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

Technical Report · Thu Aug 01 04:00:00 EDT 1996

DOI:https://doi.org/10.2172/270682· OSTI ID:270682

Bakel, A J; Ebert, W L; Strachan, D M ^[1]; Brown, N R ^[2]

---

1. Argonne National Lab., IL (United States). Chemical Technology Div.
2. Dept. of Energy Operations Office, Richland, WA (United States)

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.

• Research Organization: Argonne National Lab., IL (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: W-31109-ENG-38; AC06-76RL01830
• OSTI ID: 270682
• Report Number(s): ANL/CMT/CP--88362; CONF-9604124--13; ON: DE96012808
• Country of Publication: United States
• Language: English

Related Subjects

05 NUCLEAR FUELS
36 MATERIALS SCIENCE
BORON
BOROSILICATE GLASS
DISSOLUTION
EXPERIMENTAL DATA
HANFORD RESERVATION
HYDROLYSIS
ION EXCHANGE
LEACHATES
LOW-LEVEL RADIOACTIVE WASTES
SILICON
SODIUM
SODIUM OXIDES
VITRIFICATION
WASTE FORMS