Showing papers in "Journal of Nuclear Materials in 1991"

TL;DR: Simulated high-burnup nuclear fuel (SIMFUEL) replicates the chemical state and microstructure of irradiated fuel so that detailed experiments on fission gas release, thermal conductivity and leaching can be undertaken in the laboratory.

TL;DR: In this paper, an extensive investigation has been carried out into the effectiveness of aluminized layers as permeation barriers on AISI 316L stainless and DIN 1.4914 martensitic steels.

TL;DR: In this paper, the oxidation of Zircaloy by steam and by steam-hydrogen mixtures was studied experimentally from 1100-1600°C using the continuously-recording gravimetric method.

TL;DR: In this article, the crystal parameters and the cell volume of boron carbide compounds have been investigated versus composition by an improved method allowing the use of bulk samples and leading to a higher accuracy than previous determinations.

TL;DR: In this paper, the authors considered the nature of the Fe-enhancement mechanism in terms of vacancies strongly bound to either substitutional or interstitial Fe atoms and concluded that the experimentally observed substitutional diffusion enhancements are most readily interpreted as transport via an inter-stitial Fe/vacancy pair.

TL;DR: In this article, the reaction of oxygen and water vapour with UN microspheres containing 0.78 and 10.9 mol% UO2 as impurity was studied under non-isothermal heating conditions in a thermobalance under different partial pressures of oxygen, a fixed pressure of water vapours in argon, and in air.

TL;DR: In this article, the microstructures and mechanical properties of solution annealed 300-series austenitic stainless steels irradiated under conditions relevant to the design of near term fusion reactors were investigated.

TL;DR: In this paper, polycrystalline MgAl 2 O 4 and A1 2 O 3 have been irradiated with 18 MeV protons at temperatures from 200-500°C while maintained in an electric field of 500 kV/m.

TL;DR: Radiation-enhanced electrical breakdown was observed in Al2O3 under conditions simulating fusion reactor devices in this article, where ionization and displacement damage played key roles in the breakdown.

TL;DR: In this article, Alloy composition selection for improving creep rupture strength and toughness of reduced activation 9Cr-W steels was investigated, and minor additions of V, Ta and B stabilized the fine structure of lath martensite and markedly increased strength without any significant degradation of toughness.

TL;DR: In this paper, an atomistic model for describing the irradiation-induced amorphization and swelling of graphite is proposed, which shows that a high concentration of C2 molecules and their clusters between basal planes induce abrupt swelling along the c-axis within 4 × 10−3 dpa and fade the periodical structural image at 4× 10−2 dpa.

TL;DR: In this paper, the tensile and fatigue properties of cold-worked copper and a commercial Cu-Al2O3 dispersion-strengthened alloy were measured at temperatures between 25 and 600°C.

TL;DR: In this article, the results of irradiation experiments on N3M graphite at two temperatures, 600 and 875 °C in the High Flux Isotope Reactor (HFIR) at ORNL were reported.

TL;DR: In this paper, the effects of specimen thickness and aspect ratio (thickness/width) on tensile properties were studied, and scaling equations to evaluate valid yield strength and tensile strength from small specimens with thickness less than the critical thickness were proposed.

TL;DR: In this article, normalized-and-tempered 9Cr-1MoVNb and 12Cr1MoVW steels were irradiated in the Experimental Breeder Reactor II (EBR-II) at 390, 450, 500, and 550°C to displacement damage levels of up to 23 to 25 dpa.

TL;DR: In this article, a new strategy was applied to discriminate the working coarsening mechanism of inert gas bubble growth in metals, and the invariances of OR and migration and coalescence (MC) were investigated.

TL;DR: In this article, measurements of thermal conductivity were performed on irradiated SiC samples over a temperature range from 300 to 1700 K. The results showed that the thermal conductivities of the irradiated samples were reduced over a wide temperature range compared to the behavior of non-irradiated reference samples and that the extent of this reduction depends not only on the damage dose or particle fluence, but is also influenced by the irradiation temperature.

TL;DR: In this paper, the irradiation creep and swelling at 400-750°C of the fusion heats of PCA, HT9 and 9Cr-lMo were studied using pressurized tubes irradiated in the Fast Flux Test Facility (FFTF).

TL;DR: In this article, the energy density deposited into the lattice by the primary knock-on atom was derived by solving a simplified version of the beat equation, and a thermodynamic description of the cascades that allows us to analyze the influence of the cascade geometry on parameters like ion mixing, life time and volume of the melt.

TL;DR: In this article, the effects of the δ-ferrite phase on the impact properties of martensitic Cr-steels are investigated using instrumented impact testing and SEM investigations.

TL;DR: In this article, the swelling of unalloyed vanadium and vanadium alloys containing Cr, Ti, Si, Fe, Zr, W, Mo, and Ni was determined after neutron irradiation at 420 and 600°C to 17-84 dpa in the FFTF-MOTA reactor facility.

TL;DR: In this article, analytical electron microscopy and electrochemical potentiokinetic reactivation (EPR) testing were applied to the radiation-induced segregation (RIS) and sensitization of a titanium-modified austenitic stainless steel neutron-irradiated to 9 dpa.

TL;DR: In this paper, the theory of radiation-induced swelling is reviewed and concepts central to the understanding of experimental data and the control of swelling by alloy design are discussed, and approaches to alloy design for swelling resistance are recommended.

TL;DR: In this paper, the radiation enhanced sublimation (RES) effect of carbon materials with metals was investigated and the basic features of this model were presented and compared with experimental observations.

TL;DR: In this article, computer-simulated data concerning the incident energy and ion temperature dependence of the sputtering yields of lithium, gallium and indium due to light-particle (deuterium and tritium) bombardment are presented together with such data on the selfsputtering yields.

TL;DR: In this article, self-diffusion in α-Zr single crystals has been measured in the temperature interval 871-1074 K, with the effective activation enthalpy increasing with decreasing temperature.

TL;DR: The V-7.2Cr-14.5Ti, V-9.9Cr- 9.2Ti and V-2.5-1.0Si alloys were evaluated for use as structural material in fusion reactors.

TL;DR: In this paper, natural UO2+x (uraninite) samples were annealed in a reducing atmosphere up to 1200°C, and the initial unit cell parameters of 0.5385, 0.5469,0.5447,0.,5462, and 0.,5456 nm increased after annealing.