Cementitious Radioactive Waste Hosts Formed Under Elevated Temperatures and Pressures (Fuetap Concretes)

Dole, L.R.; Moore, Johnathan; Rogers, G.C.; West, G.A.; Devaney, H. E.; Morgan, M.T.; McDaniel, E. W.; Kessler, John H.

doi:10.1557/proc-6-585

Cited by 9 publications

(3 citation statements)

References 7 publications

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“…Associates 1980; Bernadzikowski et al 1987;Stone et al 1979;Lutze and Ewing 1988;and Dole et al 1983).…”

Section: -15mentioning

confidence: 99%

High-Level Waste Melter Study Report

Perez¹,

Bickford²,

Day³

et al. 2001

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At the Hanford Site in Richland, Washington, the path to site cleanup involves vitrification of the majority of the wastes that currently reside in large underground tanks. A Joule-heated glass melter is the equipment of choice for vitrifying the high-level fraction of these wastes. Even though this technology has general national and international acceptance, opportunities may exist to improve or change the technology to reduce the enormous cost of accomplishing the mission of site cleanup. Consequently, the U.S. Department of Energy requested the staff of the Tanks Focus Area to review immobilization technologies, waste forms, and modifications to requirements for solidification of the high-level waste fraction at Hanford to determine what aspects could affect cost reductions with reasonable long-term risk. The results of this study are summarized in this report.

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“…Associates 1980; Bernadzikowski et al 1987;Stone et al 1979;Lutze and Ewing 1988;and Dole et al 1983).…”

Section: -15mentioning

confidence: 99%

High-Level Waste Melter Study Report

Perez¹,

Bickford²,

Day³

et al. 2001

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“…in 1996 is a combination of the "Clay Reaction Process" attributed to Hanford's workers and the "FUETAP" technology that originated at the Oak Ridge National Laboratory (ORNL), Tennessee [6]. FUETAP grouts themselves had shown better results on the MCC-1 test when they were mixed with Indian red pottery clay or bentonite than when they were leached without clay additions [17].…”

Section: Hydroceramics As An Innovative Waste Formmentioning

confidence: 99%

Physical, Chemical and Structural Evolution of Zeolite-Containing Waste Forms Produced From Metakaolinite and Calcined HLW

Grutzeck¹,

Kwan²

2001

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Calcine 1) 20 g raw waste liquid (control sample) Calcine 2) 20 g raw waste liquid + 2.5 g sucrose (control sample) Calcine 3) 20 g raw waste liquid + 2.5 g sucrose + 11.9 g boehmite Calcine 4) 20 g raw waste liquid + 2.5 g sucrose + 11.9 g 5µm SiO 2 (MIN-U-SIL) Calcine 5) 20 g raw waste liquid + 2.5 g sucrose + 11.9 g metakaolinite Calcine 6) 20 g raw waste liquid + 2.2 g aluminum powder Calcine 1 and 2 were made from the liquid simulants. Enough solid material was added to Calcines 3-5 to convert the liquid SBW into thick pastes. Calcine 6 was tested because it offered an alternate to thermal calcination. Simulants 1 and 2 contained ~7 mol/L of sodium hydroxide (NaOH). If finely divided aluminum metal is added to a highly caustic solution at room temperature (no sucrose, no additives) the nitrates/nitrites present can be reduced producing ammonia gas. The additional aluminum content of the waste is actually beneficial since aluminum ion is needed to produce zeolites and SBW normally does not contain much aluminum. Calcines 1 through 5 were dried at 90°C for 24 hours (to remove most of the water) and then calcined at 525°C for 18 hours. The addition of alumina and/or silica to Calcines 3-5 gave the sodium oxide something other than CO 2 to react with; rudimentary aluminosilicate phases tended to form instead of Na 2 CO 3. In addition, Calcine 6 was "cold de-nitrated" by adding aluminum powder to the caustic rich solution containing nitrate/nitrite salts. After the reaction was complete, Calcine 6 was dried at 90°C for 24 hours. Each of the 6 calcines for both simulants was ground to pass a 150-micron sieve. The portion retained on 74-micron sieve was used for the conductivity test. One gram of each calcine was placed in 10 ml DI water at 90°C for 24 hours. Sodium is normally the most mobile element;

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“…• FUETAP Cement. Cement formed Qnder ~levated !emperature ~nd Qressure has been under development at ORNL for a number of years (Dole et al 1982). The FUETAP • Borosilicate Glass.…”

Section: Waste-form System Selection Criteria and Assumptions For Thementioning

confidence: 99%

Comparative assessment of TRU waste forms and processes. Volume I. Waste form and process evaluations

Ross¹,

Lokken²,

May³

et al. 1982

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Cementitious Radioactive Waste Hosts Formed Under Elevated Temperatures and Pressures (Fuetap Concretes)

Cited by 9 publications

References 7 publications

High-Level Waste Melter Study Report

High-Level Waste Melter Study Report

Physical, Chemical and Structural Evolution of Zeolite-Containing Waste Forms Produced From Metakaolinite and Calcined HLW

Comparative assessment of TRU waste forms and processes. Volume I. Waste form and process evaluations

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