Showing papers in "Journal of Nuclear Materials in 2002"

TL;DR: In this article, the authors reviewed the JNC activities on ODS steel development as "nano-composite materials" and concluded that the ODS-technology development achieved in the field of fast reactors should be effectively spun off to the fusion reactor first wall and blanket structural materials to allow for safe and economical reactor design.

TL;DR: An overview of the available data on hydrogen isotope retention and recycling for beryllium, tungsten, carbon, and selected liquid metals can be found in this paper, where recommendations are made as to the most appropriate values to use for parameters such as diffusivity, solubility, recombination rate coefficient, and trapping.

TL;DR: In this paper, the authors describe the rationale for the selection of PFMs in ITER (Be, W, carbon fibre reinforced carbon) is described with regard to the critical issues concerning PFMs, esp. erosion during transient heat loads and the T-inventory in connection with the redeposition of carbon.

TL;DR: In this paper, a review of the literature on ferritic/martensitic steels for fusion is presented, focusing on the international collaboration under the auspices of the International Energy Agency (IEA) to address potential problems with ferri tic/marten si tic steels and prove their feasibility for fusion.

TL;DR: In this paper, two ODS variants of the 9%CrWVTa-RAFM steel EUROFER 97 with Y2O3 contents of 03 and 05 wt% have been produced by means of optical and electron microscopy (SEM, TEM).

TL;DR: In this article, the authors present the results of the irradiation, characterization and irradiation assisted stress corrosion cracking (IASCC) behavior of proton- and neutron-irradiated samples of 304SS and 316SS from the same heats.

TL;DR: In this article, the performance of a series of high-density U-Mo alloy, aluminum matrix dispersion fuels, were evaluated in two irradiation test vehicles to irradiate low-enrichment fuels to approximately 40 and 70 U burnup in the advanced test reactor at fuel temperatures of approximately 65 °C.

TL;DR: The tensile and creep properties of two oxide dispersion-strengthened (ODS) steels with nominal compositions of Fe-12Cr-0.4Ti-O3 (12YWT) and Fe-14Cr-2.5W−0.25Y2O3 were investigated in this article.

TL;DR: In this article, a review of recent progress in research on vanadium alloys with emphasis on V-4Cr-4Ti as a reference composition is presented, and the effects of other trace impurities on some of the properties are also discussed.

TL;DR: In this article, the authors have made advances in understanding radiation damage in SiC at the fundamental level through MD simulations of displacement cascades and showed that SiC composites made with the advanced fibers of Nicalon Type S and the UBE Tyranno SA have excellent thermal conductivity and radiation stability.

TL;DR: The thermodynamic basis for controlling oxygen level in lead-bismuth to prevent steel corrosion and coolant contamination is examined in this article, where the operational conditions, including the thermodynamic activity of oxygen, cover gas oxygen partial pressure, mixtures of H2 and H2O (steam), and voltage signals of one type of oxygen sensors are calculated.

TL;DR: In this article, a thermodynamic assessment of the uranium-oxygen system is presented, and a consistent set of experimental data is selected among the numerous data in the literature on the phase diagram and oxygen chemical potential.

TL;DR: Corrosion tests were carried out on austenitic AISI 316L and 1.4970 steels and on MANET steel up to 2000 h of exposure to flowing Pb/Bi.

TL;DR: In this article, the reduced-activation martensitic steel F82H (8Cr 2W 0.04Ta 0.1C) was used for fusion reactor structural materials.

TL;DR: In this article, a cluster-dynamics model for point-defect clustering in ferritic alloys under irradiation at large fluence is presented. But the model is based on rate equations and it is applied to two alloys FeCu (0.13 wt%) and FeMn(1.5 wt%).

TL;DR: In this paper, the structural materials part of the ITER program along with the latest R&D results from the main programs are assessed and it is shown that stainless steels and ferritic/martensitic steels, retained for ITER and DEMO, will also remain the principal contenders for the future FPR, despite uncertainties over irradiation induced embrittlement at low temperatures and consequences of high He/dpa ratio.

TL;DR: The fusion-driven multi-functional hybrid reactor system (FDS) is proposed as a middle step toward the final application of fusion energy and its strategic goal and roadmap is addressed along with its potential advantages.

TL;DR: In this paper, post-irradiation annealing was used to identify the role of radiation-induced segregation (RIS) in irradiation-assisted stress corrosion cracking (IASCC) by preferentially removing dislocation loop damage from protonirradiated austenitic stainless steels while leaving the RIS of major and minor alloying elements largely unchanged.

TL;DR: In this article, the effects of pre-irradiation with helium ions of fusion relevant energy on trapping of injected deuterium in W was studied by thermal desorption spectrometry technique using high-resolution quadrupole mass spectrometer.

TL;DR: In this paper, the authors performed compatibility tests on the austenitic AISI 316L and the martensitic MANET II steels in stagnant PbBi with exposures up to 5000 h.

TL;DR: In this paper, a microstructural analysis and tensile tests were performed on two oxide dispersion strengthened ferritic/martensitic steels and it was shown that the ODS with 0.3 wt%) yttria presents, in terms of critical stress and uniform elongation, a better mechanical behaviour than the base material up to 500 degreesC and still maintains fair properties up to 700 degreesC.

TL;DR: In this paper, Boron carbide powder has been prepared by carbothermal process using boric acid and citric acid as raw materials and the product obtained has been characterized by X-ray diffraction (XRD), chemical analysis, particle size analysis and scanning electron microscopy.

TL;DR: In this article, a Raman spectral library of UO 2 corrosion phases was set up for the identification of unknown products found on altered nuclear fuel samples, such as U peroxide (UO 4 ).

TL;DR: The authors summarizes the design and performances of recent breeding blanket concepts and identifies the key material issues associated with them, by balancing out the potential performance of the concepts with the risk associated with the required material development.

TL;DR: In this paper, single crystals of the ABO3 phases CaTiO3, SrTiO-3, BaTiO 3, LiNbO3 and LiTaO3 were irradiated by 800 keV Kr+, Xe+, or Ne+ ions over the temperature range from 20 to 1100 K. The critical amorphization temperature, Tc, above which radiation-induced amorphisation does not occur varied from approximately ∼450 K for the titanate compositions to more than 850 K for tantalates.

TL;DR: In this article, tensile specimens were irradiated at ≃70 °C in the HFIR reactor at Oak Ridge National Laboratory to fluences in the range of 4.5×1020-4.7×1024 n/m2 (E>1 MeV) corresponding to displacement dose levels in range of about 0.0001-0.8 dpa.

TL;DR: In this paper, the correlation between microstructure and corrosion characteristics of Zr-Nb alloy was investigated, and the microstructural observation and corrosion test with the change of cooling rate from beta temperature and the variation of Nb content were performed.

TL;DR: In this article, a computational study of some fission products (FP) energetics in uranium dioxide is presented, and solutions energies are calculated within the density functional theory in the local density approximation with the plane wave pseudopotential method.

TL;DR: In this article, the radial distributions of Xe, Cs and Nd in the UO2 fuel matrix were measured using an Electron Probe Microanalysis (EPMA) and scanning electron microscopy (SEM) techniques.

TL;DR: In this paper, the solubility of Li 2 O in LiCl was measured to be 8.8 wt% at 650 °C. This result indicates that the reduction proceeds more easily than the prediction based on the Gibbs free energy of formation.