The objective of this study is to determine the technical feasibility of processing transuranic tank waste in a high-level waste vitrification facility. This is achieved by performing an impact assessment of a reference case high-level waste facility modified to separately process transuranic waste. Data are presented for

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A study was performed to assess radionuclide leak-detection systems for use in locating a capsule leaking strontium-gO or cesium-137 into a waterfilled pool. Each storage pool contains about 35,000 L of water and up to 715 capsules, each of which contains up to 150 kCi strontium-gO or 80 kCi cesium-137. Potential systems assessed included instrumental chemical analyses, radionuclide detection, visual examination, and other nondestructive nuclearfuel examination techniques. Factors considered in the assessment include: cost, simplicity of maintenance and operation, technology availability, reliability, remote operation, sensitivity, and ability to locate an individual leaking capsule in its storage location. The study concluded that an adaption of the spent nuclear-fuel examination technique of wet sipping be considered for adapt ion. In the suggested approach, samples would be taken continuously from pool water adjacent to the capsule(s) being examined for remote radiation detection. In-place capsule isolation and subsequent water sampling would confirm that a capsule was leaking radionuclides. Additional studies are needed before implementing this option. Two other techniques that show promise are ultrasonic testing and eddy-current testing. v Two other promising concepts for individual capsule inspection were identified: ultrasonic inspection and eddy-current testing. viii