Structural materials for DEMO: The EU development, strategy, testing and modelling

Lässer, R.; Baluc, N.; Boutard, Jean-Louis; Diegele, E.; Dudarev, S. L.; Gasparotto, M.; Möslang, A.; Pippan, Reinhard; Riccardi, B.; Schaaf, B. van der

doi:10.1016/j.fusengdes.2007.06.031

Cited by 76 publications

(48 citation statements)

References 35 publications

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“…The density of precipitates on the grain boundaries increases after annealing up to 1000 K. We found some Ta-rich carbides, W-rich carbides and few V-rich carbides after annealing of Eurofer at 1000 K. This is in agreement with [20]. Randomly distributed regions of large ferritic grains retained after the heat treatments as it was also mentioned in [20]. Transmission electron microscopy (TEM) analysis confirms the microstructural analysis suggested by SEM, showing ferritic matrix with carbides precipitated at grain boundaries (GBs) and within the grains in all the heat-treated samples [23].…”

Section: Materials and Samplessupporting

confidence: 90%

Surface modification and deuterium retention in reduced-activation steels under low-energy deuterium plasma exposure. Part I: undamaged steels

et al. 2016

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Section: Materials and Samplessupporting

confidence: 90%

Surface modification and deuterium retention in reduced-activation steels under low-energy deuterium plasma exposure. Part I: undamaged steels

et al. 2016

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“…Tungsten is a promising candidate for the plasma-facing components of a future fusion reactor due to its unique combination of properties such as the very high melting point or the good thermal conductivity [1,2]. However, tungsten features a ductile-to-brittle transition (DBT), which isdepending on the type of experiment and fabrication route -at several hundred degrees centigrade.…”

Section: Introductionmentioning

confidence: 99%

“…The occurrence of a DBT means that below a certain temperature tungsten behaves brittle. In addition, tungsten is heavily embrittled both by recrystallization and neutrons from the fusion reaction [1][2][3]. Numerous efforts are undertaken to overcome these problems.…”

Section: Introductionmentioning

confidence: 99%

Enhanced toughness and stable crack propagation in a novel tungsten fibre-reinforced tungsten composite produced by chemical vapour infiltration

et al. 2014

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Abstract. Tungsten is a promising candidate for the plasma-facing components of a future fusion reactor, but its use is strongly restricted by its inherent brittleness. An innovative concept to overcome this problem is tungsten fibre-reinforced tungsten composite. In this article we present the first mechanical test of such a composite material using a sample containing multiple fibres. The in-situ fracture experiment was performed in a scanning electron microscope for close observation of the propagating crack. Stable crack propagation accompanied with rising load bearing capacity is observed. The fracture toughness is estimated using the test results and the surface observation.

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“…One substantial disadvantage of EUROFER 97 ODS is that it has a very high DBTT. The mechanical and physical properties and the effect of heat treatments on EUROFER variants have been widely studied [1][2][3]. The aim of this study is to take a combined approach, looking at the effect of solution treatment (ST) temperature and cooling rate on both the microstructure and DBTT.…”

Section: Introductionmentioning

confidence: 99%

Effects of heat treatment conditions on the microstructure and impact properties of EUROFER 97 ODS steel

Martino¹,

Faulkner²,

Riddle³

et al. 2011

Phys. Scr.

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Probably the most important range of materials to consider for the blanket material in the tokamak design for fusion reactors such as ITER and DEMO is the high alloy Fe9Cr oxide dispersion strengthened (ODS) ferritic steels. These steels possess exceptional thermal conductivity and low thermal expansion while being strongly resistant to void swelling. Their main drawback is the high ductile-to-brittle transition temperature (DBTT), particularly in the ODS versions of the material. This paper describes attempts that are being made to reduce this DBTT in as yet unirradiated materials by a novel heat treatment procedure. The principle behind this approach is that low DBTT in the unirradiated materials will lead to relatively low DBTT even in He-containing material that has been irradiated with fusion blanket-type irradiations. New batches of high alloy Fe9Cr ODS (EUROFER) ferritic steel have been produced by a powder metallurgical route, and relatively homogeneous material has been produced by a hot isostatic pressing procedure. Mini-Charpy test specimens were made from materials that had been subjected to a matrix of heat treatments designed to show up variations in solution treatment (ST) temperature, cooling rate from the ST temperature and tempering treatment. The initial DBTT was in the range 150-200 • C. Extremely interesting results have been obtained. DBTT downward shifts of up to 200 • C have been observed by using a high 1300 • C ST temperature and a low cooling rate. The paper goes on to describe the microstructure of this material, and discusses the possible microstructural factors needed to produce these very high DBTT downward shifts. Low dissolved carbon and higher proportions of low-angle grain boundaries seem to provide the key to the understanding of the alloy behaviour.

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Structural materials for DEMO: The EU development, strategy, testing and modelling

Cited by 76 publications

References 35 publications

Surface modification and deuterium retention in reduced-activation steels under low-energy deuterium plasma exposure. Part I: undamaged steels

Surface modification and deuterium retention in reduced-activation steels under low-energy deuterium plasma exposure. Part I: undamaged steels

Enhanced toughness and stable crack propagation in a novel tungsten fibre-reinforced tungsten composite produced by chemical vapour infiltration

Effects of heat treatment conditions on the microstructure and impact properties of EUROFER 97 ODS steel

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