Showing papers in "Journal of Nuclear Materials in 2006"

TL;DR: The microstructural stability of Alloyed Alloyed, Oxide Dispersion Stiffened (MA/ODS) 14YWT ferritic alloys was investigated by atom probe tomography.

TL;DR: In this paper, a transmission electron microscopy investigation was performed on oxides formed on three zirconium alloys (Zircaloy-4, ZIRLO and Zr-2.5Nb) in pure water and lithiated water environments.

TL;DR: In this article, most of the available data from the literature are compared in order to discuss to what extent they are consistent and the existing differences do not correlate in any explicit way with the description that the interatomic potential gives of point-defects and their mobility.

TL;DR: Examination of specimens after tensile deformation revealed localized deformation in the form of cleared dislocation channels, presumably due to the multiaxial stress state produced during necking and fracture of the tensile specimen.

TL;DR: In this paper, Alloy 600 was tested in simulated pressurised water reactor (PWR) primary water, at 360 °C, under an hydrogen partial pressure of 30 kPa. These testing conditions correspond to the maximum sensitivity of alloy 600 to crack initiation.

TL;DR: In this article, the development of chemically vapor-deposited (CVD) high-purity beta-SiC during neutron and self-ion irradiation at elevated temperatures was studied.

TL;DR: In this paper, the relative impact of radiolysis products in radiation induced oxidative dissolution of UO2 has been studied experimentally and the experiments were performed by y-irradiating an aqueous solution con...

TL;DR: In this paper, a suitable glass matrix based on barium borosilicate has been developed for immobilization of high-level radioactive liquid waste (HLW) in a plant scale.

TL;DR: In this article, the microstructural and mechanical properties changes in irradiated ferritic-martensitic alloy T91 were evaluated with 2.0 MeV protons to doses of 3, 7, and 10 dpa at a dose rate of 2.5 × 10−5 dpa/s and at temperatures of 400,°C, 450,°c, and 500 °C.

TL;DR: In this article, three phosphate-based ceramics were studied for the immobilization of tri-and tetravalent actinides: britholite Ca 9 Nd 1 - x An x IV ( PO 4 ) 5 - x ( SiO 4 ) 1 + x F 2, monazite/brabantite Ln 1 - 2 x III Ca x An X IV PO 4 and thorium phosphate diphosphate β - Th 4 - x AN x IV 4 P 2 O 7 (β-TPD).

TL;DR: In this article, the authors used phenomenological-empirical fitting models to assess the dose (displacement-per-atom, dpa), irradiation temperature (Ti) and test temperature (Tt) dependence of yield stress changes (Δσy), as well as the corresponding dependence of sub-sized Charpy V-notch impact test transition temperature shifts (�Tc).

TL;DR: In this article, three dimensional X-ray tomographic images of intergranular stress corrosion crack nucleation and growth in sensitised austenitic stainless steel provide evidence for the development of crack bridging ligaments, caused by the resistance of non-sensitised special grain boundaries.

TL;DR: In this article, two silicate glass compositions leading to efficient nucleation and crystallization of either zirconolite (Ca 1− x Nd x ZrTi 2− x Al x O 7, x 2 Nd 8 Si 6 O 26 ) in their bulk were studied as potential waste forms.

TL;DR: Grain boundary engineering (GBE) was applied to INCOLOY alloy 800H by means of thermomechanical processing as mentioned in this paper, which improved the protective oxidation behavior by enhancing spallation resistance and reducing oxidation rate.

TL;DR: In this article, the cumulative effect of high alpha decay doses (>10 19 α /g) and the dose rate were investigated for four R7T7-type borosilicate glass samples doped with 0.04, 0.4, 1.2 and 3.25% 244 CmO 2.

TL;DR: In this paper, a pseudopotential approach in the generalized gradient approximation (GGA) can satisfactorily describe the cohesive properties of these actinide dioxides, and the formation energies of point defects (vacancies and interstitials) are calculated.

TL;DR: In this article, the authors studied the kinetic and crystalline evolutions of UO2 during its oxidation into U3O8 at 250 degrees C in air, using isothermal thermogravimetry and calorimetry, coupled with an in situ synchrotron X-ray diffraction on the D2AM-CRG beamline at ESRF.

TL;DR: In this article, the authors simulated displacement cascades up to 50 keV in Fe-10%Cr by molecular dynamics using an embedded-atom method (EAM) interatomic potential which satisfactorily reproduces the interact...

TL;DR: In this paper, the role of water diffusion on the long-term nuclear waste glass alteration was investigated with the borosilicate SON 68 glass in synthetic solutions enriched in Si, Na and B at 50 and 90 °C.

TL;DR: In this article, an electrorefining in the molten LiCl-KCl eutectic salt containing actinide (An) and rare-earth (RE) elements was conducted to recover An elements up to 10% into liquid cadmium (Cd) cathode, which is much higher than the solubility of the An elements in liquid Cd at the experimental temperature of 773 K.

TL;DR: In this paper, Magnesium potassium phosphate (MKP) ceramics have been developed to treat 99 Tc that has been partitioned and eluted from simulated high-level tank wastes by means of sorption processes.

TL;DR: In this article, a 12% Cr ferritic-martensitic steel, HT9, was examined after exposure to supercritical water (SCW) at 500°C with two different dissolved oxygen contents, 25wppb and 2wppm, for exposure periods of up to 505h.

TL;DR: In this paper, data obtained by ab initio calculation of point defects (vacancies and self-interstitial atoms, foreign interstitial defects (C, N, H and He) in different matrix elements (Fe and Zr) as well as of some substitutional elements (Cu, Ni, Mn, Si, Cr and P") in bcc Fe will be presented and discussed.

TL;DR: In this paper, the aging behavior of JIS SCS14A cast duplex stainless steels was investigated on the basis of the mechanical properties and microstructural changes during accelerated aging at 350°C and 400°C.

TL;DR: In this article, the authors studied the diffusion mechanism of He atoms in grain boundaries in α-Fe and found that He atoms diffuse rapidly in the Σ11 grain boundary, where the binding energy of a He atom to the boundary is high.

TL;DR: The diffusion-controlled ion exchange phase in the corrosion of nuclear waste borosilicate glasses has been examined using the Doremus' model accounting for interdiffusion and exchange of the cations in the glass with protons from the water.

TL;DR: In this paper, a model for simulating thermal hydraulic and chemical conditions within fuel crud deposits is described, which is coupled to the thermal hydraulics via the increase in the saturation temperature with the concentration of dissolved species.

TL;DR: Theories of fission-fragment-driven re-solution of gas atoms from intragranular bubbles in irradiated UO2 nuclear fuel are reviewed in this paper.

TL;DR: In this paper, an empirical potential fitted to both formation and relaxation energies of a single He defect and small He clusters obtained from the first principles calculations was constructed and used to study stability of He-vacancy clusters at zero temperature.

TL;DR: In this article, the effect of irradiation on the mechanical properties of ODS F/M steels was investigated by transmission electron microscopy and mechanical properties were assessed by tensile and Charpy tests.