Drip tests to measure radionuclide release from spent nuclear fuel are being performed at 90 °C at a drip rate of 0.75 ml every 3.5 days. The test conditions are designed to simulate the behavior of spent fuel under the unsaturated and oxidizing conditions expected in a potential repository at Yucca Mountain. The 238 U, 239 Pu, ,17 Cs, w Sr, "Tc, and l29 I content in the leachate after 581 days of testing is reported. These data provide valuable information for estimating the release of long-lived radionuclides. A comparison is made between our results and those of other researchers. The "Te release fractions are suggested to be representative of matrix dissolution.
We describe a method that can be used to analyze chemical process flowsheets for waste minimization options for hazardous waste. The system is based on relating current waste minimization solutions to the waste generating unit operation. The system is simple and emphasizes EPA pollution prevention priorities. The system database contains numerous waste minimization solutions compiled from case studies, EPA 380 SLATER, KHAN, AND SMITH reports, consultant reports and options identified during waste minimization visits. The database structure and the system which uses the database to analyze chemical process flow is described for two existing companies, a specialty chemical company and a plating company. A pollution prevention index (PPI) that emphasizes EPA pollution prevention priorities as well as economic and technical factors is proposed and is used by the system to rank solutions for a given process flowsheet. Analyses for the specific plating and specialty chemical companies examined are described in detail. It is shown that the new system and structure are effective in locating and providing an analysis of a chemical process flowsheet. The system has been applied to more than 16 South Carolina industries.
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