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...

Effect of rhenium addition on deuterium retention in neutron-irradiated tungsten

Journal of nuclear materials, 2022-08, Vol.566 (C), p.153774, Article 153774

2022

Volltextzugriff (PDF)

Helium irradiation effects on tritium retention and long-term tritium release properties in polycrystalline tungsten

Journal of nuclear materials, 2015-08, Vol.463, p.993-996

2015

Volltextzugriff (PDF)

D retention and depth profile behavior for single crystal tungsten with high temperature neutron irradiation

Journal of nuclear materials, 2020-10, Vol.539, p.152323, Article 152323

2020

Volltextzugriff (PDF)

Investigation of remaining tritium in the LHD vacuum vessel after the first deuterium experimental campaign

Physica scripta, 2020-01, Vol.T171 (1), p.14068

2020

Volltextzugriff (PDF)

Deuterium retention on He-irradiated F82H with surface impurity layer

Journal of nuclear materials, 2015-08, Vol.463, p.1001-1004

2015

Volltextzugriff (PDF)

Safety assessment of Lactobacillus brevis KB290 as a probiotic strain

Food and chemical toxicology, 2009-10, Vol.47 (10), p.2450-2453

2009

Volltextzugriff (PDF)

Deuterium retention in tungsten irradiated by high-dose neutrons at high temperature

Nuclear materials and energy, 2021-06, Vol.27 (C), p.100980, Article 100980

2021

Volltextzugriff (PDF)

Effect of induced damage on hydrogen isotope retention of F82H with impurity layer

Fusion engineering and design, 2014-10, Vol.89 (7-8), p.921-924

2014

Volltextzugriff (PDF)

Tritium retention properties of tungsten, graphite and co-deposited carbon film

Fusion engineering and design, 2014-10, Vol.89 (7-8), p.1516-1519

2014

Volltextzugriff (PDF)

Hydrogen and helium removal retained in stainless steel by neon glow discharge

Journal of nuclear materials, 2009-06, Vol.390, p.1048-1050

2009

Volltextzugriff (PDF)

Effects of modified surfaces produced at plasma-facing surface on hydrogen release behavior in the LHD

Nuclear materials and energy, 2017-08, Vol.12, p.483-487

2017

Volltextzugriff (PDF)

Hydrogen concentration of co-deposited carbon film produced in the vicinity of LHD divertor tiles

Journal of nuclear materials, 2013-07, Vol.438, p.S1040-S1043

2013

Volltextzugriff (PDF)

Deuterium ion irradiation for tritium breeding material and evaluation for tritium inventories in test blanket module and blanket of a demonstration reactor

Journal of nuclear materials, 2011-10, Vol.417 (1-3), p.713-717

2011

Volltextzugriff (PDF)

Effects of glow discharge cleanings on hydrogen isotope removal for plasma facing materials

Journal of nuclear materials, 2013-07, Vol.438, p.S1146-S1149

2013

Volltextzugriff (PDF)

JCI’s Activities－Recent Accomplishments and Challenges for Future

Konkurīto kōgaku, 2022, Vol.60 (1), p.20-27

2022

Volltextzugriff (PDF)

JCI’s Activities－Recent Accomplishments and Challenges for Future

Concrete Journal, 2022, Vol.60(1), pp.20-27

2022

Volltextzugriff (PDF)

Deuterium retention in F82H after low energy hydrogen ion irradiation

Journal of nuclear materials, 2011-10, Vol.417 (1-3), p.1147-1149

2011

Volltextzugriff (PDF)

Localized tungsten deposition in divertor region in JT-60U

Nuclear fusion, 2009-06, Vol.49 (6), p.65027

2009

Volltextzugriff (PDF)

Effect of impurity deposition layer formation on D retention in LHD plasma exposed W

Nuclear materials and energy, 2016-12, Vol.9 (C), p.84-88

2016

Volltextzugriff (PDF)

Helium retention and surface morphology of oxidized vanadium alloy

Journal of nuclear materials, 2011-10, Vol.417 (1-3), p.327-329

2011

Volltextzugriff (PDF)

