Parametric testing of a DWPF glass

Bazan, F.; Rêgo, João Henrique da Silva

doi:10.2172/59362

Cited by 6 publications

(8 citation statements)

References 3 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…When these values are plotted as a function of time as shown in Figure 6, the trend is that of initial rapid release followed by slower release. This trend has been observed previously in static leach testing (e.g., Bazan & Rego, 1985). The boron and molybdenum data behave very much like the technetium data.…”

Section: Neptuniumsupporting

confidence: 86%

“…This report will describe the experimental conditions and discuss the results obtained. Similar tests have been conducted (Bazan andRego, 1985, andBibler et al, 1984) using both radioactive and non-radioactive glass, and the results suggest that the tuff and J-13 ground water environment is less corrosive towards glass than J-13 or deionized water alone. Our results corroborate that information in more detail, particularly with respect to boron, molybdenum, and technetium.…”

Section: Introductionsupporting

confidence: 53%

See 1 more Smart Citation

Tuff reaction vessel experiment

Bazan¹,

Rêgo²

1986

Self Cite

View full text Add to dashboard Cite

show abstract

Section: Neptuniumsupporting

confidence: 86%

Section: Introductionsupporting

confidence: 53%

Tuff reaction vessel experiment

Bazan¹,

Rêgo²

1986

Self Cite

View full text Add to dashboard Cite

show abstract

“…Tests were conducted in deionized water at 90'C for times up to 28 days using SRP black frit waste glass. Monolithic samples were tested at SAN ratios of 10 and 100 n-1 , and crushed samples of the -40+60 mesh [195]) 84 size fraction were tested at SAN ratios of 100 and 1000 m-1 . Figure 32 shows the boron concentration plotted against the product (SA/V)t for these test data.…”

Section: Effects Of Sa/v On the Solution Chemistrymentioning

confidence: 99%

“…These tests were conducted for a maximum of (SA/V)t = 2800 d/m, and are not relevant to the use of the SA/V to attain saturated solution conditions. Static leach tests were conducted using monolithic and crushed SRL 165 glass at 90*C [195]. Tests with monolithic samples were conducted at SAN of 10, 30, and 50 m-1 , and tests with crushed glass (-40+80 mesh) were conducted at SAN of 30, 50, and 100 m-1 .…”

mentioning

confidence: 99%

The effects of the glass surface area/solution volume ratio on glass corrosion: A critical review

Ebert

1995

View full text Add to dashboard Cite

Argonne National Lahoratory. wi1th facilitie, in the states of liiinois and Idaho. is owned by the united States govern lent, and operated by The Un diversity of Chicago under the provisions of a contract with thie department of Enery. DISCLAIM ER THE FFFECTS OF THE GLASS SURFACE AREA/SOLUTION VOLUME RATIO ON GLASS CORROSION: A CRITICAL REVIEW William L. Ebert ABSTRACTThis report reviews and summarizes the present state of knowledge regarding the effects of the glass surface area/solution volume (SA/V) ratio on the corrosion behavior of borosilicate waste glasses. The SA/V ratio affects the rate of glass corrosion through the extent of dilution ok corrosion products released from the glass into the leachate solution: glass corrosion products are diluted more in tests conducted at low SA/V ratios than they are in tests conducted at high SAN ratios. Differences in the solution chemistries generated in tests conducted at different SA/V ratios then affect the observed glass corrosion behavior. Corrosion of borosilicate waste glasses results in the dissolution of soluble components and the accumulation of sparingly soluble components in a layer on the surface of the corroding glass. Laboratory tests performed to distinguish the effects of the solution chemistry and the surface layer on the glass corrosion rate have shown the rate to be controlled primarily by the solution chemistry. Therefore, any testing parameter that affects the solution chemistry will also affect the glass corrosion rate. The results of static leach tests conducted to assess the effects of the SAN are discussed with regard to the effects of SAN on the solution chemistry. The effects of the SA/V ratio observed in static tests can be understood based on the effects of the solution chemistry on glass corrosion behavior. Test results show several remaining issues with regard to the long-term glass corrosion behavior: Can the SAN ratio be used as an accelerating parameter to characterize the advanced stages of glass corrosion relevant to long disposal times? Is the alteration of the glass surface the same in tests conducted at different SAN, and in tests conducted with monolithic and crushed glass samples? What are the effects of the SAN and the extent of glass corrosion on the disposition of released radionuclides? These issues will bear on the prediction of the long-term performance of waste glasses during storage. The results of an experimental program conducted at ANL to address these and other remaining issues regarding the effects of SA/V on glass corrosion are described. I 2 SUMMARYThis report reviews and summarizes the present state of knowledge regarding the effects of the glass surface area/solution volume ratio (SA/V) on the corrosion behavior of borosilicate waste glasses. The effects of the SA/ occur through dilution of corrosion products and through the effects of the corrosion products on the glass corrosion mechanism and rate. Therefore, the effects of the SA/V on glass corrosion are discussed in terms of the various effects of t...

