Publications de Nadine Baluc | EPFL Graph Search

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As the upper temperature for use of reduced activation ferritic/martensitic steels is presently limited by a drop in mechanical strength at about 550 degrees C, Europe, Japan and the US are actively researching steels with high strength at higher operating ...

Materials design limits derived so far from the data generated in Europe for the reduced activation ferritic/martensitic (RAFM) steel type Eurofer are presented. These data address the short-term needs of the ITER Test Blanket Modules and a DEMOnstration fusion reactor. Products tested include plates, bars, tubes, TIG and EB welds, as well as powder consolidated blocks and solid-solid HIP joints. Effects of thermal ageing and low dose neutron irradiation are also included. Results are sorted and screened ac

In order to preserve the conditions for an environmentally safe machine, at present the selection of materials fur the structural components of fusion reactors is made not only on the basis of adequate mechanical properties, behaviour under irradiation, and compatibility with other materials and cooling media, but also on their radiological properties, i.e. radioactivity, decay heat and radiotoxicity. These conditions strongly limit the number of suitable materials to a few families of alloys, generically k

Precious alloys are subjected to a series of mechanical and thermal operations during manufacturing. For 18 carat gold alloys the processing operations can induce L1(0) ordered nanodomains, known to lead to the buildup of residual stresses, which are the p ...

Manufacturing of red gold components relies widely on controlling the formation of ordered precipitates during thermo-mechanical processing. The ordered phase hardens the material, makes it less workable and introduces residual stresses. We show that an in ...

The differences and similarities of behaviour between fee and bcc metals after irradiation have been investigated. For this purpose, fee Cu, Pd and 304 stainless steel and bcc Fe, Mo and Mo-5% Re were irradiated with either neutrons or 590 MeV protons at temperatures below recovery stage V. It is shown that a dense population of defect clusters (up to 10(22)-10(24) m(-3)) develops, the type of cluster formed depending apparently on the stacking fault energy. In the case of stacking fault tetrahedra formed i

Ferritic/martensitic (F/M) steels show good resistance to swelling and low damage accumulation upon irradiation relative to stainless steels. 0.3 wt% yttria particles were added to the F/M steel EUROFER 97 to produce oxide dispersion strengthened (ODS) ste ...

Irradiated 304 and 316 stainless steel samples were investigated. The steels were neutron irradiated to 1.5 and 7.5 dpa at 550 K. Similar types of steels were irradiated at 550 K with 590 MeV protons in the PIREX facility at PSI, Switzerland. The doses reached in this case were 0.15 and 0.3 dpa. The stress-strain relationships at different temperatures were measured. The irradiation and deformation microstructures were investigated using transmission electron microscopy (TEM). Two modes of deformation were

Oxide dispersion strengthened steels based on the ferritic/martensitic steel EUROFER97 are promising candidates for a fusion reactor because of their improved high temperature mechanical properties and their potential higher radiation resistance relative t ...

W-(0.3-2)Y2O3 and W-(0.3-2)Y materials (in wt.%) have been manufactured by conventional powder metallurgy methods including dry mechanical alloying of elemental powders in Ar atmosphere, cold pressing in air using a pressure in the range of 150-250 MPa and ...

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, i ...

Reduced activation ferritic/martensitic (RAFM) steels are the reference structural materials for future fusion reactors. They have proven to be a good alternative to austenitic steels for their higher swelling resistance, lower damage accumulation and improved thermal properties. However, irradiated RAFM steels exhibit a low temperature hardening and an increase in the ductile-to-brittle transition temperature, which imposes a severe restriction on reactor applications at temperatures below about 350degrees

The effects of neutron irradiation on the microstructure of welded joints made of austenitic stainless steels have been investigated. The materials were welded AISI 304 and AISI 347, so-called test weld materials, and irradiated with neutrons at 300 degree ...

