Temperature dependence of electrical resistivity, deformation, and fracture of polygranular graphite with different amounts of porosity

Synthetic polygranular graphites have a wide range of current and potential applications. Indeed, some are being considered as candidate moderator materials for the next generation of nuclear power plants, which are designed to operate at temperatures as high as 1000 °C. Detailed experimental work has been performed to investigate the electrical resistivity and mechanical behaviour of a synthetic graphite over a range of temperatures. An electrothermomechanical testing rig has been employed to conduct tensile tests to evaluate elastic modulus and fracture strength over the temperature range from room temperature to 700 °C for a near-isotropic synthetic polygranular graphite. A series of mm length scale ‘dogbone’ geometry specimens, containing varying levels of porosity between 8% and 18%, were used for testing. Acquired data revealed an average of 30% gain in material stiffness, occurring at temperatures above 400 °C. Tensile strength decreased linearly with increasing porosity at higher temperatures (700 °C). The accumulated percentage reduction of resistivity during the transition from room temperature to 700 °C reduced linearly with increasing amounts of porosity. The resistivity and mechanical property measurements are discussed, with particular attention given to the porosity of the synthetic graphite.

In-situ, time resolved monitoring of uranium in BFS:OPC grout. Part 2: Corrosion in water

To reflect potential conditions in a geological disposal facility, uranium was encapsulated in grout and submersed in de-ionised water for time periods between 2-47 weeks. Synchrotron X-ray Powder Diffraction and X-ray Tomography were used to identify the dominant corrosion products and measure their dimensions. Uranium dioxide was observed as the dominant corrosion product and time dependent thickness measurements were used to calculate oxidation rates. The effectiveness of physical and chemical grout properties to uranium corrosion and mobilisation is discussed and Inductively Coupled Plasma Mass Spectrometry was used to measure ²³⁸U_(aq) content in the residual water of several samples.

An Investigation on the Persistence of Uranium Hydride during Storage of Simulant Nuclear Waste Packages

Synchrotron X-rays have been used to study the oxidation of uranium and uranium hydride when encapsulated in grout and stored in de-ionised water for 10 months. Periodic synchrotron X-ray tomography and X-ray powder diffraction have allowed measurement and identification of the arising corrosion products and the rates of corrosion. The oxidation rates of the uranium metal and uranium hydride were slower than empirically derived rates previously reported for each reactant in an anoxic water system, but without encapsulation in grout. This was attributed to the grout acting as a physical barrier limiting the access of oxidising species to the uranium surface. Uranium hydride was observed to persist throughout the 10 month storage period and industrial consequences of this observed persistence are discussed.

Nuclear waste viewed in a new light; a synchrotron study of uranium encapsulated in grout

How do you characterise the contents of a sealed nuclear waste package without breaking it open? This question is important when the contained corrosion products are potentially reactive with air and radioactive. Synchrotron X-rays have been used to perform micro-scale in-situ observation and characterisation of uranium encapsulated in grout; a simulation for a typical intermediate level waste storage packet. X-ray tomography and X-ray powder diffraction generated both qualitative and quantitative data from a grout-encapsulated uranium sample before, and after, deliberately constrained H2 corrosion. Tomographic reconstructions provided a means of assessing the extent, rates and character of the corrosion reactions by comparing the relative densities between the materials and the volume of reaction products. The oxidation of uranium in grout was found to follow the anoxic U+H2O oxidation regime, and the pore network within the grout was observed to influence the growth of uranium hydride sites across the metal surface. Powder diffraction analysis identified the corrosion products as UO2 and UH3, and permitted measurement of corrosion-induced strain. Together, X-ray tomography and diffraction provide means of accurately determining the types and extent of uranium corrosion occurring, thereby offering a future tool for isolating and studying the reactions occurring in real full-scale waste package systems.