Showing papers in "Journal of Nuclear Materials in 1998"

TL;DR: A critical review of the extensive literature on the air oxidation of UO2 at temperatures below 400°C is presented in this article, where the key parameters that affect the rate of air oxidation are examined systematically and their importance to the reaction rate is evaluated.

TL;DR: In this article, material properties up to high temperatures are presented for lanthanated and W-Re alloys, and the impact on fusion application is discussed Recently developed coatings of chemical vapor deposited tungsten (CVD-W) on copper substrates have proven to be resistant to repeated thermal and shock loading.

TL;DR: Tungsten is one of the candidate armor materials for the plasma facing components of the International Thermonuclear Experimental Reactor (ITER), and for the present reference design, tungsten has been selected as armor for the divertor upper vertical target, dome, cassette liner, and for lower baffle because of its unique resistance to ion and charge exchange particle erosion in comparison with other materials as mentioned in this paper.

TL;DR: In this paper, the authors used the Green-Kubo expression in linear response theory to obtain the thermal conductivity of a perfect crystal β-SiC and showed that the thermal capacity and thermal expansion coefficient are affected very little by point defects.

TL;DR: In this paper, the authors summarized international research and development programs on reduced-activation ferritic/martensitic steels, the primary candidate-alloys for a DEMO fusion reactor and beyond, along with some information on conventional steels.

TL;DR: In this article, the authors focus on low-activation materials for nuclear fusion power systems, with a focus on silicon carbide composites, vanadium alloys, and advanced martensitic steels.

TL;DR: In this paper, the current status of research and development on unirradiated and irradiated V-Cr-Ti alloys intended for fusion reactor structural applications is reviewed, with particular emphasis on the flow and fracture behavior of neutron-IRradiated vanadium alloys.

TL;DR: In this paper, the displacement threshold energies for C and Si primary knock-on atoms (PKA) in β-SiC were calculated using molecular dynamic simulations using a modified form of the Tersoff potential in combination with a realistic repulsive potential obtained from density-functional theory calculations.

TL;DR: In this article, the current status of SiC/SiC R&D is reported and it is demonstrated that future activities require a strong collaboration with the industry as well as common efforts involving the different laboratories.

TL;DR: In this article, an oxide dispersion strengthened (ODS) ferritic steel with high temperature strength has been developed in line with low activation criteria for application in fusion power systems and the composition Fe−13.5Cr−2W−0.25Y2O3 was chosen to provide a minimum chromium content to insure fully delta-ferrite stability.

TL;DR: In this article, the relative importance of the vacancy and interstitial contributions to radiation-induced segregation (RIS) in Fe-Cr-Ni alloys is studied to better understand the mechanisms causing changes in grain boundary composition and to improve the capability to predict RIS in austenitic Fe-cr-ni alloys.

TL;DR: In this paper, Li 2SiO3, Li 4SiO4 and Li2Si2O5 were synthesized by three techniques: (1) solid state reaction, (2) the precipitation method and finally, (3) the sol-gel method.

TL;DR: In this paper, the authors present two approaches to evaluate the stresses in the metal, modelled as a viscoplastic material, and the oxide, considered as elastic transverse isotropic.

TL;DR: In this paper, mass spectrometry in the residual gas was used to measure the hydrocarbon formation rates as a function of pyrolytic graphite temperature (300-1000 K) and ion energy (10-200 eV/H or D) for mass-analysed H3+ and D2+ beams.

TL;DR: A review of hydrogen isotopes-materials interactions in various materials of interest for fusion reactors is presented in this article, where the relevant parameters cover mainly diffusivity, solubility, trap concentration and energy difference between trap and solution sites.

TL;DR: In this paper, room temperature tensile properties, void swelling and microstructural changes in Fe-Cr alloys (0, 2, 6, 12 and 18 at.% Cr) have been studied following irradiation at 400°C in the BR-10 fast reactor to doses in the range 5.5-7.1 dpa.

TL;DR: In this article, the authors developed oxide dispersion strengthened (ODS) ferritic/martensitic steels for the long-life core of a Fast Breeder Reactor (FBR).

TL;DR: In this article, the retention of deuterium in polycrystalline W foils has been measured as a function of ion fluence and implantation temperature, and the retention enhancement is attributed to an increase in the D diffusion coefficient, which allows a greater diffusion depth.

TL;DR: In this paper, the authors proposed that the dendritic carbides should be avoided using a cooling rate of more than 103 K/min after the austenitization, because this phase mostly impairs the mechanical properties of the steel.

TL;DR: In this article, polycarbosilane-derived SiC fibers, Nicalon, Hi-Nicalon and S, were exposed for 1 to 100 h at 1273-1773 K in air.

TL;DR: The tritium breeding blanket is one of the most important components of a fusion reactor because it directly involves both energy extraction and tritiam production, both of which are critical to fusion power as mentioned in this paper.

TL;DR: In this article, single-crystal (001) β-SiC (3C) films have been irradiated with 360 keV Ar 2+ ions at 175, 310 and 375 K and the damage accumulation after each incremental fluence has been measured in situ by Rutherford backscattering spectroscopy in channeling geometry (RBS/C) along the [011] direction using the dual beam facilities within the Ion Beam Materials Laboratory at Los Alamos National Laboratory.

TL;DR: In this article, the authors performed transmission electron microscopy (TEM) on a V-4Cr-4Ti alloy irradiated to damage levels of 0.1-0.5 displacements per atom (dpa) at 110-505°C.

TL;DR: In this paper, two SS-Zr compositions have been selected as baseline waste form alloys: (a) stainless steel-15 wt% zirconium (SS-15Zr) for stainless steelclad fuels and (b) Zr-8wt% stainless steel (Zr−8SS) for Zircaloy-clad fuels.

TL;DR: In this paper, a new compound thorium phosphate-diphosphate Th4(PO4)4P2O7 has been synthesized in the framework of nuclear waste management aiming at the research of a storage matrix.

TL;DR: In this paper, the damage produced in α-zirconium at 100 K by displacement cascades with energy, E p, up to 20 keV has been investigated by molecular dynamics using a many-body interatomic potential.

TL;DR: In this article, the authors investigated the interdiffusion characteristics of various elements in Ti-304SS system in the temperature range between 976 and 1123 K by employing metallographic and electron probe microanalysis techniques.

TL;DR: In this article, the embrittlement behavior of ferritic/martensitic steels, after irradiation in the Petten High Flux Reactor (HFR), was investigated by Charpy-V tests with subsize specimens.

TL;DR: In this paper, photoelectron peak positions, peak widths and satellite positions were measured to identify the chemical states of mixed oxides of uranium with alkali and alkaline earth metals (Na, Li, Rb, Tl, Sr, Ba).

TL;DR: In this paper, a calcia-alumina glass-ceramic was chosen as joining and coating material, because its thermal and thermo-mechanical properties can be tailored by changing the composition, it does not contain boron oxide (incompatible with fusion applications) and it has high characteristic temperatures (softening point at about 1400°C).