Showing papers in "Journal of Nuclear Materials in 2009"

TL;DR: In this paper, different aspects of the PWI are assessed in their importance for the initial wall materials choice: CFC for the strike point tiles, W in the divertor and baffle and Be on the first wall.

TL;DR: In this paper, the authors give a brief overview of various materials that are essential to establish advanced systems feasibility and performance for in pile and out of pile applications, such as ferritic/martensitic steels (9-12% Cr), nickel based alloys (Haynes 230, Inconel 617, etc.), oxide dispersion strengthened ferritic and martensite steels, and ceramics (SiC, TiC, etc.).

TL;DR: In this paper, the status of light-water (LWR) fuel rods is reviewed with respect to important recent concerns, namely provision of outlet coolant temperatures high enough for use in H2 production, destruction of plutonium to eliminate proliferation concerns, and burning of the minor actinides to reduce the waste repository heat load and long-term radiation hazard.

TL;DR: In this article, a thorough knowledge of the chemistry of aluminum and susceptibility to corrosion in alkaline solutions is reviewed and a review of phase transitions with aging time and change of environment is also performed.

TL;DR: In this article, the authors examined cracks in an ITER-reference tungsten grade under single thermal shock loading and found that the major cracks were generated due to the brittleness of the material and microcracks were formed in a process which was initiated by plastic deformation at high temperature.

TL;DR: In this paper, the authors report on the evolution of microstructure and mechanical properties of Fe/W multilayers subjected to helium ion irradiations and show that the magnitude of hardness variation after radiation depends on the individual layer thickness.

TL;DR: In this article, the authors simulate the conditions expected at W strike-points in an ITER all-w metal divertor scenario in the linear-plasma-device PISCES-B.

TL;DR: In the framework of the Generation IV Sodium Fast Reactor Program, the Advanced Fuel Project has conducted an evaluation of the available fuel systems supporting future sodium cooled fast reactors as discussed by the authors, based on documented performance of metallic fast reactor fuels and the early results of tests currently being conducted in US and international transmutation fuel development programs.

TL;DR: In this article, the changes in mechanical properties of an advanced nanocluster strengthened ferritic alloy, designated 14YWT, and an oxide dispersion-strengthened ferritic Alloy ODS-EUROFER were investigated.

TL;DR: In this article, an object Kinetic Monte Carlo technique parameterized on ab initio calculations was used to model He desorption in W. The evolution of the number of defects in the KMC simulation was found to be in good agreement with the resistivity changes observed during an He implantation in a thin wire of tungsten.

TL;DR: A review of the irradiation performance of Ni-base alloys based upon data from fast breeder reactor programs conducted in the 1975-1985 timeframe with emphasis on the mechanisms involved in the loss of high temperature ductility and the breakdown in swelling resistance with increasing neutron dose is presented in this paper.

TL;DR: ASDEX Upgrade has successfully started the second experimental campaign with a full tungsten coverage of the plasma facing components and without using a boronisation for machine conditioning as discussed by the authors.

TL;DR: In this article, an overview and summary of recent in-situ heavy ion irradiation experiments on Fe and Fe-Cr alloys carried out on the Argonne IVEM Facility at irradiation temperatures up to 500°C.

TL;DR: In this article, both chemically extracted residue method and extraction replica method were applied to the commercial ODS ferritic alloy, MA957, and these samples were then observed using XRD (X-ray diffractometry) and FEG-STEM (field emission gun scanning transmission electron microscopy) with EDS (energy dispersive X-ray spectrometer).

TL;DR: The effective atomic number, Zeff, the effective electron density, Ne,eff, and the energy dependence, ED, have been calculated at photon energies from 1-keV to 1-GeV for CaO-SrO-B2O3, PbO-Bi2O-3-B 2O3 glasses with potential applications as gamma ray shielding materials.

TL;DR: In this article, the authors used density functional theory based ab initio calculations to investigate the tendency of He and H to form clusters and found that He atoms always bond more strongly to HexHy complexes in a vacancy than H atoms.

TL;DR: In this article, the phase separation in a thermally aged (773 K) Fe 20 at.%Cr alloy using a Tomographic Atom Probe has been investigated and it is shown that the chromium content in the α-phase evolves with ageing time synonymous of a non-classical nucleation mechanism.

TL;DR: In this paper, the effects of high-temperature neutron irradiation on microstructural evolution, thermal and electrical conductivities and mechanical properties including the fiber/matrix interfacial strength are specified under various irradiation conditions.

TL;DR: In this article, the authors present the recent CEA developments on ODS materials, and show the first results obtained on the Fe-18Cr1WTi new ferritic ODS alloy.

TL;DR: In this paper, a conceptual design of FDS-III is presented, including the design of plasma core, high temperature liquid blanket, divertor and related auxiliary systems, and preliminary performance analyzes have demonstrated the feasibility of the design.

TL;DR: In this paper, surface and sub-surface morphology and deuterium retention in polycrystalline tungsten, undamaged and pre-damaged with 5.5 MeV W2+ ions to damage levels of 0.04, 0.4, and 1.2

TL;DR: In this paper, tetravalent U and Pu are incorporated in a durable zirconolite phase, together with Gd or Hf added as neutron absorbers, and the final consolidation to produce a dense monolithic waste form was carried out using hot isostatic pressing (HIPing) of the calcined materials within a stainless steel can.

TL;DR: In this article, the stability range of intrinsic point defects in uranium dioxide is determined as a function of temperature, oxygen partial pressure, and non-stoichiometry, and the computational approach integrates high accuracy ab initio electronic-structure calculations and thermodynamic analysis supported by experimental data.

TL;DR: In this paper, an investigation of an erosion of the ITER-like divertor castellated targets of pure tungsten, lanthanum tengsten and CFC under plasma heat loads expected during the Type I ELMs and disruptions in ITER was carried out on a plasma gun QSPA-T at the SRC RF TRINITI under EU/RF collaboration.

TL;DR: In this article, small angle neutron scattering (SANS) was used to follow the precipitation of the nano-phases in ODS ferritic materials, showing that the nano phases formed in powders with some titanium are much more resistant to the coarsening than the phases formed without titanium.

TL;DR: In this paper, a first-principles method was used to investigate the structure, stability and diffusion of hydrogen (H) in tungsten (W) and found that single H atom prefers to occupy the tetrahedral interstitial site with the formation energy of ∼−2.45eV.

TL;DR: Significant progress has been achieved in the international research effort on reduced activation ferritic/martensitic steels for fusion structural applications as discussed by the authors, which is the leading structural material for test blankets in ITER and future fusion power systems.

TL;DR: In this paper, the ferritic/martensitic steel HT-9 was processed and heat treated to produce one specimen with a large grained ferritic microstructure and further heat-treated to form a fine tempered martensitic lath structure and exposed to an ion beam and tested after irradiation using nanoindentation to investigate the irradiation induced changes in mechanical properties.

TL;DR: The mechanism of the reaction between Zircaloy-4 and air at temperatures from 800 to 1500°C was studied in this article, where the main mechanism is the formation of zirconium nitride and its reoxidation.

TL;DR: In this paper, high number densities of 2-nm-diameter Ni-, Si- and Mn-enriched nanoclusters were found in the neutron irradiated base and weld metals.