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...

Flexible Electrode Made of Graphene and Few-Layer Graphite

Technical physics, 2018-07, Vol.63 (7), p.1084-1086

2018

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)

Study of Tritium and Helium Release from Irradiated Lithium Ceramics Li2TiO3

Fusion science and technology, 2011-10, Vol.60 (3), p.1139-1142

2011

Volltextzugriff (PDF)

Tritium accumulation and release from Li sub(2Ti[ETH]) sub(3) 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)

Study of Tritium and Helium Release from Irradiated Lithium Ceramics Li 2 TiO 3

Fusion science and technology, 2011-10, Vol.60 (3), p.1139-1142

2011

Volltextzugriff (PDF)

STUDY OF TRITIUM AND HELIUM RELEASE FROM IRRADIATED LITHIUM CERAMICS Li(2)TiO(3)

Fusion science and technology, 2011-01, Vol.60 (3), p.1139-1142

2011

Volltextzugriff (PDF)

Hydrogen release of reactor irradiated RGT-graphite

Journal of nuclear materials, 1996-10, Vol.233, p.1198-1201

1996

Volltextzugriff (PDF)

Tritium accumulation and release from Li2TiO3 during long-term irradiation in the WWR-K reactor

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

2011

Volltextzugriff (PDF)

Hydrogen release from irradiated vanadium alloy V–4Cr–4Ti

Fusion engineering and design, 2000-11, Vol.51, p.127-133

2000

Volltextzugriff (PDF)

Hydrogen permeability measurements of 08Cr18Ni10Ti stainless steel in fission reactor irradiation conditions

Plasma devices and operations, 1996-11, Vol.5 (1), p.71-76

1996

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)

Application of High-Energy Tritium Ions and Alpha Particles Formed in 6Li(n,α)T Nuclear Reaction to Excite the Luminescence of Inert Gas Mixtures

Fusion science and technology, 2021-05, Vol.77 (4), p.327-332

2021

Volltextzugriff (PDF)

Hydrogen permeability technique in situ reactor irradiation for ITER structural materials

Fusion technology, 1995, Vol.28 (3), p.1290-1293

1995

Volltextzugriff (PDF)

Study of Gas Swelling Processes under Irradiation with Protons and He2+ Ions in Li4SiO4–Li2TiO3 Ceramics

Crystals (Basel), 2023-10, Vol.13 (10), p.1526

2023

Volltextzugriff (PDF)

Application of High-Energy Tritium Ions and Alpha Particles Formed in 6 Li( n ,α)T Nuclear Reaction to Excite the Luminescence of Inert Gas Mixtures

Fusion science and technology, 2021-05, Vol.77 (4), p.327-332

2021

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)

Modeling the Processes of Hydrogen Isotopes Interactions with Solid Surfaces

Fusion science and technology, 2020-05, Vol.76 (4), p.494-502

2020

Volltextzugriff (PDF)

Study of Gas Swelling Processes under Irradiation with Protons and He[sup.2+] Ions in Li[sub.4]SiO[sub.4]–Li[sub.2]TiO[sub.3] Ceramics

Crystals (Basel), 2023-10, Vol.13 (10)

2023

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)

Hydrogen Permeability Technique in Situ Reactor Irradiation for ITER Structural Materials

Fusion technology, 1995-10, Vol.28 (3P2), p.1290-1293

1995

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)

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)

Material science activities for fusion reactors in Kazakhstan

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

2009

Volltextzugriff (PDF)

Material science activities for fusion reactors in Kazakhstan

Journal of nuclear materials, 2009, Vol.386-88, p.15-18

2009

Volltextzugriff (PDF)

Hydrogen release from reactor-irradiated beryllium

Journal of nuclear materials, 1996-10, Vol.233 (1-3), p.837-840

1996

Volltextzugriff (PDF)

1 – 25 von 29

Suche als RSS-Feed

Suchergebnisse filtern

Filter anzeigen

Nur zeigen

Geprüft (Peer-Review)
(27)
Mit Volltextzugriff
(27)

Publikationsform

Artikel
(25)
Tagungsberichte
(4)

Sprache

Englisch
(26)
Russisch
(3)

Erscheinungsjahr

n.n

Zeitschrift / Serie

Journal Of Nuclear Materials
(7)
Fusion Science And Technology
(6)
Fusion Engineering And Design
(4)
Crystals
(2)
International Journal Of Hydrogen Energy
(2)
Plasma Devices And Operations
(2)
Fusion Technology
(1)
Technical Physics
(1)

3 weitere anzeigen...

Weniger anzeigen...

Menü

Weitere Dienste

Einstellungen

Flexible Electrode Made of Graphene and Few-Layer Graphite

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

Study of Tritium and Helium Release from Irradiated Lithium Ceramics Li2TiO3

Tritium accumulation and release from Li sub(2Ti[ETH]) sub(3) during long-term irradiation in the WWR-K reactor

Study of Tritium and Helium Release from Irradiated Lithium Ceramics Li 2 TiO 3

STUDY OF TRITIUM AND HELIUM RELEASE FROM IRRADIATED LITHIUM CERAMICS Li(2)TiO(3)

Hydrogen release of reactor irradiated RGT-graphite

Tritium accumulation and release from Li2TiO3 during long-term irradiation in the WWR-K reactor

Hydrogen release from irradiated vanadium alloy V–4Cr–4Ti

Hydrogen permeability measurements of 08Cr18Ni10Ti stainless steel in fission reactor irradiation conditions

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

Application of High-Energy Tritium Ions and Alpha Particles Formed in 6Li(n,α)T Nuclear Reaction to Excite the Luminescence of Inert Gas Mixtures

Hydrogen permeability technique in situ reactor irradiation for ITER structural materials

Study of Gas Swelling Processes under Irradiation with Protons and He2+ Ions in Li4SiO4–Li2TiO3 Ceramics

Application of High-Energy Tritium Ions and Alpha Particles Formed in 6 Li( n ,α)T Nuclear Reaction to Excite the Luminescence of Inert Gas Mixtures

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

Modeling the Processes of Hydrogen Isotopes Interactions with Solid Surfaces

Study of Gas Swelling Processes under Irradiation with Protons and He[sup.2+] Ions in Li[sub.4]SiO[sub.4]–Li[sub.2]TiO[sub.3] Ceramics

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

Hydrogen Permeability Technique in Situ Reactor Irradiation for ITER Structural Materials

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

Investigation of hydrogen isotopes interaction with lithium CPS under reactor irradiation

Material science activities for fusion reactors in Kazakhstan

Material science activities for fusion reactors in Kazakhstan

Hydrogen release from reactor-irradiated beryllium

Suchergebnisse filtern