2009
DOI: 10.2172/1019228
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Initial Laboratory-Scale Melter Test Results for Combined Fission Product Waste

Abstract: SUMMARYPacific Northwest National Laboratory (PNNL) and Savannah River National Laboratory performed a joint study to develop acceptable glasses for the combined alkali and alkaline-earth fission products (CS) + lanthanide fission products (LN) + transition metal fission products (TM) waste streams and CS + LN combined waste streams. Glass CSLNTM-C-2.5 was selected as the baseline glass for the CS + LN + TM waste stream as it had the highest MoO 3 -loaded glass that did not crystallize during slow cooling and … Show more

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Cited by 6 publications
(6 citation statements)
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“…The key to obtaining these values is to know the temperature distribution within the cold cap. The laboratory-scale melter (LSM), shown in Figure , was designed to simulate the vitrification process of nuclear waste glass in an electric melter. ,,, Because the LSM produces cold-cap samples suitable for sectioning and analysis, we attempted to determine the cold-cap temperature distribution based on the analysis of one of these samples. Previous work focused on the effect of the charging rate on the cold-cap structure and on comparing the cold-cap features with heat-treated feed samples .…”
Section: Introductionmentioning
confidence: 99%
“…The key to obtaining these values is to know the temperature distribution within the cold cap. The laboratory-scale melter (LSM), shown in Figure , was designed to simulate the vitrification process of nuclear waste glass in an electric melter. ,,, Because the LSM produces cold-cap samples suitable for sectioning and analysis, we attempted to determine the cold-cap temperature distribution based on the analysis of one of these samples. Previous work focused on the effect of the charging rate on the cold-cap structure and on comparing the cold-cap features with heat-treated feed samples .…”
Section: Introductionmentioning
confidence: 99%
“…The concentrations of MoO 3 are predicted to vary from 1.35 to 13.99 mass%, ZrO 2 from 3.04 to 13.75 mass%, and noble metals from 0.96 to 19.60 mass%. With regards to waste loading, two limiting compositions, representing extreme end points, that are expected to result from the separation processes, have been identified [Ryan et al 2009, Riley et al 2009];…”
Section: Re-processed Spent Nuclear Fuelmentioning
confidence: 99%
“…As a result, the waste loading limitations are different for commercial nuclear fuel reprocessing HLWs than those for U.S. defense wastes. Glass formulation for immobilizing HLW from an advanced U.S. fuel recycling plant are reported by Crum et al ., 108 Riley et al ., 109 Ryan et al ., 110 Gombert et al ., 111 and Youchak et al 112 Table III. shows the primary waste‐loading limiting aspects of commercial nuclear fuel recycling of HLW.…”
Section: Glass Formulationsmentioning
confidence: 99%