Showing papers in "Journal of Nuclear Materials in 1993"

TL;DR: In this article, the evolution of mechanical properties in austenitic stainless steels during irradiation is reviewed and the effects of irradiation on fatigue appear to be modest except at high temperature where helium embrittlement becomes important.

TL;DR: In this paper, microstructural data on the evolution of the dislocation loop, cavity, and precipitate populations in neutron-irradiated austenitic stainless steels are reviewed in order to estimate the displacement damage levels needed to achieve the steady state condition.

TL;DR: In this paper, the α to γ transformation in ODS martensitic steel has been successfully achieved by introducing the α-to-γ transformation in 13Cr-3W ODS ferritic steels.

TL;DR: In this paper, a review of hydrogen bubble formation in metals is presented, focusing on those areas of bubble formation where the distinct chemical character of hydrogen is important, and a distinction is made between nucleation and subsequent cavity growth mechanisms.

TL;DR: In this paper, the authors identify three significant aspects of defect accumulation behavior under cascade damage conditions: (a) evolution of cavity microstructure in a spatially heterogeneous and segregated fashion, (b) high swelling rates at very low doses when the dislocation density is negligibly low and (c) enhanced vacancy accumulation in the vicinity of grain or subgrain boundaries.

TL;DR: In this paper, the mechanisms of defect production in displacement cascades in α-iron have been investigated by computer simulation, and the morphology of cascades during the collisional phase changes at about 1-2 keV, due to the collective nature of atomic displacements at higher energy.

TL;DR: In this article, the authors provide an overview of the large and complex body of data accumulated from various fission reactor irradiation experiments conducted over the many years of research on microstructural evolution in this family of steels.

TL;DR: A review of the current understanding of the subject, giving were possible examples of the approach and techniques used to obtain this, can be found in this paper, where the authors also highlight areas of current research activity and indicate the type of work still required to provide information on aspects that currently lack a full understanding.

TL;DR: In this paper, the authors review the evolution of the defect population in an isolated displacement cascade, and outline a framework for identifying the relevant components of displacement damage and defect production under cascade damage conditions.

TL;DR: The detailed characteristics of fission gas bubbles in UO2 fuel pellets (burnup: 6-83 GWd/t) before and after postirradiation annealing at 1600 and 1800°C have been examined by TEM and SEM fractography as discussed by the authors.

TL;DR: In this paper, the microstructural evolution of a 17Cr ferritic steel (F17) and five stabilized (EM12, FV448, HT9 and 1.4914) or unstabilized (EM10) 9-12Cr Ferritic-martensitic steels irradiated in Phenix were examined.

TL;DR: The first fast breeder reactors, constructed in the 1945-1960 time period, used metallic fuels composed of uranium, plutonium, or their alloys, and they were chosen because most existing reactor operating experience had been obtained on metallic fuels and because they provided the highest breeding ratios.

TL;DR: In this article, fabrication tests of thin-walled cladding tubes were carried out from a viewpoint of future industrial manufacturing, and the manufactured claddings within the specification limit exhibited a superior high temperature strength and sufficient Charpy impact properties.

TL;DR: The results indicated that Zircaloy-2, Ti-5% Ta and thermally-oxidised Ti showed excellent corrosion resistance also in a simulated uranium-containing reprocessing medium in a concentrated nitric acid solution.

TL;DR: In this paper, a set of kinetic equations taking the escape of one-dimensionally gliding SIA loops into account is proposed to represent an efficient driving force for void swelling, in particular in regions adjacent to grain boundaries.

TL;DR: In this article, a number of different borosilicate glasses were developed in different national programs and the criteria and the reasons for selecting the final compositions are described briefly, focusing on the French product R7T7 and on thermal and physicochemical properties though glasses developed in other national projects (e.g., the German product GP 98/12, etc.).

TL;DR: In this article, the authors review recent ion-irradiation experiments which have been performed to investigate the collapse of displacement cascades to dislocation loops in a range of metals and alloys.

TL;DR: In this article, a review of the experimental observations of ordered defect structures formed in metals under irradiation with energetic particles, such as neutrons, ions, and electrons, is given.

TL;DR: In this paper, the hyperstoichiometric U 4 O 9 produced by air-oxidation of LWR spent fuel was studied by ceramography, XRD, TEM, and thermal analysis methods.

TL;DR: In this article, the concept, derivation, and usefulness of irradiation variable shifts based on a requirement of invariance in point defect absorption was discussed. But the authors did not consider the effects of different types of irradiations on point defect concentrations, helium buildup, and embrittlement.

TL;DR: For pure hexagonal-close-packed (hcp) metals, the principal habit plane for dislocation loop nucleation is generally the most close-packed plane and this varies with c/a ratio as discussed by the authors.

TL;DR: In this paper, the effectiveness of CVD coatings on TZM and 316L stainless steel in the form of discs of diameter 48 mm and thickness 0.1 or 1 mm was investigated.

TL;DR: A review of such studies shows that a number of prevailing perceptions of radiation-induced microstructural evolution are not universally correct as discussed by the authors, and the use of irradiation studies conducted on simple metals or model alloys assists in understanding the behavior of alloys of engineering relevance.

TL;DR: In this article, the release behavior of metallic fission products from the Triso-coated UO 2 particles was studied by postirradiation heating tests in the temperature range 1600 to 1900°C (1873 to 2173 K) and subsequent postheating examinations.

TL;DR: In this article, the Gibbs energy of the liquid phase is described by the inclusion of associate species and non-ideal interactions between the components and associate species, and the results show that the overall system cannot properly be treated as a pseudo ideal liquid and solid solution.

TL;DR: In this article, the authors conducted twenty-five elevated-temperature tests on irradiated U-19wt%Pu-10wt%Zr fuel clad with HT9 at the Alpha-Gamma Hot Cell Facility at Argonne National Laboratory, Illinois.

TL;DR: In this article, the authors showed that diffusion of Fe is the rate-controlling process for Fe depletion in Zr(Fe, Cr)2 precipitates in Zircaloy-2 and -4.

TL;DR: In this paper, a nuclear fuel injection cast with the addition of two minor actinides, 2.1% Am and 1.3% Np, was reported to contain 60% of the initial Am and 100% of Np charge was present in the as-cast fuel.

TL;DR: In this paper, the formation of a permeation barrier on DIN 1.4914 (MANET) martensitic stainless steel by plasma spraying aluminium on the surface of the steel, followed by heat treatment of the sample to form Al3Fe and Al5Fe2.