Showing papers in "Journal of Nuclear Materials in 2004"

TL;DR: In this article, the authors show that the performance of tungsten surfaces under intense transient thermal loads is another critical issue, since the formation of a melt layer may favor the generation of highly activated dust particles.

TL;DR: In this paper, an object kinetic Monte Carlo (OKMC) method was developed to investigate the evolution of radiation damage in simple Fe alloys (Fe, Fe-Cu) under irradiation conditions (temperature, dose and dose-rate) typical of experiments with different impinging particles and also operating conditions.

TL;DR: In this paper, the development of fundamental knowledge to support alloy design strategies for resistance to irradiation and to form a scientific basis to develop better materials is discussed, and a database supporting designs is presented.

TL;DR: In this article, a detailed study of oxides formed in 360 °C water on four Zr-based alloys (Zircaloy-4, ZIRLO™,1 Zr−2.5%Nb and Zr•2.9%Cu) was undertaken to relate oxide structure to corrosion performance.

TL;DR: In this article, the formation mechanism of micron-sized He bubbles and holes in powder metallurgy tungsten due to helium ion irradiation with an ion energy below 30 eV and a particle flux above 1022 m−2 ǫ s−1 has been performed in the linear divertor plasma simulator NAGDIS-II.

TL;DR: In this paper, the defect production fundamentals in neutron-irradiated face centered cubic and body centered cubic (BCC) metals are briefly reviewed, based primarily on transmission electron microscope observations.

TL;DR: In this article, annealing experiments have been performed to assess the change in grain size induced by irradiation, and experimentally showing the resistance of nanostructured material to radiation damage.

TL;DR: SiCf/SiC composites are among the most promising candidate structural materials for fusion because of their potential application for high performance reactors and superior safety characteristics compared to metallic materials as mentioned in this paper.

TL;DR: The microstructure of a commercial mechanically-alloyed oxide dispersion strengthened MA957 alloy has been characterized in the as-received condition and after annealing for up to 24 h at 1300 °C (∼0.85 Tm) by atom probe tomography and electron microscopy.

TL;DR: In this article, two low-enriched uranium fuel plates consisting of U-7wt%Mo atomized powder dispersed in an aluminum matrix, have been irradiated in the FUTURE irradiation rig of the BR2 reactor at SCK•CEN.

TL;DR: In this article, the mechanical properties of ODS-ferritic alloy, Fe-14Cr-1Ti-0.25Y2O3 (MA957), were evaluated with two microstructures characterized by different grain sizes and degree of crystallographic texture.

TL;DR: In this article, the structure and composition of ODS steels were analyzed using HRTEM and energy-filtered transmission electron microscopy (EFTEM) to obtain a strong correlation of the orientation of the ODS particles with the lattice.

TL;DR: In this article, the thermal diffusivity and specific heat of UO 2 fuel have been measured starting from end-of-life conditions at various burn-ups, and measurements under thermal annealing cycles were performed in order to investigate the recovery of the thermal conductivity as a function of temperature.

TL;DR: The International Fusion Materials Irradiation Facility (IFMIF) as mentioned in this paper has been proposed to fill a critical need for fusion materials development, which can provide safe, economical, and environmentally acceptable energy.

TL;DR: In this article, a novel SiC/SiC composite, which has recently been developed through nano-infiltration and transient eutectic phase (NITE) processing route, surpasses conventional materials in many of these properties.

TL;DR: The thermal and irradiation creep behavior of V-4Cr-4Ti is summarized along with an overview of the effects of interstitial impurities on tensile properties in this paper.

TL;DR: Significant progress has been achieved in the international research effort on reduced-activation steels as discussed by the authors, and extensive tensile, fracture toughness, fatigue and creep properties in unirradiated and irradiated conditions have been performed and evaluated.

TL;DR: In this article, the deuterium permeability of α-alumina has been investigated at Eurofer in the temperature range 573-873 K at driving pressures 10 3 -10 5 Pa.

TL;DR: A modular He-cooled divertor concept with integrated pin array (HEMP) is being developed at the Forschungszentrum Karlsruhe to achieve a high heat flux of at least about 10–15 MW/m 2, proposed for a near-term reactor model like DEMO.

TL;DR: In this article, the authors investigated the effects of irradiation on three austenitic stainless steels, SA 304L, CW 316 and CW Ti-modified 316, both experimentally and theoretically.

TL;DR: A large database of intergranular porosity development on irradiated fuels has been provided by the PIE campaigns as mentioned in this paper, from which, from these, models of bubble growth, coalescence, morphological relaxation and venting have been developed.

TL;DR: In this paper, materials design limits for the reduced activation ferritic/martensitic (RAFM) steel type Eurofer are presented, which address the short-term needs of the ITER Test Blanket Modules and a DEMOnstration fusion reactor.

TL;DR: In this article, the available data for Frenkel pair resistivity and the experimental data for damage resistivity rate in metals were compiled and analyzed, and the defect production efficiency has been calculated with the help of the binary collision approximation model.

TL;DR: The deformation microstructures of neutron-irradiated nuclear structural alloys, A533B steel, 316 stainless steel, and Zircaloy-4, have been investigated by tensile testing and transmission electron microscopy to map the extent of strain localization processes in plastic deformation as mentioned in this paper.

TL;DR: In this article, the results of steel exposure up to 7200 h in flowing liquid eutectic Pb 45 Bi 55 (LBE) at elevated temperatures were presented.

TL;DR: In this article, the authors evaluated the synergistic effect of helium and hydrogen on Fe-Cr ferritic model alloys, to provide basic understanding concerning development of fusion reactor components.

TL;DR: In this paper, different ODS EUROFER steels reinforced with Y2O3 and MgAl2O4 were elaborated by mechanical milling and hot isostatic pressing.

TL;DR: In this article, the alteration of SON68 glass (inactive R7T7 type glass) in alkaline (NaOH and KOH) solution was studied at pH 11.4 at 90 C and at an S=V ratio of 65 cm � 1.

TL;DR: In this article, the effects of cold work and low-temperature sensitization heat treatment of non-sensitized austenitic stainless steels have been investigated and related to the cracking in nuclear power reactors.