Present development status of EUROFER and ODS-EUROFER for application in blanket concepts

Lindau, R.; Möslang, A.; Rieth, M.; Klimiankou, M.; Materna-Morris, E.; Alamo, A.; Tavassoli, A.A.; Cayron, Cyril; Lancha, A.M.; Fernández, P.; Baluc, N.; Schäublin, R.; Diegele, E.; Filacchioni, G.; Rensman, J.W.; Schaaf, B. van der; Lucon, Enrico; Dietz, W.

doi:10.1016/j.fusengdes.2005.06.186

Cited by 431 publications

(179 citation statements)

References 16 publications

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“…Eurofer97 steel is targeted to be used as structural material for ITER blanket test units and in future versions of fusion reactors [1]. Mechanically alloyed oxide dispersion strengthened ODS Eurofer steel was developed on the base of Eurofer 97 steel to increase creep-rupture resistance [1][2].…”

Section: Introductionmentioning

confidence: 99%

Evolution of microstructure in advanced ferritic-martensitic steels under irradiation: the origin of low temperature radiation embrittlement

et al. 2016

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Advanced reduced activation ferritic/martensitic steels and oxide dispersion-strengthened steels exhibit significant radiation embrittlement under low temperature neutron irradiation. In this study we focused on atom probe tomography (APT) of Eurofer97 and ODS Eurofer steels irradiated with neutrons and heavy ions at low temperatures. Previous TEM studies revealed dislocation loops in the neutron-irradiated f\m steels. At the same time, our APT showed early stages of solid solution decomposition. High density (10 24 m -3 ) of ~3-5 nm clusters enriched in chromium, manganese, and silicon atoms were found in Eurofer 97 irradiated in BOR-60 reactor to 32 dpa at 332°C. In this steel irradiated with Fe ions up to the dose of 24 dpa, pair correlation functions calculated using APT data showed the presence of Cr-enriched pre-phases.APT study of ODS Eurofer found a significant change in the nanocluster composition after neutron irradiation to 32 dpa at 330 °C and an increase in cluster number density. APT of ODS steels irradiated with Fe ions at low temperatures revealed similar changes in nanoclusters.These results suggest that irradiation-induced nucleation and evolution of very small precipitates may be the origin of low temperature radiation embrittlement of f\m steels.

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Section: Introductionmentioning

confidence: 99%

Evolution of microstructure in advanced ferritic-martensitic steels under irradiation: the origin of low temperature radiation embrittlement

et al. 2016

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“…Due to its mechanical properties, long-term stability and predictability up to ∼650 • C, the reduced activation ferritic-martensitic EUROFER 97 steel is being considered for structural applications in the breeding blankets of ITER, and for the demonstration fusion reactor DEMO [1,2]. The strength of this steel can be enhanced by precipitation hardening, and strengthening induced by dislocations, particle dispersion or grain boundaries.…”

Section: Introductionmentioning

confidence: 99%

Texture and mechanical properties of EUROFER 97 steel processed by ECAP

Eddahbi

Monge

Fernández

et al. 2011

Materials Science and Engineering: A

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Abstract:The EUROFER 97 steel was processed by equal channel angular pressing (ECAP) at 550 • C for four passes via route C. The starting material consisted of ferrite-martensite dual phase composed by small subgrains of about 0.5 m and low angle boundaries less than 5 • . The volume fraction of second phase particles was around 10 vol.%, besides a texture formed by several fibers orientations belonging to the zone axes 110 , 111 and 112 . Increasing ECAP deformation, this microstructure became into equiaxed grain structures of less than 1 m, and the misorientation between contiguous grains increased. This refine-ment of the microstructure was accompanied by the development of a new texture described by a family of fiber orientations related by rotations around axes 110 and 111 . Tensile tests have revealed that an ECAP treatment at 550 • C for two passes could significantly strengthen the tempered material still maintaining good ductility.

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“…The upper temperature for use of reduced activation ferritic/martensitic (RAFM) steels destined to structural applications in fusion power reactors is presently limited by a drop in mechanical strength at about 820 K [1]. ODS RAFM steels and ODS RAF steels appear promising structural materials for use up to about 920 K [1] and 1020 K [2], respectively.…”

Section: Development Of Advanced Metallic Materialsmentioning

confidence: 99%

“…ODS RAFM steels and ODS RAF steels appear promising structural materials for use up to about 920 K [1] and 1020 K [2], respectively. The upper temperature for use of ODS RAFM steels (which contain typically between 7 and 9 wt% Cr) can be increased only by about 100 K with respect to that of RAFM steels (7-9 wt% Cr), as it is actually restricted by the ferrite to austenite transformation (γ -loop in the phase diagram).…”

Section: Development Of Advanced Metallic Materialsmentioning

confidence: 99%

From materials development to their test in IFMIF: an overview

Baluc¹,

Schäublin²,

Spätig³

et al. 2011

Nucl. Fusion

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R&D activities on fusion reactor materials in Switzerland focus on (1) the development of advanced metallic materials for structural applications in plasma-facing (first wall, divertor) and breeding blanket components of the future fusion power reactors, in particular oxide dispersion strengthened reduced activation ferritic steels and tungsten-base materials, (2) the modelling of radiation damage and radiation effects and (3) small specimen test technology for the future International Fusion Materials Irradiation Facility. The main objectives, examples of recent results and future activities are described in the case of these three R&D areas.

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Present development status of EUROFER and ODS-EUROFER for application in blanket concepts

Cited by 431 publications

References 16 publications

Evolution of microstructure in advanced ferritic-martensitic steels under irradiation: the origin of low temperature radiation embrittlement

Evolution of microstructure in advanced ferritic-martensitic steels under irradiation: the origin of low temperature radiation embrittlement

Texture and mechanical properties of EUROFER 97 steel processed by ECAP

From materials development to their test in IFMIF: an overview

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