With the full data sample of 772 × 10 6 BB pairs recorded by the Belle detector at the KEKB electronpositron collider, the decayB → D Ã τ −ν τ is studied with the hadronic τ decays τ − → π − ν τ and τ − → ρ − ν τ . The τ polarization P τ ðD Ã Þ in two-body hadronic τ decays is measured, as well as the ratio of the branching fractions
The intense influx of hydrogen plasma onto the tungsten wall of a nuclear fusion reactor causes severe microstructural damage in the near-surface layer. The evolution of hydrogen-induced damage is often promoted by local plastic flow. Since hydrogen solutes are known to lower the hardness of many metals, the question arises as to the extent to which the tungsten walls are softened by the implantation of hydrogen. In this study, we investigated the change in slip resistance of tungsten single crystals following deuterium implantation. To determine the inherent yield stress of tungsten, we performed nanoindentation on high-purity single crystals. The statistical distribution of pop-in stresses (yield stress upon a single slip) revealed a significant reduction in pop-in load upon hydrogen implantation. In addition, the average stress at pop-in was found to be a function of crystallographic orientation of the samples, with much larger pop-in loads observed on (100) and (110) surface planes than on (111) surfaces.
We present the measurement of the absolute branching fractions of B þ → X cc K þ and B þ →D ðÃÞ0 π þ decays, using a data sample of 772 × 10 6 BB pairs collected at the ϒð4SÞ resonance with the Belle detector at the KEKB asymmetric-energy e þ e − collider. Here, X cc denotes η c , J=ψ, χ c0 , χ c1 , η c ð2SÞ, ψð2SÞ, ψð3770Þ, Xð3872Þ, and Xð3915Þ. We do not observe significant signals for Xð3872Þ or Xð3915Þ and set the 90% confidence level upper limits at BðB þ → Xð3872ÞK þ Þ < 2.6 × 10 −4 and BðB þ → Xð3915ÞK þ Þ < 2.8 × 10 −4 . These represent the most stringent upper limit for BðB þ → Xð3872ÞK þ Þ to date and the first limit for BðB þ → Xð3915ÞK þ Þ. The measured branching fractions for η c and η c ð2SÞ are the most precise towhere the first and second uncertainties are statistical and systematic, respectively.
Abstract:Deuterium retention in tungsten films deposited on polycrystalline bulk tungsten substrates was investigated and compared with deuterium retention in W films deposited on silicon and in polycrystalline bulk W alone. The structure of the deposited films was investigated by X-ray diffraction and scanning electron microscopy combined with focused ion beam cutting. D retention after implantation was measured by nuclear reaction analysis and temperature programmed desorption (TPD). The W films deposited on bulk W show a typical columnar epitaxial growth. After D implantation, high densities of blisters with diameters of about hundred µm were formed. Interestingly, the blisters are located within the W substrate well below the interface of deposited film and substrate. TPD spectroscopy reveals two D 2 release peaks at 510 and 700 K, indicating at least two different trap energies. Keywords IntroductionBecause retention of large quantities of tritium in the first-wall materials increases the fuel costs of a reactor and presents a safety concern, understanding of the fuel-retention properties of first-wall materials is important for ITER and next step fusion reactors such as DEMO [1][2][3]. Due to its favourable physical properties, such as low erosion yield and high melting temperature, tungsten is under consideration for use as plasma-facing material in the ITER divertor. Actually, a full tungsten inner wall and a full tungsten divertor have already been successfully developed and tested in ASDEX Upgrade and JET, respectively [4][5][6][7]. However, up to now mostly tungsten coatings were used as first-wall material for the so-called full-metal fusion devices, predominantly due to design limitations and cost concerns. Consequently, the influence of coating structure on the D retention should be taken into account.Some results for D retention in W films used in ASDEX Upgrade were published by Ogorodnikova et al. [8]. We used W films deposited by magnetron sputtering as a model system to investigate the influence of film structure on the deuterium retention. Different film structures were achieved by using different deposition parameters or annealing treatments. Deuterium loading was performed in well-quantified deuterium plasma. In this work, D retention in W films deposited on polycrystalline bulk W was studied and compared with deuterium retention in W films deposited on silicon and in polycrystalline bulk W alone. D retention and release and blistering after D implantation were investigated and are discussed in this article.
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