Waste simulated radioactive

Method for Determining Leach Rates of Simulated Radioactive Waste Forms... 

Extraction of neptunium, plutonium, and americium from simulated radioactive liquid waste was carried out in particular with tert-butyl and dealkylated tetramers, hexamers, and octamers of calixarene [ethoxy(diphenylphosphine oxide)]. Among these six calixarenes, the highest distribution ratios were obtained with the dealkylated calix[8]arene. Using a different sample of the dealkylated hexamer, the Strasbourg group concluded that this compound is the most efficient. This discrepancy can be explained by the presence of impurities, detected by NMR, which were probably responsible for the poor performances of the dealkylated hexamer tested at Cadarache. 

The stabihzation of a range of contaminants, including Cr , in Ceramicrete was demonstrated by Wagh et al. [60] with two liquid waste streams that simulated radioactive supernatant and sludge from Hanford tanks within the DOE complex. These waste streams... 

ION EXCHANGE CHARACTERISTICS OF PALLADIUM FROM A SIMULATED RADIOACTIVE LIQUID WASTE... 

Stefanovsky, S. V. Dmitriev, S. A. 1995. EPR of radiation centers in ion-implanted glasses simulating vitrified radioative wastes. In Slate, S., Feizollahi, F. Creer, J. (eds) Proceedings of the Fifth International Conference on Radioactive Waste Management and Environmental Remediation. ASME, New York, 1, 409-411. 

Clark, W. E. Godbee, H. W. 1963. Fixation of simulated highly radioactive wastes in glassy solids. In Treatment and Storage of High Level Radioactive Wastes. IAEA, Vienna, 412-432. 

Werme, L. B., Bjorner, I. K., et al. 1990. Chemical cotrosion of highly radioactive borosilicate nuclear waste glass under simulated repository conditions. Journal of Materials Research, 5, 1130-1146. 

The leach rates seen here can be compared to those from a similar test on simulated waste glass of the same composition. The leach rates for cesium and strontium from the fully radioactive Rlass were the same as the leach rates of the simulated glass. Although both tests were done on bulk glass samples, they differed in configuration. The fully radioactive samples were disks cm (height) x 3.5 cm (diameter)], and the... 

The release rate was determined for 10 radioisotopes from fully radioactive waste glasses in deionized water for a period of 1.75 years. For cesium and strontium, good agreement exists between the leach rates for simulated and fully radioactive glass of the same composition. 

Table II. Composition of Simulated High Level Radioactive Waste Revision of Bonner s Data(13)...

This assessment included results of leach tests with glass contain ing either actual(2,3) or simulated(4) radioactive waste in leachants that simulated groundwaters of possible geologic repositories salt, basalt, tuff, and granite. In support of the environmental... 

The data presented in this paper support the following conclusions concerning the performance of SRP radioactive nuclear waste glass in deionized water and in two simulated groundwaters. 

Leach behavior of borosilicate glass containing actual radioactive SRP high-level waste is similar to glass containing nonradio<-active simulated waste. 

The tren-based heteroditopic receptor 22, featuring a tripodal tetrahedral amide hydrogen-bond anion-recognition site in combination with benzo-15-crown-5 ether cation-binding moieties, has been found to cooperatively bind chloride, iodide, and perrhenate anions via co-bound crown ether-complexed sodium cations. It also can efficiently extract the radioactive sodium pertechnetate from simulated aqueous nuclear waste streams. The anion-binding affinity of 22 is considerably reduced in the absence of a co-bound cation <1999CC1253>... 

Table 16.5 lists the surrogate (simulated) waste streams that were part of this study. The ash stream represents radioactive waste from the inventory of US Department of Energy (DOE) facilities. The Delphi DETOX streams are secondary waste generated during destruction of organics from similar waste streams [57]. The soil represents the waste from Argonne National Laboratory s inventory that was included in a site treatment plan for actual treatment. 

Leaching of contaminants Eission products Tc, partitioned from high-level waste tanks, debris from contaminated pipes from K-25 plant at Oak Ridge Cs, from salt supernatant and sludge, silico-titanates, and wastewater Radioactive components Ra, Fernald silo waste, transuranics, simulated and actual Rocky Flats ash waste, wastewater... 

In contrast to the two studies mentioned above, the work at ANL has been mainly in demonstrating treatment of a range of radioactive waste streams (both simulated and actual) from the US DOE complex in the Ceramicrete matrix. The reader is referred to Ref. [21] and additional references therein. In this section, we provide an overview in the form of case studies. Table 17.5 lists acceptance criteria and the corresponding case studies selected to demonstrate compliance by the Ceramicrete waste forms with those criteria. 

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