Showing papers in "Journal of Nuclear Materials in 2014"

TL;DR: In this article, three general strategies for accident tolerant fuels are explored: modification of current state-of-the-art zirconium alloy cladding to further improve oxidation resistance (including use of coatings), replacement of Zr Alloy cladding with an alternative oxidation resistant high-performance cladding, and replacement of the monolithic ceramic oxide fuel with alternative fuel forms.

TL;DR: In this article, an application of advanced oxidation-resistant iron alloys as light water reactor fuel cladding is proposed, based on specific limitations associated with zirconium alloys.

TL;DR: In this article, a summary of the properties of SiC/SiC composites with chemically vapor-infiltrated (CVI) SiC matrices is presented.

TL;DR: The silicon carbide fiber-reinforced SiC/SiC composite system for fusion applications has seen a continual evolution from development a fundamental understanding of the material system and its behavior in a hostile irradiation environment to the current effort which is directed at a broad-based program of technology maturation program as mentioned in this paper.

TL;DR: The findings of the EU 'Materials Assessment Group' (MAG), within the 2012 EU Fusion Roadmap exercise, are discussed in this paper, where the authors analyse the technical consequences for the materials required and the development, testing and modelling programmes, using: a systems engineering approach, considering reactor operational cycles, efficient maintenance and inspection requirements, and interaction with functional materials/coolants.

TL;DR: In this paper, the impact of fuel/cladding materials on the fuel performance at normal operating conditions and on the reactor system under DB and BDB accident conditions was analyzed. But the authors focused on the impact on the nuclear power station's fuel performance.

TL;DR: In this paper, a standardized methodology for carrying out joint testing has been established consistent with the small volume samples mandated by neutron irradiation testing, and significant progress made towards identifying and processing irradiation-tolerant joining methods for nuclear-grade SiC.

TL;DR: The China low activation martensitic (CLAM) steel is being developed at the Institute of Nuclear Energy Safety Technology (INEST) under wide collaboration within China as mentioned in this paper, and significant R&D work on CLAM steel was carried out to help make it suitable for industrial applications.

TL;DR: In this paper, the authors focus on clarifying remaining uncertainty in the operating temperature window of V-4Cr-4Ti for application to near to middle term fusion blanket systems, and on further exploration of advanced materials for improved performance for longer-term fusion reactor systems.

TL;DR: In this article, the nanoparticles in an Al-alloyed high-Cr oxide dispersion strengthened (ODS) ferritic steel with Hf addition, i.e., SOC-16 (Fe-15Cr-2W- 0.62Hf-0.35Y2O3), have been examined by transmission electron microscopy (TEM) and high resolution transmission electron microscope (HRTEM).

TL;DR: In this article, it has been shown that after the beginning of a rate drop due to the approach of silica saturation of the solution and the formation of a passivating layer, a resumption of alteration is possible.

TL;DR: The feasibility of using SiC f -SiC m composites in light water reactor (LWR) fuel designs was evaluated in this paper, which was motivated by the desire to improve fuel performance under normal and accident conditions.

TL;DR: In this paper, the effects of alloying elements, microstructure and corrosion kinetics on hydrogen uptake were investigated in zirconium-based alloys used for nuclear fuel cladding.

TL;DR: In this paper, microstructural development of pure tungsten (W) and Tungsten-rhenium (Re) alloys due to neutron irradiation in the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory, TN, USA, was investigated.

TL;DR: In this article, the authors quantify the contributions of different types of defect-solute clusters to the total irradiation-induced yield stress increase in industrial-purity Fe-Cr model alloys.

TL;DR: In this paper, the influence of void swelling on the depth-dependent defect imbalance between vacancies and interstitials has been investigated using the Boltzmann transport equation (BTE) method, and it was shown that void swelling does not depend solely on the local dose level.

TL;DR: In this article, the long-term behavior of SON68 nuclear glass towards alpha decay accumulation was investigated by examining glass specimens, doped with a short-lived actinide 244Cm, irradiated by light and heavy ions.

TL;DR: In this article, a dedicated framework for thermo-mechanical analysis of the in-pile performance of SiC/SiC composite fuel cladding concepts in LWRs has been developed.

TL;DR: In this paper, the authors investigated the long-term corrosion behavior of Ni-based Hastelloy-N and B3 under moisture-containing molten alkali fluoride salt (LiF-NaF-KF: 46.5-11.5

TL;DR: In this article, the state of the art of fundamental data for substance or materials involved in pyropocessing is reviewed and reanalyzed, and new correlations are developed based on available data from different measurements.

TL;DR: A review of the work done on RAFM steels by the fusion materials community over the past 30 years, in particular on the Eurofer steel and its design code qualification for RCC-MRx can be found in this paper.

TL;DR: In this paper, nano-sized boron carbide (B4C) powder was prepared using ball milling, and milled nano-powders were melt blended with high density polyethylene (HDPE) using a polymer mixer followed by hot pressing to fabricate sheet composites.

TL;DR: In this paper, the potential swelling behavior of the ODS ferritic alloy MA957 at very high dpa levels was studied using a transmission electron microscopy (TEM).

TL;DR: In this paper, the authors addressed the feasibility issues facing the application of SiC-matrix microenculated fuels for light water reactor application and found that the SiC matrix was quite stable with behavior similar to that of CVD SiC.

TL;DR: In this paper, it is shown that uncertainty bands related to oxygen behavior in the equilibria between condensed phases and gas should not significantly affect the qualitative trend of the current solid-liquid phase boundaries.

TL;DR: In this article, the thermal stability of a pure tungsten plate warm-rolled to 67% thickness reduction was investigated by long-term isothermal annealing in the temperature range between 1150-°C and 1350-h up to 2200h.

TL;DR: In this paper, atom probe tomography was used to characterize the microstructural changes in a Fe-15-at%Cr model alloy irradiated to 182-dpa at 290-°C.

TL;DR: In this article, the diffusion of fission gas atoms (Xe) in UO2 nuclear fuel has been calculated for a range of non-stoichiometry (i.e. UO 2 ± x ), under both out-of-pile (no irradiation) and inpile(irradiation) conditions.

TL;DR: In this paper, the glass ceramics are developed to immobilize fission products, separated from used nuclear fuel by aqueous reprocessing, into a stable waste form suitable for disposal in a geological repository.

TL;DR: In this paper, Zr was used to capture impurity oxygen in tungsten and form nanometer scaled ZrO2 particles, which significantly increased the fracture strength and toughness of tengsten.