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The uranium-molybdenum (U-Mo) alloy in a monolithic form has been proposed as one fuel design capable of converting some of the world's highest power research reactors from the use of high enriched uranium to low enriched uranium. One aspect of the fuel development and qualification process is to demonstrate appropriate understanding of the thermal-conductivity behavior of the fuel system as a function of temperature and expected irradiation conditions. The purpose of this paper is to verify functionality of equipment installed in hot cells for eventual measurements on irradiated uranium-molybdenum (U-Mo) monolithic fuel specimens, refine procedures to operate the equipment, and validate models to extract the desired thermal properties. The results presented here demonstrate the adequacy of the equipment, procedures, and models that have been developed for this purpose based on measurements conducted on surrogate depleted uranium-molybdenum (DU-Mo) alloy samples containing a Zr diffusion barrier and clad in aluminum alloy 6061 (AA6061). The results are in excellent agreement with thermal property data reported in the literature for similar U-Mo alloys as a function of temperature.

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Total Alpha Analysis (AT) AT Worklist # 30095 (973, 974, 975) . This document consists o f pages 1 to 479. Pages i i , 2, 15, 20, 25, 28, 33, 39, 40, 42, 46, 51, 54, 281 (Fowler 1995, Mulkey and Miller 1998). The analytical results are presented in the data summary report (Table 1).None of the subsamples submitted for differential scanning calorimetry (DSC), total organic carbon (TOC) and plutonium 239 (Pu239) analyses exceeded the notification limits as stated in TSAP (Sasaki, 1999). Aapearance and Sample HandlingThe sample breakdown diagrams (Attachment 1) are provided as a cross-reference for relating the tank farm customer identification numbers with the 222-S Laboratory sample numbers and the portion of sample analyzed. Table 2 provides the appearance information. 2U-99-1This sample was collected at a depth of 343 inches. Visual observation indicated that the sample was an opaque yellow liquid with approximately eight-percent fine brown solids. No organic layer was observed.There was insufficient solid material to submit to the laboratory for analyses. Two IO-gram liquid samples were submitted to the laboratory for analysis of inorganic analytes and radionuclides. 2U-99-2This sample was collected at a depth of 410 inches. Visual observation indicated that the sample was an opaque yellow liquid with approximately nine-percent fine brown solids. No organic layer was observed. 2U-99-5This sample was collected at a depth of 470 inches. Visual observation indicated that the sample was an opaque yellow liquid with sixty-percent fine brown and gray-white crystalline solids. No organic layer was observed.The solids were allowed to settle and the liquid portion of the sample was decanted. One 1 0-gram solid sample and two 1 0-gram liquid samples were submitted to the laboratory for analysis of inorganic analytes and radionuclides. Analvtical Results SummaryThe data summary report (Table 1) included in this report compiles the analytical results that comply with the applicable DQO. Differential Scanning Calorimetry (DSC)The DSC analysis was performed in duplicate on direct subsamples. The exothermic energy based on the dry weight of the subsample was calculated for all subsamples. The average of the TGA results for each subsample was used in the dry weight correction for that subsample. More information may be obtained by examining the raw data.The standard recoveries were within the required limits of 80% -120% and Relative Percent Differences (RPDs) were below 20%. TGA -Thermogravimetric AnalysisThe TGA analysis was performed in duplicate on direct subsamples. Typically the TGA results are determined by summing the weight loss steps which occur below 200°C. However, for tank 241-U-102 Grab Samples 100% of the thermograms showed weight loss beyond 200°C. The results for all subsamples were the sum of two weight loss steps. More information may be obtained by examining the raw data.The standard recoveries were within the required limits of 80% -120% and the RPDs were less than 20%. Bulk DensityBulk density ...

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