Deuterium concentration of co-deposited carbon layer produced at gap of wall tiles

Journal of nuclear materials, 2011-10, Vol.417 (1-3), p.607-611

2011

Volltextzugriff (PDF)

Effect of rhenium addition on deuterium retention in neutron-irradiated tungsten

Journal of nuclear materials, 2022-05, Vol.566 (1)

2022

Volltextzugriff (PDF)

Hydrogen isotopes retention in the outboard first wall tiles of JT-60U

Journal of nuclear materials, 2009-06, Vol.390, p.635-638

2009

Volltextzugriff (PDF)

Characterization of Surface Modifications of Plasma-Facing Components in LHD

Fusion science and technology, 2010-08, Vol.58 (1), p.305-320

2010

Volltextzugriff (PDF)

Hydrogen behavior in damaged tungsten by high-energy ion irradiation

Journal of nuclear materials, 2009-04, Vol.386, p.768-771

2009

Volltextzugriff (PDF)

1 – 25 von 93

Suche als RSS-Feed

Suchergebnisse filtern

Filter anzeigen

Nur zeigen

Geprüft (Peer-Review)
(85)
Mit Volltextzugriff
(80)

Publikationsform

Sprache

Englisch
(86)
Japanisch
(7)

Erscheinungsjahr

n.n

Thema

Science & Technology
(61)
Technology
(36)
Nuclear Science & Technology
(33)
Materials Science
(21)
Exact Sciences And Technology
(19)
Materials Science, Multidisciplinary
(18)
Applied Sciences
(16)
Controled Nuclear Fusion Plants
(16)
Energy
(16)
Energy. Thermal Use Of Fuels
(16)
Installations For Energy Generation And Conversion: Thermal And Electrical Energy
(16)
Life Sciences & Biomedicine
(16)
Humans
(13)
Fuels
(12)
Male
(11)
Fission Nuclear Power Plants
(10)
Lhd
(10)
Nuclear Fuels
(10)
Physical Sciences
(10)
Deuterium
(9)

15 weitere anzeigen...

Weniger anzeigen...

Menü

Weitere Dienste

Einstellungen

Effect of rhenium addition on deuterium retention in neutron-irradiated tungsten

Helium irradiation effects on tritium retention and long-term tritium release properties in polycrystalline tungsten

D retention and depth profile behavior for single crystal tungsten with high temperature neutron irradiation

Investigation of remaining tritium in the LHD vacuum vessel after the first deuterium experimental campaign

Deuterium retention on He-irradiated F82H with surface impurity layer

Safety assessment of Lactobacillus brevis KB290 as a probiotic strain

Deuterium retention in tungsten irradiated by high-dose neutrons at high temperature

Effect of induced damage on hydrogen isotope retention of F82H with impurity layer

Tritium retention properties of tungsten, graphite and co-deposited carbon film

Hydrogen and helium removal retained in stainless steel by neon glow discharge

Effects of modified surfaces produced at plasma-facing surface on hydrogen release behavior in the LHD

Hydrogen concentration of co-deposited carbon film produced in the vicinity of LHD divertor tiles

Deuterium ion irradiation for tritium breeding material and evaluation for tritium inventories in test blanket module and blanket of a demonstration reactor

Effects of glow discharge cleanings on hydrogen isotope removal for plasma facing materials

JCI’s Activities－Recent Accomplishments and Challenges for Future

JCI’s Activities－Recent Accomplishments and Challenges for Future

Deuterium retention in F82H after low energy hydrogen ion irradiation

Localized tungsten deposition in divertor region in JT-60U

Effect of impurity deposition layer formation on D retention in LHD plasma exposed W

Helium retention and surface morphology of oxidized vanadium alloy

Deuterium concentration of co-deposited carbon layer produced at gap of wall tiles

Effect of rhenium addition on deuterium retention in neutron-irradiated tungsten

Hydrogen isotopes retention in the outboard first wall tiles of JT-60U

Characterization of Surface Modifications of Plasma-Facing Components in LHD

Hydrogen behavior in damaged tungsten by high-energy ion irradiation

Suchergebnisse filtern