show abstract

“…Figure 3 Indicates that errors of ±20X In the H2O/OH ratio are to be expected. [15]. Only hydroxyl 1s detectable In these samples.…”

Section: Methodsmentioning

confidence: 71%

Hydrogen Speciation in Hydrated Layers on Nuclear Waste Glass

1986

View full text Add to dashboard Cite

DE87 005836The hydration of an outer layer on nuclear waste glasses Is known to occur during leaching, but the actual speclatlon of hydrogen (as water or hydroxyl groups) in these layers has not been determined. As part of the Nevada Nuclear Waste Storage Investigations Project, we have used infrared spectroscopy to determine hydrogen spedatlons n three nuclear waste glass compositions (SRL-131 & 165, and PNL 76-6 1, which were leached at 90'C (all glasses) or hydrated In a vapor-satu ated atmosphere at 202*C (SRL-131 only). Hydroxyl groups were found in the surface layers of all the glasses. In addition, molecular wat~>r was found in the surface of SRL-131 and PNL 76-68 glasses that had i.een leached for several months 1n deionlzed water, and 1n the vapor-hydrated sample. The water/hydroxyl ratio Increases with increasing reaction time; molecular water makes up most of the hydrogen In the thick reaction layers on vapor-phase hydrated glass while only hydroxyl occurs In the least reacted samples. Using the known molar absorptlvltle; of water and hydroxyl 1n silica-rich glass the vapor-phase layer contained 4.8 moles/liter of molecular water, and 0.6 moles water in the forr hydroxyl. A 15 micrometer layer on SRL-131 glass formed by leachln at 90°C contained a total of 4.9 moles/liter of water, 2/3 of which wa: as hydroxyl. The unreacted bulk glass contains about 0.018 moles/liter water, all as hydroxyl.The amount of hydrogen added to the SRL-131 glass was about 70% of the original Na + Li content, not the 300% that would result from alkali-hydronium 1on (HgO-1 -) interdiffusion. If all the hydrogen Is then assumed to be added as the result of alkali-H + Interdiffusion, the molecular water observed nay have formed from condensation of the original hydroxyl groups according to: 20H -H2O molecular + 0°where 0° refers to a bridging oxygen, and OH refers to a hydroxyl group attached to a silicate polymer. The hydrated layer on the nuclear waste glasses appears to be of relatively low water content (4 to 7% by weight) and Is not substantially hydroxylated. Thus, these layers do not have many of the properties associated with "gel" layers.

show abstract

Parametric testing of a DWPF glass

Cited by 6 publications

References 3 publications

Tuff reaction vessel experiment

Tuff reaction vessel experiment

The effects of the glass surface area/solution volume ratio on glass corrosion: A critical review

Hydrogen Speciation in Hydrated Layers on Nuclear Waste Glass

Contact Info

Product

Resources

About