotopes with titanium beryllide (Be12Ti)

Fusion engineering and design, 2023-06, Vol.191, p.113738, Article 113738

2023

Volltextzugriff (PDF)

Irradiation experiments of titanium beryllide samples in the WWR-K reactor

Annals of nuclear energy, 2023-12, Vol.194, p.110120, Article 110120

2023

Volltextzugriff (PDF)

Radiation-induced attenuation in single-mode pure-silica-core optical fibers two years after high-fluence reactor irradiation

Optical fiber technology, 2023-10, Vol.80, p.103441, Article 103441

2023

Volltextzugriff (PDF)

1 – 25 von 101

Suche als RSS-Feed

Suchergebnisse filtern

Filter anzeigen

Nur zeigen

Geprüft (Peer-Review)
(97)
Mit Volltextzugriff
(90)

Publikationsform

Artikel
(94)
Tagungsberichte
(7)

Sprache

Englisch
(95)
Russisch
(7)

Erscheinungsjahr

n.n

Thema

Science & Technology
(72)
Technology
(65)
Nuclear Science & Technology
(53)
Tritium
(30)
Neutron Irradiation
(25)
Lithium
(22)
Materials Science
(18)
Materials Science, Multidisciplinary
(17)
Physical Sciences
(16)
Deuterium
(13)
Helium
(13)
Hydrogen
(13)
Hydrogen Isotopes
(13)
Reactor Irradiation
(12)
Irradiation
(11)
Tritium Release
(9)
Ceramics
(8)
Chemistry
(8)
Physics
(8)
Chemistry, Physical
(7)

15 weitere anzeigen...

Weniger anzeigen...

Neu hinzugefügt

... seit 7 Tagen
(1)
... seit 90 Tagen
(2)

Menü

Weitere Dienste

Einstellungen

Determination of the activation energy of tritium diffusion in ceramic breeders by reactor power variation

Modeling of hydrogen isotopes release from lithium ceramics Li2TiO3 during in-situ experiments using vacuum extraction method

Radiation Resistance of Single-Mode Optical Fibers at λ = 1.55 μm Under Irradiation at IVG.1M Nuclear Reactor

Radiation resistance of single-mode optical fibres with view to in-reactor applications

Radiation Resistance of Fiber Bragg Gratings under Intense Reactor Irradiation

Effect of low-temperature neutron irradiation on the properties of titanium beryllide

Tritium migration in the materials proposed for fusion reactors: Li2TiO3 and beryllium

Reactor studies of tritium release from lead-lithium eutectic Li15.7Pb with deuterium over the sample

Investigation of hydrogen isotopes interaction with lithium CPS under reactor irradiation

Experimental facility for reactor experiments on study of spectral-luminescent characteristics of nuclear-excited plasma

Development of the reactor lithium ampoule device for research of spectral-luminescent characteristics of nuclear-excited plasma

Investigation of hydrogen isotope permeation through F82H steel with and without a ceramic coating of Cr2O3-SiO2 including CrPO4 (out-of-pile tests)

Study of Li2TiO3 + 5 mol% TiO2 lithium ceramics after long-term neutron irradiation

Tritium accumulation and release from Li2TiО3 during long-term irradiation in the WWR-K reactor

Studies of reactor irradiation effect on hydrogen isotope release from vanadium alloy V4Cr4Ti

Experiments on tritium generation and yield from lithium ceramics during neutron irradiation

Material science activities for fusion reactors in Kazakhstan

Reactor experiments on irradiation of two-phase lithium ceramics Li2TiO3/Li4SiO4 of various ratios

Measurement system for in-pile tritium monitoring from Li2TiO3 ceramics at WWRK reactor

In-pile tritium permeation through F82H steel with and without a ceramic coating of Cr2O3-SiO2 including CrPO4

Analysis of reactor experiments to study the transfer processes of generated tritium in lithium cps (capillary-porous system)

The temperature-time dependence of the amount and type of niobium beryllides formed during the synthesis of the binary intermetallic compound NbBe3

Study of interaction of hydrogen isotopes with titanium beryllide (Be12Ti)

Irradiation experiments of titanium beryllide samples in the WWR-K reactor

Radiation-induced attenuation in single-mode pure-silica-core optical fibers two years after high-fluence reactor irradiation

Suchergebnisse filtern