Showing papers in "Journal of Nuclear Materials in 1974"

TL;DR: In this article, an analysis of the segregation-induced strain field around the voids indicates that minor substitutional alloying elements with negative and positive size factors segregate towards and away from the void surface respectively.

TL;DR: In this article, the void swelling tendencies of over twenty Fe-Cr-Ni alloys have been compared by bombarding with 5 MeV Ni ions, and the results imply that the major composition of an alloy has a strong influence on swelling behavior.

TL;DR: In this paper, the results show a significant reduction of both gas release and swelling with increasing grain size, and the major contribution to swelling was due to grain-edge tunnels which were extensively interlinked to the free surface.

TL;DR: In this article, the conditions of redox potential and oxide concentration wherein the fuel may be contained without significant corrosion or precipitation reactions, or conditions wherein selective oxide precipitation may be carried out for purposes of fuel reprocessing are presented.

TL;DR: In this article, an equilibrium phase diagram is proposed, and the relationship between structure and lattice parameter for the α-U 2 N 3 -UN 2 system is shown; the data on decomposition pressures, specific heats, and heat and free energies of formation are summarized and evaluated.

TL;DR: In this article, the authors attributed delayed failures at welds in components of Zi-2.5 wt % Nb are attributed to zirconium hydride forming at the root of a notch adjacent to the welds.

TL;DR: In this paper, a weak beam image of long and relatively straight dislocation lines in annealed Zr3Al was obtained to obtain information on the equilibrium width of the extended dislocations.

TL;DR: In this article, a technique using nuclear microanalysis has been developed to determine 2D an 3He concentrations versus depth profiles in the near surface regions (∼2 μm) of solids.

TL;DR: In this article, the defect structure of UO 2+x has been reviewed and the variation of the relative partial molar entropy of oxygen with composition in the UO2+x phase was derived on the basis of the 2:2:2 defect complex model proposed from the neutron diffraction study of Willis.

TL;DR: In this paper, the stability of the γ-hydrides and the possible existence of a δ-hydride → γhydride transformation has been studied in sponge zirconium sheet containing up to 500 ppm hydrogen (4.33 at %) at temperatures in the range 150-250°C.

TL;DR: In this paper, He re-emission was measured during 150 keV H+ implantation of Mo, V, and 316 SS between −90°C and 115 °C.

TL;DR: The critical dose at which blisters first appear is about 1 to 2 × 10 17 incident He ions per cm 2. It increases slightly with increasing ion energy and with decreasing target temperature as mentioned in this paper.

TL;DR: In this article, it was shown that void density is a strong function of irradiation temperature for a constant number of displacements per atom (dpa) and a function of reactor power and spectrum when normalized to dpa.

TL;DR: In this paper, reaction-bonded SiC loses nearly 50% of its fracture strength when exposed to neutron irradiation, and the damage occurs soon after exposure and levels out with continuing exposure up to 3 × 10 21 n/cm 2.

TL;DR: The steady-state rate of void nucleation for irradiated materials containing mobile helium was calculated for breeder-reactor environments as discussed by the authors, and the helium is less effective at high displacement rates typical of accelerator experiments, but can increase the void-nucleation rate by 10 4 at a helium concentration of 10 −8.

TL;DR: In this article, it was shown that dechanneling can be due to an obstruction, to the deformation of the lattice, or to both simultaneously, and the experimental results were in very satisfactory agreement with the theoretical estimates.

TL;DR: In this paper, a brief review of some of the important parameters governing the radiation blistering process is given, where erosion rates associated with helium blistering in V, Nb and Type 304 stainless steel are reported for different irradiation temperatures and different projectile energies.

TL;DR: In this paper, it was shown that the cascade generated stresses may be responsible for the emission of such particles by triggering the release of stored internal energy, and that spall phenomena may be in part responsible.

TL;DR: In this paper, a polyphase alloys based on ordered Zr3Al (Ll2 type) have been deformed in tension at 20 to 600°C and exposed to moist air (300°C), pressurized water and atmospheric pressure steam (400°C).

TL;DR: In this article, the residual resistivity increase rate, dpi/dt,as a function of induced resistivity for fast-neutron irradiated Cu, Nb and Nb doped with oxygen, V, Ta, Pb, Cd, Cc, Nc and NcTi has been studied after 18 K fast neutron irradiation.

TL;DR: In this paper, analytical and finite-difference methods developed to deal with diffusion in finite systems with moving boundaries were used to compute oxygen concentration profiles in the beta phase of Zircaloy specimens oxidized in steam.

TL;DR: In this article, the surface deformation produced by high-dose He and H implantations in Mo, 316 stainless steel, and V have been studied using scanning electron microscopy.

TL;DR: The effect of adding up to 0.33 wt % titania on grain growth and densification of UO2 has been studied in this article, where it was shown that the grain growth rate is proportional to the concentration of added titania up to the solubility limit, remaining constant thereafter.

TL;DR: In this article, the 3He (d,p)4He nuclear reaction was used together with ion channeling to determine the lattice locations of ion-implanted D and 3He in tungsten.

TL;DR: Tritium diffusion in niobium, Zircaloy-2 and stainless steel has been studied by measurement of both tritium concentration profiles and surface trittium release rates.

TL;DR: In this article, at room temperature polycrystalline targets of cold-rolled Marz grade niobium with beams of helium ions of 1, 5, 10 and 15 keV at doses varying from 0.1 to 10.0 C/cm 2.

TL;DR: In this paper, a model for the expected outgassing behavior of oxidized steels at temperatures which are of interest in the design of controlled thermonuclear research experiments and reactors is suggested.

TL;DR: The physical characteristics of thorium oxalate powders are dependent upon the precursor material and the calcining temperature, and the physical properties of the resulting oxides determined as mentioned in this paper.

TL;DR: In this article, a mathematical analysis for the carburization-decarburization kinetics of austenitic stainless steels in high-temperature flowing sodium has been developed that incorporates thermodynamic and kinetic information for carbon in the alloys, the thermal-mechanical treatment of the material (solution-annealed versus cold-worked) which influences the microstructure, and the carbon concentration in sodium and its dependence on sodium-system parameters.