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The corrosion behavior of a borosilicate glass containing 20 mass 5 Na{sub 2}O was assessed using static dissolution tests. This glass (LD6-5412) is representative of high Na glasses that may be used to stabilize Hanford low-level radioactive waste. The normalized mass loss (NL) decreases as NL(Na) {approximately} NL(B) > NL(Si) in 20 and 40 C for tests conducted at glass surface area to leachant volume (S/V) ratio of 10 m{sup {minus}1}, and decreases as NL(Na) > NL(B) {approximately} NL(Si) in 90 C tests conducted at 10 m{sup {minus}1} and in all tests conducted at higher S/V. The difference in the corrosion behavior is probably caused by the influence of dissolved glass components in the leachates. The NL(Na) is greater than the NL(B) or NL(Si) in all the tests conducted. Results from long-term tests at 2,000 m{sup {minus}1} show that the preferential release of Na persists for longer than one year at all temperatures and indicate that Na is released from this glass by an ion exchange process

Glass dissolution at 20, 40, 70 and 90 C: Short-term effects of solution chemistry and long-term Na release