TY - GEN
T1 - Tungsten and Beryllium Armour Development for the JET ITER-like Wall Project
AU - Likonen, J.
AU - Maier, H.
AU - et al., null
AU - JET-EFDA contributors
PY - 2006
Y1 - 2006
N2 - The operational behaviour and the interplay of the ITER plasma facing material choice has never been investigated in a tokamak experiment. This motivated the ITER-like Wall Project at JET in which the present main chamber CFC tiles will be exchanged with Be tiles and in parallel a fully tungsten-clad divertor will be prepared. Among the scientific objectives of the ITER-like Wall project are general questions of plasma operation with a low melting Be wall, compatibility of all envisaged ITER scenarios with a W divertor, tritium retention and removal and mixed materials effects, erosion behaviour and lifetime investigations. For the tungsten divertor, two R&D programs were initiated: Forschungszentrum Jülich, Germany, developed a conceptual design for a bulk W horizontal target plate, based on an assembly of tungsten blades. For all other divertor parts five Euratom Fusion Associations performed R&D to provide the technology to coat the 2-directional CFC material used at JET with thin tungsten coatings. In addition, beryllium coatings for the first wall inconel steel are developed. In a first screening, the tungsten coated CFC tiles were subjected to heat loads with power densities ranging from 6 MW/m2 to 22 MW/m2 with surface temperatures exceeding 2000oC. In a second step, a selection of coatings was exposed to cyclic heat loading for 200 pulses at 10 MW/m2 for 5 s corresponding to surface temperatures of about 1600oC. All coatings tested developed cracks perpendicular to the CFC fibres due to the stronger contraction of the coating upon cool-down after the heat pulses. For the bulk tungsten, a design with an an assembly of tungsten blades was developed. To minimise electromagnetic forces the design consists of stacks of tungsten blades of 6 mm width that are insulated in toroidal direction. High heat flux tests of a test module were performed on the electron beam facility JUDITH at a nominal power and duration of (7 MW/m2, 10 s) for 100 pulses and finally with increasing power loads leading to surface temperatures in excess of 3000oC. No macroscopic failure occurred during the test while SEM showed the development of microcracks at grain boundaries.
AB - The operational behaviour and the interplay of the ITER plasma facing material choice has never been investigated in a tokamak experiment. This motivated the ITER-like Wall Project at JET in which the present main chamber CFC tiles will be exchanged with Be tiles and in parallel a fully tungsten-clad divertor will be prepared. Among the scientific objectives of the ITER-like Wall project are general questions of plasma operation with a low melting Be wall, compatibility of all envisaged ITER scenarios with a W divertor, tritium retention and removal and mixed materials effects, erosion behaviour and lifetime investigations. For the tungsten divertor, two R&D programs were initiated: Forschungszentrum Jülich, Germany, developed a conceptual design for a bulk W horizontal target plate, based on an assembly of tungsten blades. For all other divertor parts five Euratom Fusion Associations performed R&D to provide the technology to coat the 2-directional CFC material used at JET with thin tungsten coatings. In addition, beryllium coatings for the first wall inconel steel are developed. In a first screening, the tungsten coated CFC tiles were subjected to heat loads with power densities ranging from 6 MW/m2 to 22 MW/m2 with surface temperatures exceeding 2000oC. In a second step, a selection of coatings was exposed to cyclic heat loading for 200 pulses at 10 MW/m2 for 5 s corresponding to surface temperatures of about 1600oC. All coatings tested developed cracks perpendicular to the CFC fibres due to the stronger contraction of the coating upon cool-down after the heat pulses. For the bulk tungsten, a design with an an assembly of tungsten blades was developed. To minimise electromagnetic forces the design consists of stacks of tungsten blades of 6 mm width that are insulated in toroidal direction. High heat flux tests of a test module were performed on the electron beam facility JUDITH at a nominal power and duration of (7 MW/m2, 10 s) for 100 pulses and finally with increasing power loads leading to surface temperatures in excess of 3000oC. No macroscopic failure occurred during the test while SEM showed the development of microcracks at grain boundaries.
M3 - Conference article in proceedings
T3 - IAEA Conference Proceedings
BT - Fusion Energy 2006
PB - International Atomic Energy Agency IAEA
T2 - 21st IAEA Fusion Energy Conference
Y2 - 16 October 2006 through 21 October 2006
ER -