Dislocation dynamics in a Ni-3(Al, Ta) single-crystal alloy have been studied by means of mechanical spectroscopy at intermediate temperatures, that is in the temperature range of the flow stress anomaly. The mechanical loss of specimens predeformed at 300 K was found to be strongly dependent on temperature, pre-deformation level and heating rate. Thermal cycling (heating-cooling) and ageing experiments were also performed, which provided additional information about the annealing time dependence of the mec

Examples of the observation and analysis of dislocation cores and dislocation fine structure in metals and intermetallics using high resolution transmission electron microscopy are discussed. Specific examples include the 60 degrees dislocations in aluminu ...

Radiation effects on the mechanical behavior and the microstructure of pure her, titanium polycrystals have been investigated. Results have been analyzed in the frame of a dispersed obstacle hardening model and compared to those previously obtained for pure metals with a fcc or bee structure. such as Cu and I'd or Fe. respectively. Differences in the defect accumulation rate and the dose dependence of hardening are discussed in terms of possible irradiation hardening mechanisms for the hcp structure. (C) 20

Poly-quasicrystalline samples of an icosahedral Al-Cu-Fe alloy have been deformed in compression tests under constant-strain-rate conditions at temperatures ranging from room temperature up to 1020 K (m approximate to 1150 K, where T-m is the melting temperature). The activation volumes, which were measured by performing load relaxation experiments, were found to be small and reveal that two different thermally activated mechanisms belonging to two different temperature regimes, are responsible for plastic

Polycrystalline specimens of the ferritic-martensitic OPTIMAX A steel have been irradiated on the one hand with neutrons at 523 K to a dose of 2.5 dpa and with 590 MeV protons at ambient temperature and 523 K to doses of about 0.3 and 1 dpa on the other. Charpy tests reveal a shift of the ductile-to-brittle transition temperature from about 190 to 268 K in the neutron-irradiated steel. Proton irradiations at ambient temperature lead to hardening and reduction of tensile ductility of the material. Both pheno

Irradiation induces the formation of stacking fault tetrahedra (SFTs) in a number of fcc metals, such as stainless steel and pure copper. In order to understand the role of the material's parameters on this formation, pure Cu, Ni, Pd and Al, having a respe ...

In fusion power reactors, the plasma facing and breeding-blanket components will suffer intense irradiation by 14MeV neutrons. These high-energy fusion neutrons will produce atomic displacement cascades and nuclear transmutation reactions inside the irradi ...

Nadine Baluc

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Optimization of the chemical composition and manufacturing route for ODS RAF steels for fusion reactor application

Materials design data for reduced activation martensitic steel type EUROFER

Structural materials for fusion reactors

Influence of thermo-mechanical history on the ordering kinetics in 18 carat Au alloys

Enhanced precipitate growth at reduced temperatures during chemical ordering in deformed red gold alloys

The microstructure and associated tensile properties of irradiated fcc and bcc metals

Effect of irradiation on the microstructure and the mechanical properties of oxide dispersion strengthened low activation ferritic/martensitic steel

The effects of irradiation and testing temperature on tensile behaviour of stainless steels

Microstructural development under irradiation in European ODS ferritic/martensitic steels

Sintering and characterization of W–Y and W–Y2O3 materials

From materials development to their test in IFMIF: an overview

On the potentiality of using ferritic/martensitic steels as structural materials for fusion reactors

Welding-induced microstructure in austenitic stainless steels before and after neutron irradiation

Strain-amplitude-dependent mechanical loss at intermediate temperatures in a Ni-3(Al, Ta) single crystal

HRTEM of dislocation cores and thin-foil effects in metals and intermetallic compounds

Structure-mechanics relationships in proton irradiated pure titanium

Activation parameters of plastic flow in icosahedral Al-Cu-Fe

The mechanical properties and microstructure of the OPTIMAX series of low activation ferritic-martensitic steels

Irradiation-induced stacking fault tetrahedra in fcc metals

Material degradation under DEMO relevant neutron fluences