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Leach tests at Savannah River Laboratory for radioactive and nonradioactive nuclear waste glasses

Conference ·
OSTI ID:6348614
The high-level nuclear wastes currently stored at Savannah River Plant as caustic slurries will be immobilized into borosilicate glass. To characterize the glass resulting from this vitrification process, the Savannah River Laboratory (SRL) has developed and performed a variety of leach tests on both radioactive glass containing actual nuclear waste and nonradioactive glass containing simulated waste. These leach tests range from simple tests using monolithic samples in deionized water to complex tests using radioactive glass and performed remotely. Some of the tests were designed to determine the effects of factors such as radiation or groundwater oxidation potential (Eh) on the leaching process. Other tests were designed to obtain a measure of how the waste glass will respond in geologic environments. This paper describes the rationale used in the development of these tests and presents a brief survey of the tests including some of their special procedures and pertinent results. 12 refs.
Research Organization:
Westinghouse Savannah River Co., Aiken, SC (USA)
DOE Contract Number:
AC09-76SR00001
OSTI ID:
6348614
Report Number(s):
DP-MS-88-233; CONF-890401-9; ON: DE89010753
Country of Publication:
United States
Language:
English

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