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Qualification Of A Radioactive High Aluminum Glass For Processingin The Defense Waste Processing Facility At The Savannah River Site
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Book Synopsis QUALIFICATION OF A RADIOACTIVE HIGH ALUMINUM GLASS FOR PROCESSINGIN THE DEFENSE WASTE PROCESSING FACILITY AT THE SAVANNAH RIVER SITE. by :
Download or read book QUALIFICATION OF A RADIOACTIVE HIGH ALUMINUM GLASS FOR PROCESSINGIN THE DEFENSE WASTE PROCESSING FACILITY AT THE SAVANNAH RIVER SITE. written by and published by . This book was released on 2008 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: At the Savannah River Site (SRS) the Defense Waste Processing Facility (DWPF) has been immobilizing SRS's radioactive high level waste (HLW) sludge into a borosilicate glass for approximately eleven years. Currently the DWPF is immobilizing HLW sludge in Sludge Batch 4 (SB4). Each sludge batch is nominally two million liters of HLW and produces nominally five hundred stainless steel canisters 0.6 meters in diameter and 3 meters tall filled with the borosilicate glass. In SB4 and earlier sludge batches, the Al concentration has always been rather low, (less than 9.5 weight percent based on total dried solids). It is expected that in the future the Al concentrations will increase due to the changing composition of the HLW. Higher Al concentrations could introduce problems because of its known effect on the viscosity of glass melts and increase the possibility of the precipitation of nepheline in the final glass and decrease its durability. In 2006 Savannah River National Laboratory (SRNL) used DWPF processes to immobilize a radioactive HLW slurry containing 14 weight percent Al to ensure that this waste is viable for future DWPF processing. This paper presents results of the characterization of the high Al glass prepared in that demonstration. At SRNL, a sample of the processed high Al HLW slurry was mixed with an appropriate glass frit as performed in the DWPF to make a waste glass containing nominally 30% waste oxides. The glass was prepared by melting the frit and waste remotely at 1150 C. The glass was then characterized by: (1) determining the chemical composition of the glass including the concentrations of several actinide and U-235 fission products; (2) calculating the oxide waste loading of the glass based on the chemical composition and comparing it to that of the target; (3) determining if the glass composition met the DWPF processing constraints such as glass melt viscosity and liquidus temperature along with a waste form affecting constraint that prevents the precipitation of nepheline (NaAlSiO4) crystals in the glass melt; (4) measuring the durability of the glass using the ASTM Standard Product Consistency Test (PCT) leach test to determine if the durability of the glass based on B, Li, and Na releases met the requirements for acceptance in a US geologic repository; (5) measuring the leachability of several radionuclides using the ASTM Standard PCT leach test and comparing them to the B, Li, and Na releases; and (6) examining the glass by scanning electron microscopy and energy dispersive X-ray spectrometry to determine if any crystals had formed in the glass melt. Results indicate that the high Al glass met all the requirements for processing and product quality in the DWPF.
Book Synopsis Analyses of High-level Radioactive Glasses and Sludges at the Savannah River Site by :
Download or read book Analyses of High-level Radioactive Glasses and Sludges at the Savannah River Site written by and published by . This book was released on 1990 with total page 22 pages. Available in PDF, EPUB and Kindle. Book excerpt: Reliable analyses of high level radioactive glass and sludge are necessary for successful operation of the Defense Waste Processing Facility (DWPF) at the Savannah River Site (SRS). This facility will convert the radioactive waste sludges at SRS into durable borosilicate glasses for final disposal in a geologic repository. Analyses that are crucial to DWPF operation and repository acceptance of the glass are measurement of the radioactive and nonradioactive composition of the waste sludges and final glasses and measurement of the Fe(II)/Fe(III) ratio in a vitrified sample of melter feed. These measurements are based on the remote dissolutions of the glass and sludge followed by appropriate chemical analyses. Glasses are dissolved by a peroxide fusion method and a method using HF, HNO3, H3BO3, and HCl acids where the solutions are heated in a microwave oven. The resulting solutions are analyzed by inductively coupled plasma-atomic emission spectroscopy (ICP-AES) and atomic absorption spectroscopy (AAS) for nonradioactive elements and appropriate counting techniques for radioactive elements. Results for two radioactive glasses containing actual radioactive waste are also presented. Sludges are dissolved by the Na2O2 fusion method and an aqua regia method. 8 refs., 4 tabs.
