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Design requirements for SiC/SiC composites structural material in fusion power reactor blankets

Fusion engineering and design, 1998-09, Vol.41 (1), p.165-171

1998

Volltextzugriff (PDF)

Conceptual design of a high temperature water-cooled divertor for a fusion power reactor

Fusion engineering and design, 2005-11, Vol.75, p.383-386

2005

Volltextzugriff (PDF)

Simulation experimental investigation of plasma off-normal events on advanced silicon doped CFC-NS31

Journal of nuclear materials, 2002-12, Vol.307, p.100-105

2002

Volltextzugriff (PDF)

Progress of the European R&D on plasma–wall interactions, neutron effects and tritium removal in ITER plasma facing materials

Fusion engineering and design, 2001-10, Vol.56, p.179-187

2001

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Determination of the lithium diffusion coefficient in irradiated boron carbide pellets

Journal of nuclear materials, 1999-03, Vol.265 (3), p.321-324

1999

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Neutron effects on properties and annealing of low-Z materials

Fusion engineering and design, 2000-11, Vol.49, p.383-388

2000

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Carbon fiber composites application in ITER plasma facing components

Journal of nuclear materials, 1998-10, Vol.258, p.149-159

1998

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The effect of high-dose neutron irradiation on the properties of graphite and silicon carbide

Journal of nuclear materials, 1994, Vol.208 (1), p.1-7

1994

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European development of prototypes for ITER high heat flux components

Fusion engineering and design, 2000-11, Vol.49, p.135-143

2000

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Neutron irradiation effects on the thermal conductivity and dimensional stability of carbon fiber composites at divertor conditions

Journal of nuclear materials, 1996-03, Vol.228 (2), p.155-161

1996

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EU results on neutron effects on PFC materials

Fusion engineering and design, 1998-09, Vol.39 (1-4), p.263-273

1998

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European development of the ITER divertor target

Fusion engineering and design, 1999-11, Vol.46 (2), p.221-228

1999

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Neutron irradiation effects on the thermal conductivity and the dimensional stability of carbon fiber composites

Physica scripta, 1996-01, Vol.1996, p.26-31

1996

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Neutron irradiation effects on carbon based materials at 350°C and 800°C

Journal of nuclear materials, 2000, Vol.277 (2), p.351-359

2000

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Thermal conductivity changes in graphites and carbon/carbon fiber materials induced by low neutron damages

Journal of nuclear materials, 1994-09, Vol.212, p.1168-1173

1994

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Neutron induced dimensional changes in carbon materials at high temperatures and high damage doses

Journal of nuclear materials, 1994-09, Vol.212, p.1218-1222

1994

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Neutron irradiation effects on the properties of carbon materials

Journal of nuclear materials, 1994-09, Vol.212, p.416-420

1994

Volltextzugriff (PDF)

Neutron irradiation effects on carbon based materials at 350 deg C and 800 deg C

Journal of nuclear materials, 2000-02, Vol.277 (2-3), p.351-359

2000

Volltextzugriff (PDF)

Determination of the lithium diffusion coefficient in irradiated boron carbide pellets

Journal of nuclear materials, 1998-02, Vol.265 (3), p.321-324

1998

Volltextzugriff (PDF)

Neutron induced thermal properties changes in carbon fiber composites irradiated from 600 to 1000°C

Journal of nuclear materials, 1996-06, Vol.230 (3), p.271-279

1996

Volltextzugriff (PDF)

Nuclear microprobe analysis of exp 7 Li profile induced in HfB sub 2 by a neutron irradiation

Journal of nuclear materials, 2001-09, Vol.297 (3), p.244-250

2001

Volltextzugriff (PDF)

Nuclear microprobe analysis of 7Li profile induced in HfB2 by a neutron irradiation

Journal of nuclear materials, 2001-09, Vol.297 (3), p.244-250

2001

Volltextzugriff (PDF)

Neutron effects on properties and annealing of low-Z materials

Fusion engineering and design, 1999-09, Vol.49-50, p.383-388

1999

Volltextzugriff (PDF)

Simulation experimental investigation of plasma off-normal events on advanced silicon doped CFC-NS31

Journal of nuclear materials, 2002, Vol.307-11, p.100-105

2002

Volltextzugriff (PDF)

Design requirements for SiC/SiC composites structural material in fusion power reactor blankets

Fusion engineering and design, 1998-09, Vol.41 (Pt B), p.165-171

1998

Volltextzugriff (PDF)

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Design requirements for SiC/SiC composites structural material in fusion power reactor blankets

Conceptual design of a high temperature water-cooled divertor for a fusion power reactor

Simulation experimental investigation of plasma off-normal events on advanced silicon doped CFC-NS31

Progress of the European R&D on plasma–wall interactions, neutron effects and tritium removal in ITER plasma facing materials

Determination of the lithium diffusion coefficient in irradiated boron carbide pellets

Neutron effects on properties and annealing of low-Z materials

Carbon fiber composites application in ITER plasma facing components

The effect of high-dose neutron irradiation on the properties of graphite and silicon carbide

European development of prototypes for ITER high heat flux components

Neutron irradiation effects on the thermal conductivity and dimensional stability of carbon fiber composites at divertor conditions

EU results on neutron effects on PFC materials

European development of the ITER divertor target

Neutron irradiation effects on the thermal conductivity and the dimensional stability of carbon fiber composites

Neutron irradiation effects on carbon based materials at 350°C and 800°C

Thermal conductivity changes in graphites and carbon/carbon fiber materials induced by low neutron damages

Neutron induced dimensional changes in carbon materials at high temperatures and high damage doses

Neutron irradiation effects on the properties of carbon materials

Neutron irradiation effects on carbon based materials at 350 deg C and 800 deg C

Determination of the lithium diffusion coefficient in irradiated boron carbide pellets

Neutron induced thermal properties changes in carbon fiber composites irradiated from 600 to 1000°C

Nuclear microprobe analysis of exp 7 Li profile induced in HfB sub 2 by a neutron irradiation

Nuclear microprobe analysis of 7Li profile induced in HfB2 by a neutron irradiation

Neutron effects on properties and annealing of low-Z materials

Simulation experimental investigation of plasma off-normal events on advanced silicon doped CFC-NS31

Design requirements for SiC/SiC composites structural material in fusion power reactor blankets

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