Showing papers in "Journal of Nuclear Materials in 2016"

TL;DR: In this paper, a feasibility study was performed to fabricate ITER In-Vessel components by Selective Laser Melting (SLM) supported by Fusion for Energy (F4E), almost fully dense 316L stainless steel (SS316L) components were prepared from gas-atomized powder and with optimized SLM processing parameters.

TL;DR: In this paper, the authors provide a comprehensive summary of the current issues surrounding processing and containment of 129I, the isotope of greatest concern due to its long half-life of 1.6 × 107y and potential incorporation into the human body.

TL;DR: In this paper, a dispersed barrier hardening model informed by the available microstructure data has been used to predict the hardness of pure tungsten samples irradiated in HFIR at 90-850°C to 0.03-2.2°C.

TL;DR: In this article, multilayer coatings were applied to ZIRLO® coupon substrates by cathodic arc physical vapor deposition (CA-PVD) to develop accident-tolerant fuel (ATF) that can delay the deleterious consequences of loss-of-coolant-accidents (LOCA).

TL;DR: In this article, the microstructural development of tungsten (W) and Tungsten rhenium (Re) alloys were obtained after neutron irradiation at 400-800°C in the Japan Materials Testing Reactor (JMTR), the experimental fast test reactor Joyo, and the High Flux Isotope Reactor(HFIR) for irradiation damage levels in the range of 0.09-1.54 displacement per atom (dpa).

TL;DR: In this article, the corrosion behavior of commercial and model FeCrAl alloys and type 310 stainless steel was examined by autoclave tests and compared to Zircaloy-4, the reference cladding materials in light water reactors.

TL;DR: In this paper, a Mo layer was introduced between the FeCrAl coating and the Zr matrix to prevent inter-diffusion at high temperatures to improve the oxidation resistance of Zr fuel claddings for light water nuclear reactors.

TL;DR: In this article, computational alloy thermodynamics coupled with strength modeling have been employed to explore a new generation reduced activation ferritic-martensitic (RAFM) steels, which were designed to significantly increase the amount of MX nanoprecipitates, which are manufacturable through standard and scalable industrial steelmaking methods.

TL;DR: In this paper, the effect of sodium sulfate content and curing duration on the binder structure of activated slag cements was evaluated, and the most significant changes upon curing at advanced ages observed were growth of the AFt phase and an increase in silicate chain length in the C-A-S-H, resulting in higher strength.

TL;DR: In this article, high-purity (110) single-crystal tungsten was examined by positron annihilation spectroscopy and transmission electron microscopy following low-temperature (∼90°C) and low-dose (0.006 and 0.03 dpa) mixed-spectrum neutron irradiation and subsequent isochronal annealing at 400, 500, 650, 800, 1000, 1150, and 1300°C.

TL;DR: In this article, the microstructures of AlxCoCrFeNi (x = 0.1, 0.75 and 1.5 in molar ratio) high entropy alloys (HEAs) irradiated at room temperature with 3 MeV Au ions at the highest fluence of 105, 91, and 81 displacement per atom, respectively, were studied.

TL;DR: In this paper, the effect of fabrication process on microstructure, ductile-to-brittle transition temperature (DBTT), tensile and fracture behaviour of powder-metallurgy pure tungsten materials has been investigated.

TL;DR: In this paper, the void swelling and microstructure evolution of ferritic-martensitic alloys HT9, T91 and T92 were characterized following irradiation with Fe ++ ions at 460°C to damage levels of 75-650 displacements per atom with 10 atom parts per million pre-implanted helium.

TL;DR: In this article, the development status of current reduced-activation ferritic-martensitic (RAFM) steels is updated, together with ongoing efforts to develop next-generation RAFM steels for superior high-temperature performance.

TL;DR: In this paper, an autoclave testing of FeCrAl-coated Zircaloy 2 (Zy2) coupons under pressure-temperature-dissolved oxygen coolant conditions representative of a boiling water reactor (BWR) environment has been performed.

TL;DR: In this paper, U3Si2 was synthesized via the use of arc-melting and mixed with UN powders, which together were sintered using the SPS method.

TL;DR: In this paper, a combination of ion irradiation and nanoindentation was used to establish a screening test procedure for the resistance of ferritic/martensitic (f/m) steels to neutron damage in terms of hardening.

TL;DR: In this paper, the authors report on the characterization of defects formed in polycrystalline Ti 3 SiC 2 and Ti 2 AlC samples exposed to neutron irradiation up to 0.1 displacements per atom (dpa) at 350,±-40°C or 695,±−25°C, respectively.

TL;DR: In this paper, the properties of U 3 Si 2, such as stable crystalline structures, density of states, charge distributions, formation energy of defects, as well as the mechanical properties are explored.

TL;DR: In this paper, the role of spin-orbit coupling and on-site Coulomb correction (GGA+U) methods to investigate the U-Si system was investigated, and the results showed that the GGA+ U method removed the significant imaginary frequencies observed for U 3 Si 2 when the correction was not considered.

TL;DR: In this article, a systematic and statistically based analysis of the repeatability and device dependence of small punch test results was performed on an unirradiated ferritic-martensitic steel T91.

TL;DR: In this article, the authors used density functional theory calculations and thermochemical analysis to assess the stability of U3Si2 with respect to non-stoichiometry reactions in both the hypo- and hyper-stochastic regimes.

TL;DR: In this paper, the microstructure and irradiation hardening of tungsten were compared with previous data obtained from the irradiation campaigns in the mixed spectrum Japan Material Testing Reactor (JMTR) and the sodium-cooled fast reactor Joyo.

TL;DR: In this paper, the nanoindentation plastic zone size is calculated using two approaches: (1) an analytical model based on the expanding spherical cavity analogy, and (2) finite element modeling (FEM).

TL;DR: In this paper, in situ observations of damage development have been obtained of tensile and C-ring mechanical test specimens of a braided nuclear grade SiC-SiC ceramic composite tube, using a combination of ex situ and in situ computed X-ray tomography observation and digital volume correlation analysis.

TL;DR: In this paper, the burst behavior of austenitic and ferritic Fe-based alloy tubes has been examined under a simulated large break loss of coolant accident, where type 304 stainless steel (304SS) and oxidation resistant FeCrAl tubes were studied alongside Zircaloy-2 and ZircAloy-4 that are considered reference fuel cladding materials.

TL;DR: In this article, the thermal shock resistance of fine grained W-Y 2 O 3 materials fabricated by two different manufacturing technologies (i.e. spark plasma sintering and high temperature Sintering in combination with hot rolling deformation) was examined under transient high heat loads below and slightly above the melting threshold of pure tungsten.

TL;DR: In this article, the reliability of atomistic simulations of primary radiation damage hinges on the quality of the interatomic potential, and the authors compare the predictions of five interatomic projections for tungsten in cascade simulations with primary knock-on energies ranging from threshold energies for defect production, up to 200 kV.

TL;DR: In this article, the authors study the mechanical response and texture evolution of alpha-uranium during simple compression and rolling at 573 K. In order to determine the underlying mechanisms governing plasticity and texture formation, they perform detailed characterizations using electron backscattered diffraction and constitutive modeling using a dislocation-density based hardening law within a visco-plastic self-consistent homogenization.

TL;DR: In this article, the dissolution rate of the International Reference Glass (ISG) powders with different particle sizes and polished monoliths, and soda-lime glass beads were examined.