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Characterization Of Radioactive Macrobatch 4 Glass Being Produced By The Dwpf At Savannah River Site
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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 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.
Book Synopsis Characterization of Borosilicate Glass Containing Savannah River Plant Radioactive Waste by : Ned E. Bibler
Download or read book Characterization of Borosilicate Glass Containing Savannah River Plant Radioactive Waste written by Ned E. Bibler and published by . This book was released on 1983* with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
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 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 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 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.
Book Synopsis Environmental Issues and Waste Management Technologies in the Ceramic and Nuclear Industries IX by : John D. Vienna
Download or read book Environmental Issues and Waste Management Technologies in the Ceramic and Nuclear Industries IX written by John D. Vienna and published by John Wiley & Sons. This book was released on 2012-04-05 with total page 384 pages. Available in PDF, EPUB and Kindle. Book excerpt: In today's world of increasingly stringent environmental regulations, it is critical to identify and adequately address environmental issues in the ceramic industry to ensure success. In addition, ceramics and glasses play a critical role in the nuclear industry. Nuclear fuels and waste forms for low-level and high-level radioactive, mixed, and hazardous wastes are primarily either ceramic of glass. Effective and responsible environmental stewardship is becoming increasingly more important in the world. These proceedings detail the results of the ongoing effort in these areas. Proceedings of the symposium held at the 105th Annual Meeting of The American Ceramic Society, April 27-30, in Nashville, Tennessee; Ceramic Transactions, Volume 155.
Book Synopsis Measurement of the Volatility and Glass Transition Temperatures of Glasses Produced During the DWPF Startup Test Program by :
Download or read book Measurement of the Volatility and Glass Transition Temperatures of Glasses Produced During the DWPF Startup Test Program written by and published by . This book was released on 1995 with total page 56 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Defense Waste Processing Facility (DWPF) will immobilize high-level radioactive waste currently stored in underground tanks at the Savannah River Site by incorporating the waste into a glass matrix. The molten waste glass will be poured into stainless steel canisters which will be welded shut to produce the final waste form. One specification requires that any volatiles produced as a result of accidentally heating the waste glass to the glass transition temperature be identified. Glass samples from five melter campaigns, run as part of the DWPF Startup Test Program, were analyzed to determine glass transition temperatures and to examine the volatilization (by weight loss). Glass transition temperatures (T{sub g}) for the glasses, determined by differential scanning calorimetry (DSC), ranged between 445 C and 474 C. Thermogravimetric analysis (TGA) scans showed that no overall weight loss occurred in any of the glass samples when heated to 500 C. Therefore, no volatility will occur in the final glass product when heated up to 500 C.
Book Synopsis Recent Results on the Effect of Gamma Radiation on the Durability and Microstructure of DWPF Glass by :
Download or read book Recent Results on the Effect of Gamma Radiation on the Durability and Microstructure of DWPF Glass written by and published by . This book was released on 1989 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt: The effect of gamma radiation on the durability and microstructure of a simulated nuclear waste glass from the Savannah River Site has been carefully investigated. Three large pieces of glass were irradiated with a Co-60 source to three doses up to a maximum dose of 3.1 x 101° rad. Internal samples of the large pieces of irradiated and unirradiated glass were leached in deionized water to investigate durability changes and were examined by transmission electron microscopy (TEM) to investigate microstructure changes. Leach tests were performed in triplicate at 90°C with crushed glass samples in deionized water. A statistical analysis of the results indicated to the 95% confidence level that the radiation did not affect the glass durability. Careful examination by TEM indicated no effect of gamma radiation on the microstructure of the glass although severe damage could be induced by the electron beam from the microscope. 19 refs., 2 figs., 3 tabs.
Book Synopsis INVESTIGATION OF WASTE GLASS POURING PROCESS OVER A KNIFE EDGE. by :
Download or read book INVESTIGATION OF WASTE GLASS POURING PROCESS OVER A KNIFE EDGE. written by and published by . This book was released on 1999 with total page 56 pages. Available in PDF, EPUB and Kindle. Book excerpt: Vitrification is the process of capturing radioactive waste in glass. The Savannah River Site's (SRS) Defense Waste Processing Facility (DWPF) is one of the facilities using the vitrification technology to treat and immobilize radioactive waste. The objective of the project is to investigate the pouring behavior of molten glass over a pour spout knife edge. Experiments are run using simulant glass containing the same chemical formulation as the radioactive sludge glass, but without radioactive contaminants. The purpose of these tests is to obtain actual glass data that, when combined with previous cold data from other fluids, will provide an overall understanding of the physics of liquids flowing over a pour spout and knife edge, A specific objective is to verify computational fluid dynamics (CFD) models with a range of liquid data with particular emphasis on glass so as to provide confidence in use of these CFD models for designing a new improved pour spout for the DWPF melter. The work to be performed at FIU-HCET includes assembling the melting and pouring system that mimics the DWPF melter and determining the key parameters that may influence wicking. Information from the FIU-HCET melter tests will lead to better operating guidelines for the DWPF melter so as to avoid wicking. During FY98, a bench-scale melter complete with pour spout and a knife edge was designed and assembled at FIU-HCET. Initially, the system was tested with glycerine. Subsequently, glass provided by SRS was used for experimentation. Flow visualization tests were performed with the melter in FY98 to investigate the pouring behavior of molten glass over a pour spout model simulating a DWPF pour spout of the original design. Simulant glass containing the same chemical formulation as sludge glass but without radioactive contaminants was used in the tests. All the tasks and milestones mentioned in the PTP for the project were accomplished. The project completed its second year, and this document reports the tasks and milestones that were accomplished during the 1998 fiscal year.
