Showing papers in "Journal of Nuclear Materials in 2000"

TL;DR: The thermophysical properties of uranium dioxide from room temperature to 6000 K are reviewed in this article, including enthalpy, heat capacity, vapor pressure, density, thermal expansion, compressibility, thermal conductivity, viscosity, and emissivity.

TL;DR: In this article, it was shown that the steady-state swelling rate of bcc steels is inherently much lower than that of fcc and that the creep compliance of the two types of alloys also differs only by a factor of about two.

TL;DR: In this article, the mechanism of the coupled anodic (fuel dissolution) and cathodic (oxidant reduction) reactions which constitute the overall fuel corrosion process is reviewed, and the many published observations on fuel corrosion under disposal conditions discussed.

TL;DR: In this article, the microstructural changes in tungsten during low-energy He+ ion irradiations in an electron microscope linked with an ion accelerator were investigated in an in situ transmission electron microscopy (TEM) study.

TL;DR: In this article, the differences and similarities of behaviour between fee and bcc metals after irradiation have been investigated, and it is shown that a dense population of defect clusters (up to 10(22)-10(24) m(-3)) develops, the type of cluster formed depending apparently on the stacking fault energy.

TL;DR: In this paper, the effect of crystal structure on defect formation in pure metals and alloys of primary knock-on atom (PKA) energy and irradiation temperature is investigated, with particular emphasis on the influence of crystal structures.

TL;DR: In this article, the Taylor factor with a value of 3.06 is the correct parameter to apply in such work, based on an inappropriate application of the von Mises and Tresca yield criteria.

TL;DR: In this paper, the authors summarized results obtained by molecular dynamics simulations of defect clusters and small dislocation loops in α-Fe(bcc) and Cu(fcc), and the structure and stability of vacancy and interstitial loops are reviewed, and the dynamics of glissile clusters assessed.

TL;DR: In this paper, a number of simulations have been used to investigate the formation of atomic displacement cascades in iron with energies up to 50 keV (corresponding to a primary knock-on atom (PKA) energy of 79 keV) at 100 K, up to 20 keV at 600 K, and up to 10 kV at 900 K.

TL;DR: In this article, a low alloyed martensitic steel Fe9Cr (OPTIFER IVc) and an austenitic steel 16Cr15Ni (1.4970) were exposed to liquid lead to examine their suitability as structural material for lead cooled accelerator driven subcritical actinide burners.

TL;DR: In this article, the authors have simulated damage production and accumulation in fcc Cu and bcc Fe using 20 keV primary knock-on atoms (PKAs) at a homologous temperature of 0.25 of the melting point.

TL;DR: In this paper, the phase stability of 3C-SiC and the threshold displacement energy (E d ) surfaces for C and Si primary knock-on atoms (PKAs) were investigated using molecular dynamics simulations.

TL;DR: The International Energy Agency (IEA) agreement has been an effective framework for international co-operation in developing reduced activation ferritic/martensitic (RAFM) steels as mentioned in this paper.

TL;DR: In this paper, the authors used the embedded-atom method (EAM) to model the energy and mobility of self-interstitial atom (SIA) clusters in bcc α-iron.

TL;DR: SiC fiber-reinforced SiC matrix composites (SiC/SiC) are being considered as a candidate structural material for fusion reactors because of their low induced radioactivity by 14 MeV neutron irradiation and high-temperature strength.

TL;DR: In this paper, a zirconia (ZrO2)-based single-phase ceramic containing simulated excess weapons plutonium waste was synthesized, and significant amounts of gadolinium (neutron absorber) and yttrium (additional stabilizer of the cubic modification) can be dissolved in ZrO 2, together with plutonium (simulated by Ce4+, U4+ or Th4+) and impurities.

TL;DR: In this article, a trimetallic joint involving modified 9Cr-1Mo steel and 316LN austenitic stainless steel as the base materials and Alloy 800 as the intermediate piece was investigated.

TL;DR: In this paper, the authors examined the formation and strength of dipoles and junctions, and effect of jogs, using the dislocation dynamics model, and showed that the strength of these reactions for various configurations can be determined by direct evaluation of the elastic interactions.

TL;DR: In this article, a set of ODS steels with varying oxide particle dispersion were irradiated at 650°C, using 3.2 MeV Fe + and 330 keV He + ions simultaneously.

TL;DR: In this paper, the impact of different frequencies of changes in the 1-dimensional diffusion direction of interstitial clusters on their reaction kinetics is discussed, and an appropriate framework for generalising the PBM in order to describe damage accumulation behavior in metals and alloys in general, including the formation of void superlattices.

TL;DR: In this paper, a basic composition of low activation ferritic steel (Fe-12Cr-2W-0.05C), cladding tube manufacturing by means of pilger mill rolling and subsequent recrystallization heat-treatment was conducted while varying titanium and yttria contents.

TL;DR: In this paper, two alloys, having different oxidation behavior (Zy4 and Zr-1NbO), have been investigated during oxidation at high temperature (743 K) and low oxygen pressure (10 kPa) by in situ X-ray diffraction (XRD).

TL;DR: In this paper, a bimodal distribution of coarse precipitates with spacings larger than 1 μm and tiny precipitates having spacings between 30 and 40 nm was observed by scanning electron microscopy (SEM).

TL;DR: In this paper, the alteration kinetics of the French SON 68 nuclear glass simplified to its three major constituent elements (Si, B and Na) were investigated by static experiments at 90°C in order to deconvolute the effects of the solution chemistry and of the alteration gel on the diminishing alteration rate over time.

TL;DR: In this article, the effects of neutron irradiation on thermal and mechanical properties and bulk tritium retention of armour materials (beryllium, tungsten and carbon) are reviewed.

TL;DR: In this article, Austenitic stainless steels 316L(N)-IG and 316L, nickel-based alloys Inconel 718 and ICONEL 625, Ti-6Al-4V alloy and two copper alloys, CuCrZr−IG and CuAl25−IG, have been proposed as reference structural materials, and ferritic steel 430, and austenitic steel 304B7 with the addition of boron have been selected for some specific parts of the ITER in-vessel components.

TL;DR: In this paper, nanoindentation measurements of the incremental increase in hardness caused by 360 keV He-ions implanted at 200°C to concentrations from 2 to 200,000 appm.

TL;DR: In this article, the total erosion yields of graphite and carbon materials under hydrogen and deuterium bombardment measured with the weight-loss method are presented for ion energies between 15 eV and 8 keV in the temperature range 300 to above 1000 K.

TL;DR: In this article, the authors have found that the primary damage is potential sensitive and that the repulsive part of the potential has a strong influence on the cascade morphology and equilibrium properties such as the atoms mean square displacements, the vacancy migration and vacancy binding energies also appear to have some influence and should be investigated carefully when simulating radiation damage.

TL;DR: In this article, the authors measured the thermal diffusivity of PWR mixed oxide fuels with Pu contents ranging from 3 to 15 wt% and oxygen to metal ratio (O/M) ranging from 2.00 to ∼1.95.