Showing papers in "Journal of Nuclear Materials in 1999"

TL;DR: In this paper, the evolution of radiation-induced damage in fully-stabilized, cubic zirconia (FSZ) (Y, Ca and Er dopants acting as stabilizers) was investigated using Rutherford backscattering spectrometry and ion channeling (RBS/C), along with X-ray diffraction and transmission electron microscopy (TEM).

TL;DR: In this article, the authors review the current understanding of radiation-induced material changes that occur in light-water-reactor (LWR) core components and link them to intergranular failure processes.

TL;DR: In the last two years, the basic erosion mechanisms of carbon due to thermal and energetic hydrogen atoms have been resolved and the range of erosion yield data has been extended into new regimes of ion flux and energy.

TL;DR: In this article, the authors present the results of current predictions both in terms of implantation and codeposition rates, and critically discuss their uncertainties and sensitivity to important design and operation parameters such as the plasma edge conditions, the surface temperature, the presence of mixed-materials, etc.

TL;DR: The Tritium Plasma Experiment Experiment (TPE) has been used to examine the retention of tritium in tungsten exposed to very high fluxes of 100 eV tritons as mentioned in this paper.

TL;DR: In this article, it is shown that reflooding of an overheated core can result in a renewed temperature rise with localized melt formation, additional release of fission products, and in an increased hydrogen production; this increases the threat to the integrity of the reactor pressure vessel and to the containment as well as potentially misleading the operators regarding their recovery actions.

TL;DR: A thermodynamic database, Zircobase, was developed for zirconium alloys for use in the nuclear industry as discussed by the authors, and the utility of this database is demonstrated in examples of thermodynamic calculations of the α/β phase transformation temperatures performed on industrial Zr-Nb and Zy4 type alloys.

TL;DR: In this paper, the authors present an overview of studies that are today integrated into national or international projects initiated since the first Inert MAtrix Workshops held at the Paul Scherrer Institute and elsewhere since September 1995, as well as from other specific actions.

TL;DR: In this paper, the effect of ion-induced damage due to prior ion implantation on deuterium retention in tungsten has been investigated, and it was shown that 1.5 keV D 3 + ions (500 eV/D + ) to 10 23 D/m 2 at 500 K showed a 3-4 increase in retention for specimens previously exposed to a fluence of 10 24 D/M 2 and a factor of 6-7 increase for specimens recently exposed to 3-times-10 24 Dm 2 over specimens exposed only to an incident flu

TL;DR: In this article, the physical properties and chemical behaviour of homogeneous and heterogeneous diluents in PuO2 and PuN fissile materials are compiled and critically assessed.

TL;DR: In this article, the authors show that the threshold for ablation of the graphite target will be reached if the ELM transient exceeds Q/t 1/2/∼ −45 MJ m−2 s−1/2 where Q is the deposition energy density and t is the time of ELM deposition.

TL;DR: Tungsten divertor plates have been used in ASDEX Upgrade for a full experimental campaign of approximately 800 discharges as mentioned in this paper, and the results obtained so far are presented and the implications with respect to the construction of future fusion devices are discussed.

TL;DR: In this paper, an extended version of the 3D Monte Carlo edge plasma transport code EMC3 including more complex physics is presented, and the balance equations for mass, momentum and energies are formulated in a general conservation form suited for direct application of the Monte Carlo solving algorithm.

TL;DR: In this article, a comparison of the known structures of uranyl phases indicate that (SeO3) may substitute for (SiO3OH) in structures of α-uranophane and boltwoodite that are expected to be the dominant alteration products of UO2 in Si-rich groundwater.

TL;DR: The formation mechanisms of dust particles in fusion devices and the possible interactions of dust with fusion plasmas are discussed in this paper, where the growth of small particles in the plasma edge of fusion discharges is suggested in analogy to the well-known growth in reactive processes.

TL;DR: In this article, the impact toughness of the developed alloys is very sensitive to the magnitude of relative density and is greatly improved by increasing its value, and an alloy with 0.2 wt% TiC content was developed by mechanical alloying and hot isostatic pressing.

TL;DR: In this paper, the authors discuss the criteria for selecting inert matrices for Am-transmutation, their fabrication, and typical results on property measurements, often in comparison with UO2, with emphasis on radiation damage formation and damage effects.

TL;DR: In this article, the ITER divertor power deposition database is described and analyzed, and the authors derive multi-machine scaling laws for the peak divertor heat flux and width, particularly of their machine size dependence.

TL;DR: In this paper, a feasibility study was conducted on the use of chemically bonded phosphate ceramics for stabilization of combustion residue of high transuranic (TRU) wastes, and the results showed that the waste forms provided high leaching resistance for both hazardous metals and Pu.

TL;DR: In this article, the authors reviewed the recent activities and results in development and evaluation of new high-Z materials focusing on tungsten and its alloys, and they showed that VPS-W coating on graphite and CFC showed superior high heat load properties.

TL;DR: In this article, the authors review experimental data regarding hydrogenic atom inventories in experiments pertinent to tokamak applications and show that with some very plausible assumptions, the experimental data appear to exhibit rather predictable trends.

TL;DR: In this article, the properties of bulk stoichiometric silicon carbide which has been amorphized under neutron irradiation were investigated and the critical temperature for amorphization at this neutron dose and flux was estimated to be greater than ∼125°C.

TL;DR: In this article, a hybrid fuel design for americium transmutation is proposed, consisting of spherical inclusions of an americium host phase in a dense inert matrix, and a solid solution (Zr,Am)O 2, possibly stabilised by yttrium as the host phase.

TL;DR: In this paper, the role of fluctuations of the electron temperature and the instability mechanism acting in the plasma edge is summarised, and a brief account on the changes of the fluctuations and the resulting transport when discharge parameters are varied.

TL;DR: In this paper, twenty-four iron phosphate compositions (15 wt% wasteloading) were evaluated to determine their suitability for vitrifying Al-clad, highly enriched uranium, spent nuclear fuel (SNF).

TL;DR: In this article, the authors used the SPECOMP code to obtain effective, energy-dependent cross sections for two measures of primary damage production: (1) the number of surviving point defects expressed as a fraction of those predicted by the standard secondary displacement model by Norgett, Robinson, and Torrens (NRT), and (2) the fraction of the surviving interstitials contained in clusters that formed during the cascade event.

TL;DR: The Experimental Breeder Reactor-II (EBR-II) was a 62.5 MWt-20 MWe sodium cooled fast reactor that was operated successfully for 30 years.

TL;DR: In this article, the relative influence of classical particle drifts across the magnetic field is studied for self-consistent simulations by including them, together with anomalous diffusion transport, in a 2D fluid model of edge-plasma transport for the DIII-D tokamak geometry.

TL;DR: In this paper, the authors reported progress on work to develop methods of fabricating silicon carbide with cerium, as a substitute for plutonium, to achieve high densities at low sintering temperatures.

TL;DR: A survey of the literature shows that baddeleyite is widespread in nature as a trace mineral, but has a rather limited composition of 87-99 wt% ZrO2 with most of the remainder comprised of FeO, TiO2 and HfO2.