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 10 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Defense Waste Processing Facility (DWPF) located at the Savannah River Site (SRS) in Aiken, South Carolina, is currently scheduled to vitrify more than 130 million liters of High Level Waste (HLW). The glass product that will be produced must meet certain specifications, as defined in the Waste Acceptance Product Specifications (WAPS), in order for the DWPF canistered waste forms to be sent to the Civilian Radioactive Waste Management System (repository). WAPS 1.3 requires that the DWPF produce a consistent product, which is better than the Environmental Assessment (EA) glass as measured by the B, Na, and Li release from the Product Consistency Test (PCT).
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 1996-05 with total page 1130 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Analytical Results of DWPF Glass Sample Taken During Filling of Canister S01913 by :
Download or read book Analytical Results of DWPF Glass Sample Taken During Filling of Canister S01913 written by and published by . This book was released on 2004 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Defense Waste Processing Facility (DWPF) began processing Sludge Batch 2 (SB2) (Macrobatch 3) in December 2001 as part of Sludge Receipt and Adjustment Tank (SRAT) Batch 208. Macrobatch 3 consists of the contents of Tank 40 and Tank 8 in approximately equal proportions. A glass sample was obtained while pouring Canister S01913 and was sent to the Savannah River National Laboratory (SRNL) Shielded Cells for characterization. This report contains observations of the glass sample, results for the density, the chemical composition, the Product Consistency Test (PCT) and the radionuclide results needed for the Production Record for Canister S01913. The as-received glass appeared homogeneous over the entire surface with a dark and reflective luster. The glass sample weighed 33.04 grams. The results of the composition for glass sample S01913 are in good agreement with the DWPF Slurry Mix Evaporator (SME) results for Batch Number 254, the SME Batch that was being fed to the melter when the sample was collected. The PCT results for the glass indicate that it is significantly more durable than the Environmental Assessment (EA) glass with a normalized boron release of 1.18 g/L for the glass and 10.5 g/L measured for the EA glass. Thus, the glass meets the waste acceptance criterion for durability. The measured density of the glass was 2.56 plus or minus 0.03 g/cm3.
Book Synopsis Handbook of Advanced Radioactive Waste Conditioning Technologies by : Michael I. Ojovan
Download or read book Handbook of Advanced Radioactive Waste Conditioning Technologies written by Michael I. Ojovan and published by Elsevier. This book was released on 2011-01-24 with total page 505 pages. Available in PDF, EPUB and Kindle. Book excerpt: Radioactive wastes are generated from a wide range of sources, including the power industry, and medical and scientific research institutions, presenting a range of challenges in dealing with a diverse set of radionuclides of varying concentrations. Conditioning technologies are essential for the encapsulation and immobilisation of these radioactive wastes, forming the initial engineered barrier required for their transportation, storage and disposal. The need to ensure the long term performance of radioactive waste forms is a key driver of the development of advanced conditioning technologies.The Handbook of advanced radioactive waste conditioning technologies provides a comprehensive and systematic reference on the various options available and under development for the treatment and immobilisation of radioactive wastes. The book opens with an introductory chapter on radioactive waste characterisation and selection of conditioning technologies. Part one reviews the main radioactive waste treatment processes and conditioning technologies, including volume reduction techniques such as compaction, incineration and plasma treatment, as well as encapsulation methods such as cementation, calcination and vitrification. This coverage is extended in part two, with in-depth reviews of the development of advanced materials for radioactive waste conditioning, including geopolymers, glass and ceramic matrices for nuclear waste immobilisation, and waste packages and containers for disposal. Finally, part three reviews the long-term performance assessment and knowledge management techniques applicable to both spent nuclear fuels and solid radioactive waste forms.With its distinguished international team of contributors, the Handbook of advanced radioactive waste conditioning technologies is a standard reference for all radioactive waste management professionals, radiochemists, academics and researchers involved in the development of the nuclear fuel cycle. - Provides a comprehensive and systematic reference on the various options available and under development for the treatment and immobilisation of radioactive wastes - Explores radioactive waste characterisation and selection of conditioning technologies including the development of advanced materials for radioactive waste conditioning - Assesses the main radioactive waste treatment processes and conditioning technologies, including volume reduction techniques such as compaction
Book Synopsis Radioactive Waste Management and Contaminated Site Clean-Up by : William E Lee
Download or read book Radioactive Waste Management and Contaminated Site Clean-Up written by William E Lee and published by Elsevier. This book was released on 2013-10-31 with total page 925 pages. Available in PDF, EPUB and Kindle. Book excerpt: Radioactive waste management and contaminated site clean-up reviews radioactive waste management processes, technologies, and international experiences. Part one explores the fundamentals of radioactive waste including sources, characterisation, and processing strategies. International safety standards, risk assessment of radioactive wastes and remediation of contaminated sites and irradiated nuclear fuel management are also reviewed. Part two highlights the current international situation across Africa, Asia, Europe, and North America. The experience in Japan, with a specific chapter on Fukushima, is also covered. Finally, part three explores the clean-up of sites contaminated by weapons programmes including the USA and former USSR.Radioactive waste management and contaminated site clean-up is a comprehensive resource for professionals, researchers, scientists and academics in radioactive waste management, governmental and other regulatory bodies and the nuclear power industry. - Explores the fundamentals of radioactive waste including sources, characterisation, and processing strategies - Reviews international safety standards, risk assessment of radioactive wastes and remediation of contaminated sites and irradiated nuclear fuel management - Highlights the current international situation across Africa, Asia, Europe, and North America specifically including a chapter on the experience in Fukushima, Japan
