UB Paderborn / Katalog / Suche / in CDI

1 – 25 von 161

Sortiert nach

The ITER tritium systems

Fusion engineering and design, 2007-10, Vol.82 (5), p.472-487

2007

Volltextzugriff (PDF)

Counter-current isotope swamping in a membrane reactor: The PERMCAT process and its applications in fusion technology

Catalysis today, 2010-10, Vol.156 (3), p.140-145

2010

Volltextzugriff (PDF)

Tritium retention of plasma facing components in tokamaks

Journal of nuclear materials, 2003-03, Vol.313, p.478-490

2003

Volltextzugriff (PDF)

ITER fuel cycle R&D: Consequences for the design

Fusion engineering and design, 2006-02, Vol.81 (1), p.733-744

2006

Volltextzugriff (PDF)

Highly Tritiated Water Processing by Isotopic Exchange

Fusion science and technology, 2015-04, Vol.67 (3), p.563-566

2015

Volltextzugriff (PDF)

Development of fusion fuel cycle technology at the Tritium Laboratory Karlsruhe: the experiment CAPRICE

Fusion engineering and design, 1995-03, Vol.28 (1-2), p.348-356

1995

Volltextzugriff (PDF)

Codes and standards and regulation issues for design and construction of the ITER mechanical components

Fusion engineering and design, 2010-12, Vol.85 (7), p.1290-1295

2010

Volltextzugriff (PDF)

Experimental validation of upgraded designs for PERMCAT reactors considering mechanical behaviour of Pd/Ag membranes under H2 atmosphere

Fusion engineering and design, 2007-10, Vol.82 (15-24), p.2383-2389

2007

Volltextzugriff (PDF)

The inner deuterium/tritium fuel cycle of ITER

Fusion engineering and design, 2003-09, Vol.69 (1), p.39-43

2003

Volltextzugriff (PDF)

Risk-based multi-criteria design concept of the ITER SDS getter bed

Fusion engineering and design, 2014-10, Vol.89 (7-8), p.1495-1499

2014

Volltextzugriff (PDF)

Micro-Channel Catalytic Reactor Integration in Caper and R&D on Highly Tritiated Water Handling and Processing

Fusion science and technology, 2015-03, Vol.67 (2), p.312-315

2015

Volltextzugriff (PDF)

Comparison of tritium retention and carbon deposition in JET and JT-60U

Journal of nuclear materials, 2005-10, Vol.345 (2-3), p.89-95

2005

Volltextzugriff (PDF)

Tritium removal from JET and TFTR tiles by a scanning laser

Journal of nuclear materials, 2003-03, Vol.313, p.496-500

2003

Volltextzugriff (PDF)

Evolution of ITER Tritium Confinement strategy and adaptation to Cadarache site conditions and French regulatory requirements

Fusion engineering and design, 2008-12, Vol.83 (10), p.1355-1358

2008

Volltextzugriff (PDF)

Commissioning of water detritiation and cryogenic distillation systems at TLK in view of ITER design

Fusion engineering and design, 2007-10, Vol.82 (15), p.2126-2132

2007

Volltextzugriff (PDF)

Disruption-Mitigation-Technology Concepts and Implications for ITER

IEEE transactions on plasma science, 2010-03, Vol.38 (3), p.419-424

2010

Volltextzugriff (PDF)

Tritium distribution on the surface of plasma facing carbon tiles used in JET

Journal of nuclear materials, 2003-03, Vol.313 (Complete), p.507-513

2003

Volltextzugriff (PDF)

Hydrogen Interaction with Nickel Containing Radiogenic Helium

Fusion science and technology, 2011-11, Vol.60 (4), p.1552-1555

2011

Volltextzugriff (PDF)

Tritium depth profiles in 2D and 4D CFC tiles from JET and TFTR

Journal of nuclear materials, 2003-03, Vol.313 (Complete), p.501-506

2003

Volltextzugriff (PDF)

Performance of a Full-Scale ITER Metal Hydride Storage Bed in Comparison with Requirements

Fusion science and technology, 2008-07, Vol.54 (1), p.22-26

2008

Volltextzugriff (PDF)

Experimental and simulation study on adsorption of hydrogen isotopes on MS5A at 77 K

