1999
DOI: 10.1557/proc-608-426
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Characterization of a Glass-Bonded Ceramic Waste Form Loaded With U and Pu

Abstract: Abstract-The TEAM Workshops originated from probknss in fusion reaeareh. Based on his recent observations regarding automotive modeling, the author asks whether TEAM-i&e worksho~and the accompanying cooperation among model= are of vahse in areas of economic competition. I. cO&@ETtTtON AND~PSRATIONIn her study of advanced automotive government-industry cooperative programs, Melissa Polverini [1] compared the Advanced Clean Energy Project in Japan, the Car of Tomorrow in Europe, and the Partnership for a New Gen… Show more

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Cited by 20 publications
(25 citation statements)
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“…Small inclusions of oxides (uranium, plutonium, and some rare earths) and halite (NaCl) are encapsulated by glass in the CWF near glass-sodalite phase boundaries. The uranium and plutonium oxides have been identified as clusters of (U,Pu)O 2 particles of colloidal size (20-50 nm) [2]. A transmission electron micrograph of these particles in CWF is shown in figure 1 (left).…”
Section: Introductionmentioning
confidence: 99%
“…Small inclusions of oxides (uranium, plutonium, and some rare earths) and halite (NaCl) are encapsulated by glass in the CWF near glass-sodalite phase boundaries. The uranium and plutonium oxides have been identified as clusters of (U,Pu)O 2 particles of colloidal size (20-50 nm) [2]. A transmission electron micrograph of these particles in CWF is shown in figure 1 (left).…”
Section: Introductionmentioning
confidence: 99%
“…In the FBSR final waste form the radionuclide release (Cs and Re) is retarded preferentially to the matrix element, Na, release (Table V) or conversely, Na is released from one of the phases preferentially compared to the nosean phase which retains the Re. This finding is noteworthy because the Hanford specification for Na release for vitrified waste forms is an indicator for the congruent release of Tc 99 since Na and B and Tc 99 are all released at similar stoichiometric rates (congruently) from vitrified waste forms [10,11,15,16,17,18,19,20,21,22,23,24].…”
Section: Durability Testing Of the Fbsr Mineral Productmentioning
confidence: 84%
“…In addition, sodalite structures are known to retain B [8], Ge [9], I [9,6], and Br [9,6] in the cage like structures. Indeed, waste stabilization at Argonne National LaboratoryWest (ANL-W) currently uses a glass-bonded sodalite ceramic waste form (CWF) for disposal of electrorefiner wastes for sodium-bonded metallic spent nuclear fuel from the EBR II fast breeder reactor [10,11].…”
Section: X-ray Diffraction Analysis Of the Fbsr Mineral Productmentioning
confidence: 99%
“…In addition, sodalite structures are known to retain B [11,12] and Ge [13] in the cage like structures. Waste stabilization at the Materials and Fuels Complex (MFC) operated by Battelle Energy Alliance at Idaho National Laboratory (INL) currently uses a glass-bonded sodalite ceramic waste form (CWF) for containment of I from electrorefiner wastes from the Experimental Breeder Reactor (EBR) II fast breeder reactor [14,15]. Researchers' at Hanford had also researched and patented a process for stabilizing alkali metal iodides or aqueous solutions into alkali sodalites for applications at Hanford.…”
Section: Mineral Waste Formsmentioning
confidence: 99%