Book Synopsis Performing a Chemical Durability Test on Radioactive High-level Nuclear Waste Glass by :
Download or read book Performing a Chemical Durability Test on Radioactive High-level Nuclear Waste Glass written by and published by . This book was released on 1990 with total page 31 pages. Available in PDF, EPUB and Kindle. Book excerpt: Savannah River Site (SRS), currently is storing (approximately)30 million gallons of highly radioactive nuclear wastes. The Defense Waste Processing Facility (DWPF) nearing completion at SRS will incorporate the radionuclides in these wastes into solid borosilicate glass for final disposal in a geologic repository. Because of the variability of the wastes in the tanks, borosilicate glasses of different compositions will be produced by the DWPF during the 20--25 years required to solidify all the wastes at SRS. A chemical durability test, the Product Consistency Test (PCT), has been developed at SRS to measure the consistency of the durability of these glasses. This paper describes the remote and hands-on procedures for performing the PCT on these radioactive glasses. Results will be presented that indicate the good precision of the PCT and indicate some of the chemistry involved in leaching radioactive elements from the glass. 9 refs., 1 fig., 4 tabs.
Book Synopsis Glass Making Technology for High-Level Nuclear Waste by :
Download or read book Glass Making Technology for High-Level Nuclear Waste written by and published by . This book was released on 1986 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: This paper addresses specific and unique chemical engineering aspects of the Defense Waste Processing Facility (DWPF) at the Savannah River Plant. This paper also addresses the glass melter and those processes that are directly coupled to it. A somewhat disproportionate emphasis is given to sludge pretreatment, for the sake of completeness in this session. We have attempted to focus on those features of the DWPF that may be of general interest or even useful to the practicing chemical engineer.
Book Synopsis CHARACTERIZATION OF RADIOACTIVE MACROBATCH 4 GLASS BEING PRODUCED BY THE DWPF AT SAVANNAH RIVER SITE. by :
Download or read book CHARACTERIZATION OF RADIOACTIVE MACROBATCH 4 GLASS BEING PRODUCED BY THE DWPF AT SAVANNAH RIVER SITE. written by and published by . This book was released on 2006 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: At the Savannah River Site (SRS) the Defense Waste Processing Facility (DWPF) has been immobilizing SRS's radioactive high-level waste (HLW) sludge into a borosilicate glass for approximately nine years. Currently the DWPF is immobilizing HLW sludge in Macrobatch 4 (MB4). Each macrobatch is nominally five hundred thousand gallons of HLW and produces nominally five hundred stainless steel canisters two feet in diameter ten feet tall filled with the borosilicate glass. This paper presents results of the characterization of a sample of MB4 glass taken directly from the pour stream of the DWPF melter during the filling of the canister S02312. This canister was the 275th canister filled during immobilizing MB4. The purpose of the sample was to confirm that the leachability of the glass in a standard ASTM test was less than the leachability criterion set forth in the Waste Acceptance Product Specifications (WAPS) for vitrified waste forms for permanent disposal in a Federal geologic repository. The sample was sent to the Savannah River National Laboratory (SRNL) for characterization.
Book Synopsis Glass as a Waste Form and Vitrification Technology by : National Research Council
Download or read book Glass as a Waste Form and Vitrification Technology written by National Research Council and published by National Academies Press. This book was released on 1997-03-02 with total page 172 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Development of an ASTM Standard Glass Durability Test, the Product Consistency Test (PCT), for High Level Radioactive Waste Glass by :
Download or read book Development of an ASTM Standard Glass Durability Test, the Product Consistency Test (PCT), for High Level Radioactive Waste Glass written by and published by . This book was released on 1994 with total page 8 pages. Available in PDF, EPUB and Kindle. Book excerpt: The nation's first, and the world's largest, facility to immobilize high-level nuclear waste in durable borosilicate glass has started operation at the Savannah River Site (SRS) in Aiken, South Carolina. The product specifications on the glass wasteform produced in the Defense Waste Processing Facility (DWPF) required extensive characterization of the glass product before actual production began and for continued characterization during production. To aid in this characterization, a glass durability (leach) test was needed that was easily reproducible, could be performed remotely on highly radioactive samples, and could yield results rapidly. Several standard leach tests were examined with a variety of test configurations. Using existing tests as a starting point, the DWPF Product Consistency Test (PCT was developed in which crushed glass samples are exposed to 90 " 2°C deionized water for seven days. Based on extensive testing, including a seven-laboratory round robin and confirmatory testing with radioactive samples, the PCT is very reproducible, yields reliable results rapidly, and can be performed in shielded cell facilities with radioactive samples.
