Characterization of projected DWPF glasses heat treated to simulate canister centerline cooling [electronic resource]
Liquid high-level nuclear waste will be immobilized at the Savannah River Site (SRS) by vitrification in borosilicate glass. The glass will be produced and poured into stainless steel canisters in the Defense Waste Processing Facility (DWPF). Eventually these canistered waste forms will be sent to a...
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Online Access |
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| Corporate Author: | |
| Format: | Government Document Electronic eBook |
| Language: | English |
| Published: |
Washington, D.C. : Oak Ridge, Tenn. :
United States. Department of Energy ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,
1992.
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| Subjects: |
MARC
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| 245 | 0 | 0 | |a Characterization of projected DWPF glasses heat treated to simulate canister centerline cooling |h [electronic resource] |
| 260 | |a Washington, D.C. : |b United States. Department of Energy ; |a Oak Ridge, Tenn. : |b distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, |c 1992. | ||
| 300 | |a Pages: (38 p) : |b digital, PDF file. | ||
| 336 | |a text |b txt |2 rdacontent. | ||
| 337 | |a computer |b c |2 rdamedia. | ||
| 338 | |a online resource |b cr |2 rdacarrier. | ||
| 500 | |a Published through SciTech Connect. | ||
| 500 | |a 05/01/1992. | ||
| 500 | |a "wsrc-tr-92-142" | ||
| 500 | |a "DE93003325" | ||
| 500 | |a Jantzen, C.M.; Marra, S.L. | ||
| 520 | 3 | |a Liquid high-level nuclear waste will be immobilized at the Savannah River Site (SRS) by vitrification in borosilicate glass. The glass will be produced and poured into stainless steel canisters in the Defense Waste Processing Facility (DWPF). Eventually these canistered waste forms will be sent to a geologic repository for final disposal. In order to assure acceptability by the repository, the Department of Energy has defined requirements which DWPF canistered waste forms must meet. These requirements are the Waste Acceptance Preliminary Specifications (WAPS). The WAPS require DWPF to identify the crystalline phases expected to be present in the final glass product. Knowledge of the thermal history of the borosilicate glass during filling and cooldown of the canister is necessary to determine the amount and type of crystalline phases present in the final glass product. Glass samples of seven projected DWPF compositions were cooled following the same temperature profile as that of glass at the centerline of the full-scale DWPF canister. The glasses were characterized by x-ray diffraction and scanning electron microscopy to identify the crystalline phases present The volume percents of each crystalline phase present were determined by quantitative x-ray diffraction. The Product Consistency Test (PCI) was used to determine the durability of the heat-treated glasses. | |
| 536 | |b AC09-89SR18035. | ||
| 650 | 7 | |a Borosilicate Glass. |2 local. | |
| 650 | 7 | |a Evaluation. |2 local. | |
| 650 | 7 | |a Underground Disposal. |2 local. | |
| 650 | 7 | |a Vitrification. |2 local. | |
| 650 | 7 | |a Waste Forms. |2 local. | |
| 650 | 7 | |a Specifications. |2 local. | |
| 650 | 7 | |a Containers. |2 local. | |
| 650 | 7 | |a Cooling. |2 local. | |
| 650 | 7 | |a Leaching. |2 local. | |
| 650 | 7 | |a Phase Studies. |2 local. | |
| 650 | 7 | |a Quality Assurance. |2 local. | |
| 650 | 7 | |a Savannah River Plant. |2 local. | |
| 650 | 7 | |a Scanning Electron Microscopy. |2 local. | |
| 650 | 7 | |a Coherent Scattering. |2 local. | |
| 650 | 7 | |a Diffraction. |2 local. | |
| 650 | 7 | |a Dissolution. |2 local. | |
| 650 | 7 | |a Electron Microscopy. |2 local. | |
| 650 | 7 | |a Glass. |2 local. | |
| 650 | 7 | |a Management. |2 local. | |
| 650 | 7 | |a Materials. |2 local. | |
| 650 | 7 | |a Microscopy. |2 local. | |
| 650 | 7 | |a National Organizations. |2 local. | |
| 650 | 7 | |a Radioactive Materials. |2 local. | |
| 650 | 7 | |a Radioactive Wastes. |2 local. | |
| 650 | 7 | |a High-Level Radioactive Wastes. |2 local. | |
| 650 | 7 | |a Scattering. |2 local. | |
| 650 | 7 | |a Separation Processes. |2 local. | |
| 650 | 7 | |a Us Aec. |2 local. | |
| 650 | 7 | |a Us Doe. |2 local. | |
| 650 | 7 | |a Us Organizations. |2 local. | |
| 650 | 7 | |a X-Ray Diffraction. |2 local. | |
| 650 | 7 | |a Waste Disposal. |2 local. | |
| 650 | 7 | |a Waste Management. |2 local. | |
| 650 | 7 | |a Us Erda. |2 local. | |
| 650 | 7 | |a Wastes. |2 local. | |
| 650 | 7 | |a Management Of Radioactive And Non-Radioactive Wastes From Nuclear Facilities. |2 edbsc. | |
| 710 | 2 | |a Westinghouse Savannah River Company. |4 res. | |
| 710 | 1 | |a United States. |b Department of Energy. |4 spn. | |
| 710 | 1 | |a United States. |b Department of Energy. |b Office of Scientific and Technical Information. |4 dst. | |
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