Solid forms for Savannah River Plant high-level waste

Wallace, R.M.; Hull, H.L.; Bradley, R.F.

doi:10.2172/4326223

Cited by 12 publications

(9 citation statements)

References 3 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…(16,17,19) Glass, in the monolithic form, has been considered as a reference nuclear waste immobilization process and waste form by all sites involved in waste fixation. This includes TRU wastes, (19,20) defense wastes, (21)(22)(23)(24)(25)(26)(27)(28) and commercial wastes. (30)(31)(32) Glass for waste fixation has had over two decades of development and thus is a well established process.…”

Section: Review Of Waste Form Develoment In the United Statesmentioning

confidence: 99%

Review of high-level waste form properties. [146 bibliographies]

Rusín¹

1980

View full text Add to dashboard Cite

This report is a review of waste form options for the immobilization of high-level-liquid wastes from the nuclear fuel cycle. This review covers the status of international research and development on waste formS as of May 1979. Although the emphasis in this report is on waste form properties, process parameters are discussed where they may affect final waste form properties. A summary table is provided listing properties of various nuclear waste form options. It is concluded that proposed waste forms have properties falling within a relatively narrow range. In regard to crystalline versus glass waste forms, the conclusion is that either glass ~crystalline materials can be shown to have some advantage when a single property is considered; however, at this date no single waste form offers optimum properties over the entire range of characteristics investigated. A long-term effort has been applied to the development of glass and calcine waste forms. Several additional waste forms have enough promise to warrant continued research and development to bring their state of development up to that of glass and calcine. Synthetic minerals, the multi barrier approach with coated particles in a metal matrix, and high pressure-high temperature ceramics offer potential advantages and need further study. Although this report discusses waste form properties, the total waste management system should be considered in the final selection of a waste form option. Canister design, canister materials, overpacks, engineered barriers, and repository characteristics, as well as the waste form, affect the overall performance of a waste management system. These parameters were not considered in this comparison.

show abstract

Section: Review Of Waste Form Develoment In the United Statesmentioning

confidence: 99%

Review of high-level waste form properties. [146 bibliographies]

Rusín¹

1980

View full text Add to dashboard Cite

show abstract

“…Most radioactive waste originates in the two separations plants, designated F and H Areas; some waste is produced i~ the reactor areas, laboratories, and peripheral operations. 3 The principal processes in the separations plants have been the Purex a~d the HM processes, but others have been used to process a variety of fuel and target elements. The Pure x process recovers and purifies uranium and plutonium from neutron-irradiated natural uranium; wastes from the Pure x process are found in both F-and H-Area waste tanks.…”

Section: Criteria For Sludgementioning

confidence: 99%

“…2 For long-term storage of SRP waste, a suitable solid waste form is desirable. 3 In one option under investigation, the sludge component 4 would be separated from the supernate, then washed, dried, and incorporated into either concreteS or glass 6 for storage in a retrievable surface storage facility for 100 years or more. 137 CS would be removed from supernate by ion exchange and then sorbed on a zeolite.…”

Section: Introductionmentioning

confidence: 99%

Sampling and analyses of SRP high-level waste sludges

Stone¹,

Kelley²,

McMillan³

1976

View full text Add to dashboard Cite

“…This alkaline waste is made up of three components. The bulk of the waste actinides and fission products is contained in an insoluble sludge of hydroxides and hydrous oxides of iron, aluminum, and manganese [1][2][3].…”

Section: Introductionmentioning

confidence: 99%

Vitrification of High-Level Radioactive Waste in a Small-Scale Joule-Heated Ceramic Melter

Woolsey

Plodinec

1981

MRS Proc.

View full text Add to dashboard Cite

Vitrification is the reference process for the immobilization of radioactive waste from the production of defense materials at the Savannah River Plant (SRP). Since 1979, a small vitrification facility (1 Ib/hr) has been operated at the Savannah River Laboratory using actual SRP waste. In previous studies. dried waste was fed to this smaller melter. This report discusses direct feeding of actual liquid-waste slurries to the small melter. These liquidfeeding tests demonstrated that addition of premelted glass frit to the waste slurry reduces the amount of material volatilized. Results of these tests are in accord with results of large-scale tests with actual waste.

show abstract

Solid forms for Savannah River Plant high-level waste

Cited by 12 publications

References 3 publications

Review of high-level waste form properties. [146 bibliographies]

Review of high-level waste form properties. [146 bibliographies]

Sampling and analyses of SRP high-level waste sludges

Vitrification of High-Level Radioactive Waste in a Small-Scale Joule-Heated Ceramic Melter

Contact Info

Product

Resources

About