Showing papers in "Journal of Nuclear Materials in 2005"

TL;DR: In this article, the differences and similarities of different ODS steels are explained in terms of the microstructures of the steels, and observations are explained using the properties of the ODS micro-structures.

TL;DR: In this paper, the authors focus on those studies that have resulted in changed views of the importance of various mechanisms of corrosion in water-cooled PWRs and present a review of these studies.

TL;DR: In this article, the authors provided correlations between hardness and yield stress for both irradiated austenitic and ferritic steels by combining existing data in the open literature, and found that the correlation factor between change in yield stress and change in hardness was found to be 3.06.

TL;DR: In this paper, the mechanical and thermo-physical properties of refractory metal alloys and mechanically alloyed (MA)-oxide dispersion strengthened (ODS) steels are reviewed and their potential for use in space nuclear reactors is examined.

TL;DR: In this article, the effects of helium ion irradiation for tungsten and other metals have been extensively studied as functions of ion energy, temperature and fluence, for a wide range of burning plasma conditions, using not only ion accelerators, but also large-sized plasma confinement devices such as TRIAM-1M and LHD.

TL;DR: In this article, the electrochemical reduction of actinides (U, Pu, Np and Am) and lanthanides (La and Nd) chlorides was investigated by cyclic voltammetry and chronopotentiometry at different temperatures in LiCl-KCl eutectic.

TL;DR: In this article, the authors proposed a method to solve the problem of structural and energy efficiency in the field of Mechanical Engineering using artificial neural networks (ANNs) and a model-based approach.

TL;DR: In this article, a theoretical model is presented to quantify the relative phonon-scattering effectiveness of the three dominant defect types produced by neutron irradiation: point defects, dislocation loops and voids.

TL;DR: In this article, the depth at which deuterium is retained can be tentatively divided into three zones: (i) the near-surface layer (up to a depth of ∼02μm), (ii) the sub-surface layers (from ∼05 to ∼2μm) and (iii) the bulk (>5 ǫ) low-energy D ion irradiation modifies the polycrystalline structure to depths of up to about 5 m.

TL;DR: In this article, the stability of point defects in UO2 was studied using an ab initio plane wave pseudopotential method in the generalized gradient approximation of the density functional theory.

TL;DR: In this article, the deuterium ion irradiation on tungsten has been carried out with incident energies of 100 eV and flux of 1.5 eV at a temperature in range between 333-K and 1130-K up to a dose of 1Õ×1026-D+m−m−2.

TL;DR: In this article, the thermochemical and thermophysical properties of alkaline-earth perovskites known as oxide inclusions were studied and the relationship between some physical properties was studied.

TL;DR: In this article, the solid-liquid transition in stoichiometric and hyperstoichiometric UO 2 was investigated by means of advanced techniques and the melting line was determined at pressures between 10 and 250 MPa, in fair agreement to previous measurements reported in the literature.

TL;DR: In this article, a forced circulation lead-bismuth eutectic non-isothermal loop at the Institute of Physics and Power Engineering (IPPE), Russia was used for corrosion testing of several US martensitic and austenitic steels.

TL;DR: In this article, the influence of composition variations on long-term glass behavior was investigated for three nuclear glass composition domains: the French SON 68 (R7T7-type) glass, the Na-Mg borosilicate AVM glass and the aluminosilicate VRZ glass defined as part of the investigation of new containment matrices based on zirconolite (CaZrTi2O7).

TL;DR: A recent campaign of reversed field operation at JET designed to match a variety of discharges to their more frequently executed forward field counterparts has been executed in an attempt to contribute to this understanding as mentioned in this paper.

TL;DR: In this article, the authors describe the response of plasma facing components manufactured with tungsten and CFC to energy loads characteristic of Type I ELMs and disruptions in ITER, in experiments conducted under an EU/RF collaboration in two plasma guns (QSPA and MK-200UG) at the TRINITI institute.

TL;DR: In this paper, the impact test results on the use of dispersion strengthened tungsten for divertor structures are discussed in detail, and the impact of these results on use of tengsten as structural material for fusion-specific neutron irradiation is discussed.

TL;DR: In this paper, a number of electrochemical experiments were employed to investigate the effects of hydrogen on the corrosion of UO 2 under nuclear waste disposal conditions, and a combination of corrosion potential (E CORR ) measurements and cyclic voltammetry have indicated that dissolved hydrogen can polarize the UO2 surface to reducing potentials; i.e., to E CORR values more negative then those observed under anoxic (argon-purged) conditions.

TL;DR: In this article, the dependence of the chemical erosion yield of carbon on the ion flux, Φ, was established to Φ − 0.54 at high ion fluxes.

TL;DR: In this paper, the authors investigated the mechanism of erosion and corrosion of steels in lead-bismuth eutectic (45Pb-55Bi) flow and found that large-scale erosion could be caused by the detachment of lumps of corroded materials that had defects formed by dissolution of alloying elements.

TL;DR: In this paper, the low temperature matrix swelling of UO 2 fuels was analyzed as a function of burn-up, taking into account changes in the fuel density, porosity and retained Xe concentration as measured by EPMA.

TL;DR: In this article, the authors studied hydrogen blistering and subsequent cracking behavior of pure W, K-doped W, and La2O3-Doped W. They found that blisters had complicated plateau-like shapes with many cracks.

TL;DR: In this paper, polycrystalline tungsten samples have been irradiated at near room temperature by high flux deuterium plasma beams with incident ion energies ranging 7-98 eV/D.

TL;DR: In this article, a study of helium retention and surface blistering with regard to helium dose, temperature, pulsed implantation, and tungsten microstructure was conducted to better understand what may occur at the first wall of an inertial fusion energy reactor.

TL;DR: The immobilization potential of AAFA matrices for cesium has been investigated in this article, showing no significant adverse effects on mechanical strength or microstructure, nor were significant quantities of Cs leached following application of the Toxic Characteristic Leaching Procedure (TCLP).

TL;DR: A comparative analysis of the spatial and temporal characteristics of transient energy loads (ELMs and disruptions) on plasma facing components (PFCs) in present tokamak devices and their extrapolation to next-step devices is presented in this paper.

TL;DR: In this article, Young's modulus and yield strength of solid hydrides were studied at room temperature and 300°C, and the results showed that these mechanical properties remain about the same as the original zirconium alloy for hydrogen compositions up to about ZrH 1.5.

TL;DR: In this article, the effects of radiation-induced damage on the density of Titanate ceramics were investigated and the short-lived isotope 238Pu, was incorporated into the ceramic formulation.

TL;DR: In this article, high temperature helium and deuterium implantation on tungsten powder metallurgy samples was studied using the University of Wisconsin inertial electrostatic confinement device.