In this thesis I will present an approach and apparatus for detecting and precisely characterizing any dose-dependent changes in the functional behaviour of a data converter in a neutron radiation environment. Depending on the data converter such changes could include shifts in the gain, offset, noise, or linearity of the device output. The approach leverages the neutron flux produced by an Americium-Beryllium radioisotope neutron source, and is meant to emulate the neutron environment near a Cm-244 source, as found in the sensor head of the APXS instrument. This method uses a relatively low dose rate (configurable by proximity to the source) which allows for long-term monitoring and characterization of parametric changes in device behaviour. It has the additional benefit of not requiring a reactor or accelerator, and can therefore run unattended when necessary. The prototype system, which is designed to allow the data converter to be operating during irradiation, uses LVDS signalling to drive and extract data from a minimal test board which is placed in proximity to the neutron source, and a Virtex-4 FPGA board to provide clock and power, and to perform signal processing. By separating the majority of the test equipment from the neutron environment, any radiation effects will be isolated to the DUT and a minimal set of supporting devices. The prototype design is presented here, along with initial characterization results and first test results on a commercial, off-the-shelf data converter. / Canadian Space Agency, Ontario Centres of Excellence, MacDonald, Dettwiler, and Associates

It is proposed to continue operating the graphite moderated Advanced Gas-cooled Reactor (AGR) fleet past its design life. Nuclear graphite's properties change in reactor and our limited mechanistic understanding of the relationship between graphite structure, across different lengthscales, and its properties limits our ability to predict its future behaviour. An improved understanding of the relationship between graphite's structural features, the relationship between features across different lengthscales and their effect on material properties would all contribute to a mechanistic understanding of graphite behaviour. Thermal expansion generates thermal strains and stresses in the graphite core during thermal transients, such as during reactor start-up and shut-down. Thermal expansion is a function of graphite crystal thermal expansion, crystallographic preferred orientation and microstructure, although the exact relationship between these is not understood. It is also altered by neutron irradiation. This thesis investigates graphite microstructure, virgin and irradiated, and its crystallographic preferred orientation, specifically as they pertain to thermal expansion. The microstructure of British nuclear graphites PGA and Gilsocarbon, used in the Magnox and AGR fleet respectively, have been investigated using scanning electron microscopy (SEM). Trepanned AGR graphite, that is, graphite drilled from the reactor brick during routine inspection is examined. These samples are from the 2012 Hinkley Point B inspection campaign and are taken from several points through the brick thickness. This provides a 'snap shot' of current AGR graphite condition. Deep trepan samples removed from further into the brick thickness are observed for the first time. Neutron damage was observed in Magnox graphite, irradiated in an inert environment in the material test reactor programme INEEL. The spatial variation in texture of PGA and Gilsocarbon, and the change in such texture after prestress was observed using synchrotron x-ray diffraction. Numerical models were used to identify the required texture change to produce changes in CTE, observed by other authors, during in-situ stress. PGA filler lamellae are arranged in parallel arrays and Gilsocarbon's smaller platelets are arranged in bunched clusters. Severe radiolytic oxidation is observed at all trepan locations, with oxidation decreasing away from the fuel. Radiolytic oxidation occurs at platelet edges. Texture measurements have indicated that PGA graphite exhibits significant spatial variation in texture. Gilsocarbon exhibits less variation but the variation observed is large enough to cause increased thermal stresses. Texture measurements of prestressed graphite have indicated that texture changes also vary spatially. Texture results and SEM observations indicate that spatial variation in texture is caused by spatial variation in microstructure. Changes to the filler particle during prestress may alter local texture. These results indicate there is a link between nuclear graphite's microstructure and its texture. The texture, a function of lamellae or platelet arrangement, determines its thermal expansion. Spatial variations in microstructure formed during manufacturing leads to spatial variations in CTE and possibly other texture sensitive properties, such as dimensional change. Deformation of the lamellae or platelets during stress; thermal creep or irradiation creep is expected to contribute to the observed change in properties associated with these stimuli.

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