Showing papers in "Journal of Nuclear Materials in 2017"

TL;DR: A feasibility study was performed to fabricate ITER In-Vessel components by one of the metal additive manufacturing methods, Electron Beam Melting® (EBM®). Solid specimens of SS316L with 99.8% rela...

TL;DR: In this article, the performance of a single-phase, face-centered cubic high entropy alloy (HEA) Al0.1CoCrFeNi in as-cast condition was compared with the corrosion behavior of the SS304.

TL;DR: In this paper, the authors focused on the mechanical properties of model FeCrAl alloys and of a commercial Fe-CrAl alloy with up to 13.8 displacements per atom (dpa) at irradiation temperatures between 320 and 382°C.

TL;DR: In this article, the authors summarized the existing studies on nanoparticle irradiation evolution and discussed four possible contributing mechanisms for nanoparticle evolution: ballistic dissolution, Ostwald ripening, irradiationenhanced diffusion, and homogeneous nucleation.

TL;DR: In this paper, an analysis of the response of FeCrAl under normal operating and loss of coolant conditions has been performed using fuel performance modeling using BISON fuel performance code.

TL;DR: In this article, microstructures of single-crystal bulk tungsten (W) and polycrystalline W foil with a strong grain texture were investigated using transmission electron microscopy following neutron irradiation at ∼90-800°C to 0.03-4.6 displacements per atom (dpa) in the High Flux Isotope Reactor with a mixed energy spectrum.

TL;DR: In this paper, the most suitable Coulombic (U) and exchange (J) parameters for different functionals were parametrized within the DFT+U formulism to reproduce the experimental band-gap and lattice parameters for actinide oxides.

TL;DR: In this paper, the stacking fault energy (SFE) plays an important role in deformation behavior and radiation damage of FCC metals and alloys such as austenitic stainless steels.

TL;DR: In this article, the dissolution corrosion behavior of 316L stainless steels was investigated and it was found that the thickness of the dissolution-affected zone was non-uniform, and sites of locallyenhanced dissolution were occasionally observed.

TL;DR: In this paper, the authors investigate the damage production and dislocation mobility by simulating irradiation of elemental Ni and the alloys NiCo, NiCoCr and NiCoFe to assess the effect of elemental composition.

TL;DR: In this paper, the performance of nanocrystalline iron films is investigated in-situ in a transmission electron microscope (TEM) using He irradiation at 700 K, and the role of grain orientation and grain boundary character on bubble density trends is explored.

TL;DR: In this article, a mechanistic model was developed for modeling the depth-dependent hardness in ion irradiated metallic materials, which is capable of capturing the indentation size effect, ion irradiation induced damage gradient effect, and effect of unirradiated region acting as a soft substrate.

TL;DR: In this paper, the authors investigated the corrosion behavior of two heats of T91 ferritic/martensitic steel, with slightly different Cr content, in flowing (2m/s) Pb-Bi with 10 −7 mass%O at 450 and 550°C.

TL;DR: In this paper, the formation of defects in response to neutron irradiation of polycrystalline Ti3SiC2 and Ti3AlC2 samples exposed to total fluences of ≈6.7 × 1022 n/m2 at irradiation temperatures of 121 (12), 735(6) and 1085(68)°C.

TL;DR: In this paper, the authors focused on the relationship between microstructure and yield stress for an ODS Fe-9%Cr-based transformable alloy and a ODS ferritic alloy and found that particle strengthening, dislocation forest strengthening, and Hall-Petch strengthening are the major contributions.

TL;DR: In this paper, the effects of edge-localized mode like transient heat events on the as-rolled and recrystallized WZrC were investigated carefully by employing heat treatments with isochronal experiments, the evolution of tungsten grain size/orientation, second phase particle distribution, thermal conductivity and mechanical properties were systematically studied.

TL;DR: In this article, the air oxidation behavior of U3Si2, USi, and USi5 was studied from room temperature to 1000 C. The onsets of breakaway oxidation for each compound were identified during synthetic air ramps to 1000C using thermogravimetric analysis.

TL;DR: In this article, the authors measured the thermal conductivity of tungsten (W) surface layers damaged by He plasma in PISCES at UCSD and found that the damaged layers were reduced by at least ∼80% compared to that of undamaged W.

TL;DR: In this paper, a thorough review of the graphite-molecular oxygen reaction in terms of kinetics, mass and energy transport, and structural evolution is provided, showing that all three factors play a significant role in the observed rate of graphite oxidation.

TL;DR: In this paper, electron microscopy observations of irradiated U-10Zr fuel have been performed by using a grain boundary facilitated pathway to reveal lanthanide degradation of the cladding.

TL;DR: In this article, an object kinetic Monte Carlo (OKMC) model was proposed for describing the microstructural evolution in pure tungsten under neutron irradiation, focusing on low doses (under 1 dpa).

TL;DR: In this paper, a combination of ion irradiation and modeling was utilized to understand the microstructure evolution of ferritic-martensitic alloy HT9 at high dpa.

TL;DR: In this article, isothermal isothermal oxidation tests with Zircaloy-4 in steam-nitrogen mixtures have been performed at 600, 800, 1000, and 1200°C using thermogravimetry.

TL;DR: In this paper, the influence of dose rate and cascade morphology on nanocluster evolution in a model Fe-9%Cr oxide dispersion strengthened steel and the commercial ferritic/martensitic (F/M) alloys HCM12A and HT9 was evaluated.

TL;DR: In this paper, both nanoindentation and in situ SEM microcompression testing are carried out on 10 dpa proton beam irradiated 304 stainless steel to assess radiation hardening and radiation-induced deformation mechanisms in the material.

TL;DR: In this paper, four model FeCrAl alloys with chromium contents ranging from 10.01 to 17.51% and aluminum contents of 4.78 to 2.93% were irradiated to doses of 0.3-0.8 displacements per atom (dpa) at temperatures of 335-355°C.

TL;DR: In this article, 304 stainless steel specimens irradiated with 2-MeV protons to 10 dpa (full-cascade setting in the Stopping and Range of Ions in Matter, SRIM, software) at 360°C were evaluated using micro-tensile testing.

TL;DR: In this article, the effect of interlayer interlayer on the bonding quality of Tungsten and steel joints was studied. But the results showed no intermetallics occurred between W/Ti interfaces, meanwhile multiply phases were found between Ti/Steel interfaces.

TL;DR: In this paper, the defect dynamics in single-phase concentrated solid solution alloys (SP-CSAs) have been characterized using cross sectional transmission electron microscopy that distributions of voids and dislocation loops were presented as a function of depth.

TL;DR: In this paper, a nanostructured ferritic alloy (NFA), 14YWT, was produced in the form of thin walled tubing and the stability of the nano-oxides (NOs) was determined under 3.5 MeV Fe +2 irradiations up to a dose of ∼585 dpa at 450°C.