Fusion engineering and design, 2007-10, Vol.82 (15), p.2303-2310

2007

Volltextzugriff (PDF)

Tritium tests with a technical PERMCAT for final clean-up of ITER exhaust gases

Fusion engineering and design, 2003-09, Vol.69 (1), p.51-56

2003

Volltextzugriff (PDF)

Experimental and simulation study on adsorption of hydrogen isotopes on MS5A at 77K

Fusion engineering and design, 2007-10, Vol.82 (15-24), p.2303-2310

2007

Volltextzugriff (PDF)

Tritium Confinement, Retention, and Releases at the Tritium Laboratory Karlsruhe

Fusion science and technology, 2008-07, Vol.54 (1), p.160-163

2008

Volltextzugriff (PDF)

Modeling of HT and HTO release from irradiated lithium metazirconate

Journal of nuclear materials, 2004-08, Vol.329, p.1274-1278

2004

Volltextzugriff (PDF)

1 – 25 von 161

Suche als RSS-Feed

Suchergebnisse filtern

Filter anzeigen

Nur zeigen

Geprüft (Peer-Review)
(144)
Mit Volltextzugriff
(144)

Publikationsform

Sprache

Erscheinungsjahr

n.n

Thema

Science & Technology
(106)
Technology
(100)
Nuclear Science & Technology
(95)
Tritium
(58)
Exact Sciences And Technology
(56)
Applied Sciences
(51)
Controled Nuclear Fusion Plants
(49)
Energy
(49)
Energy. Thermal Use Of Fuels
(49)
Installations For Energy Generation And Conversion: Thermal And Electrical Energy
(49)
70 Plasma Physics And Fusion Technology
(23)
Materials Science
(16)
Iter Tokamak
(15)
Iter
(14)
Deuterium
(13)
Materials Science, Multidisciplinary
(13)
Hydrogen
(11)
Nuclear Fuels
(11)
Physical Sciences
(11)
General Materials Science
(8)

15 weitere anzeigen...

Weniger anzeigen...

Zeitschrift / Serie

5 weitere anzeigen...

Weniger anzeigen...

Menü

Weitere Dienste

Einstellungen

The ITER tritium systems

Counter-current isotope swamping in a membrane reactor: The PERMCAT process and its applications in fusion technology

Tritium retention of plasma facing components in tokamaks

ITER fuel cycle R&D: Consequences for the design

Highly Tritiated Water Processing by Isotopic Exchange

Development of fusion fuel cycle technology at the Tritium Laboratory Karlsruhe: the experiment CAPRICE

Codes and standards and regulation issues for design and construction of the ITER mechanical components

Experimental validation of upgraded designs for PERMCAT reactors considering mechanical behaviour of Pd/Ag membranes under H2 atmosphere

The inner deuterium/tritium fuel cycle of ITER

Risk-based multi-criteria design concept of the ITER SDS getter bed

Micro-Channel Catalytic Reactor Integration in Caper and R&D on Highly Tritiated Water Handling and Processing

Comparison of tritium retention and carbon deposition in JET and JT-60U

Tritium removal from JET and TFTR tiles by a scanning laser

Evolution of ITER Tritium Confinement strategy and adaptation to Cadarache site conditions and French regulatory requirements

Commissioning of water detritiation and cryogenic distillation systems at TLK in view of ITER design

Disruption-Mitigation-Technology Concepts and Implications for ITER

Tritium distribution on the surface of plasma facing carbon tiles used in JET

Hydrogen Interaction with Nickel Containing Radiogenic Helium

Tritium depth profiles in 2D and 4D CFC tiles from JET and TFTR

Performance of a Full-Scale ITER Metal Hydride Storage Bed in Comparison with Requirements

Experimental and simulation study on adsorption of hydrogen isotopes on MS5A at 77 K

Tritium tests with a technical PERMCAT for final clean-up of ITER exhaust gases

Experimental and simulation study on adsorption of hydrogen isotopes on MS5A at 77K

Tritium Confinement, Retention, and Releases at the Tritium Laboratory Karlsruhe

Modeling of HT and HTO release from irradiated lithium metazirconate

Suchergebnisse filtern