Postirradiation examination results from SP-1

This paper describes the postirradiation examination results from several of the fuel pins irradiated in the SP-1 test. The SP-1 test is the first of two tests irradiated in EBR-II to be examined. These tests are designed to provide a direct comparison of the performance potential of UO/sub 2/ and UN fuel pins under conditions anticipated for the SP-100 reactor. In addition, these tests examine various feasibility issues associated with each fuel system. These issues include: the high temperature swelling behavior of uranium nitride fuel, fuel-cladding compatibility and the potential for UO/sub 2//Li reactions by oxygen diffusion through the cladding

Fuel systems for compact fast space reactors

About 200 refractory metal clad ceramic fuel pins have been irradiated in thermal reactors under the 1200 K to 1550 K cladding temperature conditions of primary relevance to space reactors. This paper reviews performance with respect to fissile atom density, operating temperatures, fuel swelling, fission gas release, fuel-cladding compatibility, and consequences of failure. It was concluded that UO/sub 2/ and UN fuels show approximately equal performance potential and that UC fuel has lesser potential. W/Re alloys have performed quite well as cladding materials, and Ta, Nb, and Mo/Re alloys, in conjunction with W diffusion barriers, show good promise. Significant issues to be addressed in the future include high burnup swelling of UN, effects of UO/sub 2/-Li coolant reaction in the event of fuel pin failure, and development of an irradiation performance data base with prototypically configured fuel pins irradiated in a fast neutron flux

Performance testing of refractory alloy-clad fuel elements for space reactors

Two fast reactor irradiation tests, SP-1 and SP-2, provide a unique and self-consistent data set with which to evaluate the technical feasibility of potential fuel systems for the SP-100 space reactor. Fuel pins fabricated with leading cladding candidates (Nb-1Zr, PWC-11, and Mo-13Re) and fuel forms (UN and UO/sub 2/) are operated at temperatures typical of those expected in the SP-100 design. The first US fast reactor irradiated, refractory alloy clad fuel pins, from the SP-1 test, reached 1 at. % burnup in EBR-II in March 1985. At that time selected pins were discharged for interim examination. These examinations confirmed the excellent performance of the Nb-1Zr clad uranium oxide and uranium nitride fuel elements, which are the baseline fuel systems for two SP-100 reactor concepts

Synergies between computational modeling and experimental characterization of materials across length scales

International audienc

The diffusion coefficient of scandium in dilute aluminum-scandium alloys

The diffusion coefficient of Sc in dilute Al-Sc alloys has been determined at 748 K, 823 K, and 898 K (475 °C, 550 °C, and 625 °C, respectively) using semi-infinite diffusion couples. Good agreement was found between the results of the present study and both the higher temperature, direct measurements and lower temperature, indirect measurements of these coefficients reported previously in the literature. The temperature-dependent diffusion coefficient equation derived from the data obtained in the present investigation was found to be D(m2/s)=(2.34±2.16)*10-4(m2/s)exp((-(167±6)(kJ/mol))/RT). Combining these results with data from the literature and fitting all data simultaneously to an Arrhenius relationship yielded the expression D(m2/s)=(2.34±0.84)*10-4(m2/s)exp((-(167±2)(kJ/mol))/RT). In each equation given above, R is 0.0083144 kJ/mol K, T is in Kelvin, and the uncertainties are ±1 standard error

Atom Probe Tomography at The University of Sydney

Summary: The Australian Microscopy & Microanalysis Research Facility (AMMRF) operates a national atom probe laboratory at The University of Sydney. This paperprovides a brief review and update of the technique of atom probe tomography (APT),together with a summary of recent research applications at Sydney in the scienceand technology of materials. We describe recent instrumentation advances such asthe use of laser pulsing to effect time-controlled field evaporation, the introductionof wide field of view detectors, where the solid angle for observation is increased byup to a factor of ∼20 as well as innovations in specimen preparation. We concludethat these developments have opened APT to a range of new materials that werepreviously either difficult or impossible to study using this technique because of theirpoor conductivity or brittleness

Microstructure and Strengthening Mechanisms in an Ultrafine Grained Al-Mg-Sc Alloy Produced by Powder Metallurgy

Additions of Sc to an Al-Mg matrix were investigated, paying particular attention to the influence of Al3Sc precipitates and other dispersoids, as well as grain size, on mechanical behavior. Prior studies have shown that Sc significantly increases the strength of coarse-grained Al-Mg alloys. Prompted by these findings, we hypothesized that it would be of fundamental and technological interest to study the behavior of Sc additions to an ultrafine-grained (UFG) microstructure (e.g., 100\u27s nm). Accordingly, we investigated the microstructural evolution and mechanical behavior of a cryomilled ultrafine grained Al-5Mg-0.4Sc (wt pct) and compared the results to those of an equivalent fine-grained material (FG) produced by powder metallurgy. Experimental materials were consolidated by hot isostatic pressing (HIP\u27ing) followed by extrusion or dual mode dynamic forging. Under identical processing conditions, UFG materials generate large Al3Sc precipitates with an average diameter of 154 nm and spaced approximately 1 to 3 μm apart, while precipitates in the FG materials have a diameter of 24 nm and are spaced 50 to 200 nm apart. The strengthening mechanisms are calculated for all materials and it is determined that the greatest strengthening contributions for the UFG and FG materials are Mg-O/N dispersion strengthening and precipitate strengthening, respectively