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The ITER tritium systems

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

2007

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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

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Tritium retention of plasma facing components in tokamaks

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

2003

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ITER fuel cycle R&D: Consequences for the design

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

2006

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Highly Tritiated Water Processing by Isotopic Exchange

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

2015

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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

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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

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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

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The inner deuterium/tritium fuel cycle of ITER

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

2003

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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

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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

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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

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Tritium removal from JET and TFTR tiles by a scanning laser

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

2003

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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

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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

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Disruption-Mitigation-Technology Concepts and Implications for ITER

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

2010

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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

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Hydrogen Interaction with Nickel Containing Radiogenic Helium

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

2011

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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

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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

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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

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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

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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

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

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

2008

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Modeling of HT and HTO release from irradiated lithium metazirconate

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

2004

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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

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