The Technische Universität München (TUM) located in Germany requested that Pacific Northwest National Laboratory (PNNL) perform thermal-physical property measurement services for determining the thermal conductivities of irradiated U-Mo dispersion fuel samples. Two dispersion fuel segments containing U-7Mo dispersion fuel in an Al-2wt% Si matrix harvested from the AFIP-1 irradiation experiment were provided to PNNL for this effort. The segments were sectioned into samples for pycnometry (density) and laser flash analysis (thermal diffusivity), differential scanning calorimetry (specific heat capacity), and optical metallography (thickness, image analysis). This report summarizes the findings of the analysis performed at TUM’s request.
Revised: June 11, 2018 |
Published: September 15, 2014