Download or read book GLASS SELECTION STRATEGY written by and published by . This book was released on 2007 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: High-level radioactive wastes are stored as liquids in underground storage tanks at the Department of Energy's (DOE) Savannah River Site (SRS) and Hanford Reservation. These wastes are to be prepared for permanent disposition in a geologic repository by vitrification with glass forming additives (e.g., frit), creating a waste form with long-term durability. Wastes at SRS are being vitrified in the Defense Waste Processing Facility (DWPF). Vitrification of the wastes stored at Hanford is planned for the Waste Treatment and Immobilization Plant (WTP) when completed. Some of the wastes at SRS, and particularly those at Hanford, contain high concentrations of aluminum, chromium and sulfate. These elements make it more difficult to produce a waste glass with a high waste loading (WL) without crystallization occurring in the glass (either within the melter or upon cooling of the glass), potentially exceeding the solubility limit of critical components, having negative impacts on durability, and/or resulting in the formation of a sulfate salt layer on the molten glass surface. Although the overall scope of the task is focused on all three critical, chemical components, the current work will primarily address the potential for crystallization (e.g., nepheline and/or spinel) in high level waste (HLW) glasses. Recent work at the Savannah River National Laboratory (SRNL) and by other groups has shown that nepheline (NaAlSiO4), which is likely to crystallize in high-alumina glasses, has a detrimental effect on the durability of the glass. The objective of this task is to develop glass formulations for specific SRS and Hanford waste streams to avoid nepheline formation while meeting waste loading and waste throughput expectations, as well as satisfying critical process and product performance related constraints. Secondary objectives of this task are to assess the sulfate solubility limit for the DWPF composition and spinel settling for the WTP composition. SRNL has partnered with Pacific Northwest National Laboratory (PNNL) and the V.G. Khlopin Radium Institute (KRI) to complete this task.
Book Synopsis Scientific and Technical Aerospace Reports by :
Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1983 with total page 1368 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Durability of Defense Waste Processing Facility Glasses Within the Purex Range of Compositions by :
Download or read book Durability of Defense Waste Processing Facility Glasses Within the Purex Range of Compositions written by and published by . This book was released on 1995 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Incorporation of Savannah River Plant Radioactive Waste Into Glass by :
Download or read book Incorporation of Savannah River Plant Radioactive Waste Into Glass written by and published by . This book was released on 1975 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Effect of Melter Residence Time and Temperature on Defense Waste Processing Facility Glass Durability by :
Download or read book Effect of Melter Residence Time and Temperature on Defense Waste Processing Facility Glass Durability written by and published by . This book was released on 1994 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Glass Composition Development for Plasma Processing of Hanford High Sodium Content Low-level Radioactive Liquid Waste by :
Download or read book Glass Composition Development for Plasma Processing of Hanford High Sodium Content Low-level Radioactive Liquid Waste written by and published by . This book was released on 1995 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Government Reports Announcements & Index by :
Download or read book Government Reports Announcements & Index written by and published by . This book was released on 1983 with total page 694 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Government Reports Annual Index by :
Download or read book Government Reports Annual Index written by and published by . This book was released on 1990 with total page 1120 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Code for Air Raid Shelters, Buildings and Mines by :
Download or read book Code for Air Raid Shelters, Buildings and Mines written by and published by . This book was released on 1942* with total page 7 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis DWPF Vitrification - Characterization of the Radioactive Glass Being Produced During Immobilization of the Second Batch of High Level Waste Sludge by :
Download or read book DWPF Vitrification - Characterization of the Radioactive Glass Being Produced During Immobilization of the Second Batch of High Level Waste Sludge written by and published by . This book was released on 2001 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: This glass sample was then transported to Savannah River Technology Center's (SRTC) Shielded Cells Facility where it was characterized. The characterization includes determining the density of the glass, its nonradioactive and radioactive composition, its durability in a standard ASTM 1285 leach test, and its microstructure. This paper summarizes the results of that characterization. The paper also compares the composition of the glass to that of a glass sample from Macro Batch 1. Lastly the paper also compares the composition of the Macro Batch 2 glass sample to the composition of a sample prepared from the slurry in the MFT when sample was taken from the pour stream. Detailed results of the characterization are presented in three Department of Energy reports that have been released and are available from either author.
