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Overview of recent European materials R&D activities related to ITER

Journal of nuclear materials, 2004-08, Vol.329, p.173-177

2004

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Design and performance of shattered pellet injection systems for JET and KSTAR disruption mitigation research in support of ITER

Nuclear fusion, 2021-10, Vol.61 (10), p.106001

2021

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Dust and flakes in the JET MkIIa divertor, analysis and results

Journal of nuclear materials, 1999-03, Vol.266, p.423-428

1999

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Politica "fiscale": viva o morta?

Moneta e Credito, 2014-03, Vol.31 (123)

2014

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Is fiscal policy dead?

PSL quarterly review, 2014-01, Vol.31 (125)

2014

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Experiments on the release of tritium from the first wall of JET

Nuclear fusion, 1993-09, Vol.33 (9), p.1389-1404

1993

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The use of thin layer activation to evaluate ion beam surface treatments of orthopaedic implant materials

Surface & coatings technology, 2007-08, Vol.201 (19), p.8070-8075

2007

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Modification of the carbon and beryllium walls in JET by erosion, redeposition and deuterium trapping after the 1991 discharge period

Journal of nuclear materials, 1994-09, Vol.212, p.1245-1249

1994

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Mechanical and thermo-physical characterization of three-directional carbon fiber composites for W-7X and ITER

Fusion engineering and design, 2009-06, Vol.84 (7), p.1525-1530

2009

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Consolidation of HIP bonding technologies for the ITER first wall panels

Fusion engineering and design, 2007-10, Vol.82 (15), p.1806-1812

2007

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Development of a copper alloy to beryllium HIP bonding technology for the ITER first wall

Fusion engineering and design, 2005-11, Vol.75, p.377-381

2005

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Application of a diffusion bonding methodology to develop a Be/Cu HIP bond suitable for the ITER blanket

Fusion engineering and design, 2003-09, Vol.66, p.425-429

2003

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EU contributions to the ITER materials properties data assessment

Fusion engineering and design, 2005-11, Vol.75, p.703-707

2005

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Wall erosion and material transport to the Mark I carbon divertor of JET

Journal of nuclear materials, 1999-03, Vol.266 (1-3), p.604-610

1999

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Full scale electrical insulation coating development

Fusion engineering and design, 2003-09, Vol.69 (1), p.303-307

2003

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Tritium inventory in the first wall of JET

Fusion engineering and design, 2000-11, Vol.49, p.745-752

2000

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Transport and Redeposition of Eroded Material in JET

Physica scripta, 1999-01, Vol.1999 (1), p.13

1999

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Erosion at the vessel walls of JET

Journal of nuclear materials, 1997-02, Vol.241, p.469-475

1997

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Beryllium plasma-facing components: JET experience

Fusion engineering and design, 1997-11, Vol.37 (4), p.515-530

1997

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Deuterium trapping and impurity collection on a 1990 JET Be belt limiter

Journal of nuclear materials, 1992-12, Vol.196, p.729-734

1992

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Interpretation of deuterium pumping by plasma-facing beryllium surfaces

Journal of nuclear materials, 1992-12, Vol.196, p.997-1001

1992

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JET experience in recovery from large air leak incidents

Journal of nuclear materials, 1993-05, Vol.200 (3), p.395-399

1993

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Assessment of water-cooled beryllium components for plasma-facing applications

Journal of nuclear materials, 1994-09, Vol.212, p.1266-1271

1994

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Hydrogen, deuterium, and tritium isotope exchange experiments in JET

Journal of nuclear materials, 1992-12, Vol.196, p.139-142

1992

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Sozialpolitik in liberaler Sicht

Schweizer Monatshefte, 1957-03, Vol.36 (12), p.941

Peacock, A.T

1957

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Overview of recent European materials R&D activities related to ITER

Design and performance of shattered pellet injection systems for JET and KSTAR disruption mitigation research in support of ITER

Dust and flakes in the JET MkIIa divertor, analysis and results

Politica "fiscale": viva o morta?

Is fiscal policy dead?

Experiments on the release of tritium from the first wall of JET

The use of thin layer activation to evaluate ion beam surface treatments of orthopaedic implant materials

Modification of the carbon and beryllium walls in JET by erosion, redeposition and deuterium trapping after the 1991 discharge period

Mechanical and thermo-physical characterization of three-directional carbon fiber composites for W-7X and ITER

Consolidation of HIP bonding technologies for the ITER first wall panels

Development of a copper alloy to beryllium HIP bonding technology for the ITER first wall

Application of a diffusion bonding methodology to develop a Be/Cu HIP bond suitable for the ITER blanket

EU contributions to the ITER materials properties data assessment

Wall erosion and material transport to the Mark I carbon divertor of JET

Full scale electrical insulation coating development

Tritium inventory in the first wall of JET

Transport and Redeposition of Eroded Material in JET

Erosion at the vessel walls of JET

Beryllium plasma-facing components: JET experience

Deuterium trapping and impurity collection on a 1990 JET Be belt limiter

Interpretation of deuterium pumping by plasma-facing beryllium surfaces

JET experience in recovery from large air leak incidents

Assessment of water-cooled beryllium components for plasma-facing applications

Hydrogen, deuterium, and tritium isotope exchange experiments in JET

Sozialpolitik in liberaler Sicht

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