Showing papers in "Journal of Nuclear Materials in 2011"

TL;DR: In this paper, the use of tungsten (W) as material for plasma-facing components (PFM) in fusion devices is reviewed with respect to its plasma and material compatibility under burning plasmas conditions.

TL;DR: The ITER PFC design has now reached a rather mature stage following the 2007 ITER Design Review as discussed by the authors, and the key elements of the design, reviews the physics drivers, essentially thermal load specifications, which have defined the concept and discusses a selection of material and design issues.

TL;DR: In this paper, a successful example of high-Cr oxide dispersion strengthened (ODS) steels development is introduced with showing key technologies to overcome the issues to meet material requirements for next generation nuclear systems as well as fusion blanket systems.

TL;DR: The recent progress in the understanding and of basic phenomenon related to the use of SiC and SiC composite in fusion applications will be presented in this article, including both fundamental radiation effects in SiC, and engineering issues such as joining and general materials properties.

TL;DR: In this paper, the roles of helium nanobubbles on the formation of tungsten nanostructures were investigated and it was shown that the growth of helium bubbles beneath the nanostructure layer could lead to the formation dusts, which might have fatal influence to the tokamak operation, when the surface temperature was significantly high, say higher than 1800 K.

TL;DR: In this paper, a thermodynamic model for the (U, Pu)O 2 oxide, the carbide fuels using the Calphad method to describe consistently both phase diagrams and thermodynamic data of the phases involved in the U-Pu-O-C system was derived.

TL;DR: The long-term objective of the EFDA fusion materials programme is to develop structural as well as armor materials in combination with the necessary production and fabrication technologies for future divertor concepts as mentioned in this paper.

TL;DR: In this article, the authors modeled fuel swelling of U-Mo alloy using the measured data from samples irradiated up to a fission density of ∼7 × 1024 fissions/m3 at temperatures below ∼250 °C.

TL;DR: The status and key issues of reduced activation ferritic/martensitic (RAFM) steels R&D are reviewed as the primary candidate structural material for fusion energy demonstration reactor blankets as mentioned in this paper.

TL;DR: In this article, high purity W and W-0.9La(2)O(3) (wt.%) nanopowders were produced by a wet chemical route.

TL;DR: Sputtering yields of He-induced W ‘fuzzy’ surfaces bombarded by Ar have been measured in the linear divertor plasma simulator PISCES-B and it is found that the sputtering yield of a fuzzy surface decreases with increasing fuzzy layer thickness, L, and saturates at ∼10% of that of a smooth surface, Y smooth, at L > 1 μm.

TL;DR: In this paper, microscopic damage and D retention in tungsten have been investigated for low-energy (∼60-120 eV), high flux ( ∼1022m−m−2 s−1), high fluence ( ∼5 × 5 × 1025 m−2 ) ion bombardment at moderate temperature ( ∼573-773k) in mixed species D+He plasmas in the linear divertor plasma simulators PISCES-A and B. A significant reduction in D retention and the formation of nanometer-sized He bubbles occur

TL;DR: In this article, the long term corrosion behavior of the two structural materials foreseen in ADS, 316L and T91, was investigated in the design relevant temperature field, i.e. from 300 to 550°C.

TL;DR: In this paper, high purity chemically vapor-deposited (CVD) silicon carbide (SiC) and near-stoichiometric SiC fiber, chemically vaporinfiltrated (CVI) SiC matrix composite were evaluated following neutron irradiation to ∼28-dpa at 300 and 650°C and to ∼41-dPA at 800-°C, respectively.

TL;DR: In this paper, an atomic-scale modeling and experiment of the RIS mechanism for Cr in austenitic and ferritic-martensitic (F-M) alloys is presented.

TL;DR: In this paper, the authors summarized the core and divertor radiative characteristics of potential seeding species, namely noble gases and nitrogen, and showed that nitrogen is a suitable replacement for carbon as a divertor radiator.

TL;DR: In this article, magnetron sputtered Cu/W multilayer samples with individual layer thicknesses from 2.5 to 50nm were irradiated by 50-keV He+ ions at ion fluences from 7.2 to 6.6 m−2 at room temperature.

TL;DR: In this article, the authors compared the microstructural and mechanical properties of the same ingots aged at 325 °C and to the ferrite of an elbow steel aged on-site, and found that the linear relationship found between micro-hardness measurements and the variation V (defined as the integral of the difference between the Cr frequency distribution of the aged sample and the corresponding binomial distribution characteristic of a random solution with the same concentration) is still valid after 200,000 h of ageing at 350 °C.

TL;DR: In this article, the authors highlight the recent activities of these vanadium alloy researches, discuss the critical issues and summarizes the remaining issues to be addressed, and some efforts are oriented to issues related to DEMO blanket manufacturing technology, such as W coating for first wall protection and the welding technologies to fabricate large vanadium component.

TL;DR: In this article, the results of isothermal and transient oxidation experiments of the advanced cladding alloys M5 and ZIRLO™ in comparison to Zircaloy-4 in air at temperatures from 973 to 1853 K were presented.

TL;DR: In this article, the authors examined the deformation and fracture behavior of modified 9Cr-1Mo steel for steam generator (SG) tube application at 823, 848 and 873 K.

TL;DR: In this paper, a combination of ab-initio calculations and statistical mechanical models has been used to study diffusion behavior in dilute ferritic Fe-Cr and Fe-Ni alloys, and a full set of Onsager matrix coefficients (Lij) and tracer diffusion coefficients (D*) were calculated both for vacancy and interstitial mediated diffusion.

TL;DR: Nano-crystalline W-1%Y(2)O(3) (wt.%) powder was produced by a modified solution chemical reaction of ammonium paratungstate (APT) and yttrium nitrate as discussed by the authors.

TL;DR: In this paper, pre-damaged samples were exposed to pure and He-seeded deuterium plasmas on both front (undamaged) and rear (damaged) sides in order to separate tritium retention in plasma-induced traps and in displacement damage created by fast tungsten ions.

TL;DR: In this article, seven austenitic alloys were irradiated to 1 and 5 dpa at 360°C using 2.2 and 3.2 MeV protons and were tested both in simulated BWR environment and in argon.

TL;DR: In this paper, the effects of irradiation temperature, damage level and Re content on hardening and electrical resistivity were discussed, and the property change mechanism was discussed considering the irradiated microstructure and solute elements.

TL;DR: In this paper, the porosity of the filler particles in the virgin graphite grades of the Next Generation Nuclear Plant (NGNPP) program was analyzed using optical microscopy.

TL;DR: In this paper, the influence of both microstructure and chemical composition on the fracture behavior of tungsten-tantalum, tengsten-vanadium composites and alloys of varying chemical compositions is investigated.

TL;DR: In this paper, a new IR camera for high resolution infra red studies for the outer divertor target plate in JET has been installed, and the broadening of the ELM induced power profiles are, in contrast to earlier results based on a lower resolution IR system at JET, found to be in the range of 1.4-4.3 when compared to the inter-ELM wetted area.

TL;DR: In this article, the effect of both electronic and nuclear interactions on the structure of polycrystalline Ti3SiC2 was analyzed by low-incidence X-ray diffraction and cross-sectional transmission electron microscopy.