Showing papers in "Journal of Nuclear Materials in 1992"

TL;DR: In the absence of Pb, schoepite and becquerelite are the common initial corrosion products as mentioned in this paper, and they can dissolve completely under similar geochemical conditions.

TL;DR: In this article, a fully implicit, time dependent 2D fluid code is described that models the edge plasma region of a tokamak with a divertor or limiter.

TL;DR: The paragenetic sequence (from uraninite to schoepite to uranyl silicates) is identical to those observed in weathered Uraninite deposits as discussed by the authors.

TL;DR: A review of the status of various approaches dealing with tokamak edge related issues by employing two-dimensional numerical fluid codes for the main components of the edge plasma is given in this article.

TL;DR: The paper outlines the main features and capabilities of the TRANSURANUS code, its validation and treats also some practical aspects.

TL;DR: A revised structural formula for uraninite, nominally UO 2, was presented in this article, which emphasizes the role of cationic substitutions and clarifies the relationship between structural properties (e.g., unit cell parameters), oxidation state (U 6+ /U 4+ ratio), and phase transformations with increasing concentrations of excess oxygen.

TL;DR: In this paper, the 2D multifluid edge code B2 coupled with the 3D neutral gas Monte Carlo code EIRENE is used for edge interpretation and model validation on the axisymmetric poloidal divertor experiments ASDEX and ASDEX-Upgrade.

TL;DR: A comprehensive review of the literature on uranium and plutonium electrorefining in molten salts is given in this paper, which covers work published from 1943 to November 1991 and discusses electrodeposition and electrodissolution at solid and liquid metal electrodes as well as mass transfer in liquid metal and molten salt phases.

TL;DR: The behavior of uraninite under reducing conditions is discussed in this article, based on data in the literature and the investigation of samples from two natural analogue sites: Oklo, Gabon and Cigar Lake, Canada.

TL;DR: In this article, a diagnostic technique based on the measurement of the radial intensity profiles of selected lines emitted by an injected thermal He-atom beam was developed, which is used for the calculation of impurity fluxes from line intensities, for an estimate of the radiation losses in the boundary, and for the modelling of the particle and power fluxes in the scrape-off layer.

TL;DR: In this article, the current status of the Swedish program for the study of the corrosion of spent fuel in bicarbonate groundwaters is presented and compared with the data base accumulated over the past ten years Release of uranium and other actinides was solubility-controlled under the semistatic type of experiments performed.

TL;DR: An electrochemistry-based model to predict the dissolution of UO2 fuel under both oxidizing and nonoxidizing conditions is presented and compared with other available models for fuel dissolution as mentioned in this paper.

TL;DR: In this paper, the authors discuss the consequences of the production of small glissile self-interstitial loops under cascade damage conditions, and propose the production and incorporation of such loops into extended sinks such as dislocations and grain boundaries as an efficient driving force for void swelling, in particular in regions adjacent to grain boundaries.

TL;DR: In this article, a wide range of models/assumptions about the divertor edge plasma behavior is examined with regard to the effect on the spectroscopic intensities of C+ through C5+ in the vicinity of divertor targets.

TL;DR: In this article, a high density region near the X-point appears to play a role in momentum transfer from the flux surfaces near the outboard strike point to flux surfaces farther out into the scrapeoff.

TL;DR: In this paper, it was shown that grain subdivision related to the formation of highly pressurized (probably solid) Xe-precipitates occurs at implantation doses corresponding to fission product concentrations reached at 7 to 8 at% burnup.

TL;DR: In this article, a study by transmission electron microscopy has been made of the incorporation and oxidation of intermetallic precipitates Zr(Cr,Fe)2 into the uniform oxide layer of Zircaloy-4.

TL;DR: In this paper, the microstructural changes in commercial light-water reactor (LWR) fuels irradiated to average burnups near 50 MWd/kgM were studied by analytical transmission electron microscopy and Auger electron spectrometry.

TL;DR: The microstructure of commercial pressure vessel steels that have been neutron-irradiated is extremely complex and involves many different types of features, such as ultrafine distributions of copper atmospheres, clusters and precipitates, phosphorus clusters, molybdenum carbides and nitrides, and vanadium carbo-nitrides in the matrix as mentioned in this paper.

TL;DR: In this article, the microstructural change of UO2 fuel pellets (burnup: 6 −83 GWd/t), base irradiated under LWR conditions, has been studied by detailed postirradiation examinations.

TL;DR: In this article, a polyphase titanate ceramic designed to immobilise high-level nuclear waste was subjected to MCC-2 type dissolution tests at 150°C in doubly deionised water (surface area to volume ratio 0.01 ± 0.0005 mm −1 ).

TL;DR: In this paper, the authors collected all the primary measurements of diffusivity available in literature, and then calculated the conductivity by using up-to-date recommendations for heat capacity and density.

TL;DR: In this paper, the thermal conductivity of graphite materials was investigated at temperatures from 200 to 400°C to fluences of 0.01 to 0.82 dpa in JMTR.

TL;DR: In this paper, the results from recent studies on radiation-induced changes in the electrical conductivity, loss tangent, and thermal conductivity of ceramics are reviewed, with particular emphasis on in-situ data obtained during irradiation.

TL;DR: In this article, the deuterium-tungsten system was studied using thermal desorption spectrometry (TDS) using Auger electron spectroscopy to monitor surface coverage with impurities.

TL;DR: In this article, the effects of neutron irradiation on copper alloys are briefly discussed in terms of radiation damage and its influence on conductivity and mechanical properties, the compositional changes occurring through transmutation and the induced activity and associated γ-dose rate and biological hazard potential.

TL;DR: In this article, the experimental data on temperature dependencies of bubble density obtained under different experimental conditions are compiled and analyzed, in particular, the effects of parameters such as helium concentration, helium generation rate, annealing time and displacement damage rate on measured bubble densities are considered.

TL;DR: In this paper, microstructural change related to irradiation to high burnup levels (up to 83 MWd/kgM pellet-average) is observed, characterized by the loss of optically-definable grain structure, increased porosity, and depletion of matrix fission gas.

TL;DR: In this paper, the authors used transmission electron microscopy (TEM) to determine the behavior of solid and gaseous fission products under a variety of conditions, and their interactions with the fuel microstructure.

TL;DR: In this paper, the authors investigated the effect of the irradiation temperature on the mechanical properties of W and Mo alloys and showed that at T irr ~ 250-550°C irradiation embrittlement and intercrystalline fracture take place.