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Measurement Of Leaching From Simulated Nuclear Waste Glass Using Radiotracers
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Book Synopsis Measurement of Leaching from Simulated Nuclear-waste Glass Using Radiotracers by :
Download or read book Measurement of Leaching from Simulated Nuclear-waste Glass Using Radiotracers written by and published by . This book was released on 1982 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The use of radiotracer spiking as a method of measuring the leaching from simulated nuclear-waste glass is shown to give results comparable with other analytical detection methods. The leaching behavior of 85Sr, 1°6Ru, 133Ba, 137Cs, 141Ce, 152Eu, and other isotopes is measured for several defense waste glasses. These tests show that radiotracer spiking is a sensitive, multielement technique that can provide leaching data, for actual waste elements, that are difficult to obtain by other methods. Additionally, a detailed procedure is described that allows spiked glass to be prepared with a suitable distribution of radionuclides.
Book Synopsis Leaching Savannah River Plant Nuclear Waste Glass in a Saturated Tuff Environment by :
Download or read book Leaching Savannah River Plant Nuclear Waste Glass in a Saturated Tuff Environment written by and published by . This book was released on 1984 with total page 19 pages. Available in PDF, EPUB and Kindle. Book excerpt: Samples of SRP glass containing either simulated or actual radioactive waste were leached at 90°C under conditions simulating a saturated tuff repository environment. The leach vessels were fabricated of tuff and actual tuff groundwater was used. Thus, the glass was leached only in the presence of those materials (including the Type 304L stainless steel canister material) that would be in the actual repository. Tests were performed for time periods up t 6 months at a SA/V ratio of 100 m−1. Results with glass containing simulated waste indicated that stainless steel canister material around the glass did not significantly affect the leaching. Based on Li and B (elements not in significant concentrations in the tuff or tuff groundwater), glass containing simulated waste leached identically to glass containing actual radioactive waste. The tuff buffered the pH so that only a slight increase was observed as a result of leaching. Results with glass containing actual radioactive waste indicated that tuff reduced the concentrations of Cs-137, Sr-90, and Pu-238 in the free groundwater in the simulated repository by 10 to 100X. Also, radiolysis of the groundwater by the glass (approximately 1000 rad/h) did not significantly affect the pH in the presence of tuff. Measured normalized mass losses in the presence of tuff for the glass based on Cs-137, Sr-90, and Pu-238 in the free groundwater were extremely low, nominally 0.02, 0.02, and 0.005 g/m2, respectively, indicating that the glass-tuff system retained radionuclides well. 9 references, 2 figures, 3 tables.
Book Synopsis Leaching Savannah River Plant Nuclear Waste Glass in a Saturated Tuff Environment by : Ned Eugene Bibler
Download or read book Leaching Savannah River Plant Nuclear Waste Glass in a Saturated Tuff Environment written by Ned Eugene Bibler and published by . This book was released on 1984 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Samples of SRP glass containing either simulated or actual radioactive waste were leached at 90°C under conditions simulating a saturated tuff repository environment. The leach vessels were fabricated of tuff and actual tuff groundwater was used. Thus, the glass was leached only in the presence of those materials (including the Type 304L stainless steel canister material) that would be in the actual repository. Tests were performed for time periods up t 6 months at a SA/V ratio of 100 m−1. Results with glass containing simulated waste indicated that stainless steel canister material around the glass did not significantly affect the leaching. Based on Li and B (elements not in significant concentrations in the tuff or tuff groundwater), glass containing simulated waste leached identically to glass containing actual radioactive waste. The tuff buffered the pH so that only a slight increase was observed as a result of leaching. Results with glass containing actual radioactive waste indicated that tuff reduced the concentrations of Cs-137, Sr-90, and Pu-238 in the free groundwater in the simulated repository by 10 to 100X. Also, radiolysis of the groundwater by the glass (approximately 1000 rad/h) did not significantly affect the pH in the presence of tuff. Measured normalized mass losses in the presence of tuff for the glass based on Cs-137, Sr-90, and Pu-238 in the free groundwater were extremely low, nominally 0.02, 0.02, and 0.005 g/m2, respectively, indicating that the glass-tuff system retained radionuclides well.
Download or read book Energy Research Abstracts written by and published by . This book was released on 1983 with total page 1226 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Sodium Diffusion and the Leaching of Simulated Nuclear Waste Glass by : Bernard Peter McGrail
Download or read book Sodium Diffusion and the Leaching of Simulated Nuclear Waste Glass written by Bernard Peter McGrail and published by . This book was released on 1982 with total page 54 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Nuclear Waste Glass Leaching in a Simulated Granite Repository by : BingFu Zhu
Download or read book Nuclear Waste Glass Leaching in a Simulated Granite Repository written by BingFu Zhu and published by . This book was released on 1987 with total page 424 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Initial Comparison of Leach Behavior Between Fully Radioactive and Simulated Nuclear Waste Glass Through Long-term Testing by :
Download or read book Initial Comparison of Leach Behavior Between Fully Radioactive and Simulated Nuclear Waste Glass Through Long-term Testing written by and published by . This book was released on 1992 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt: An initial comparison of glass behavior of simulated nuclear waste glasses has been made through long-term testing of general glass types SRL165, SRL131 and SRL200. The data demonstrate that up to 560 days at S/V of 2000/m, the reacted layers consist of one outer clay layer, which is undetermined by discontinuous etch pits. The regions between the etch pits are alkali depleted. The surface layer becomes thicker as test duration progresses and the reacted layer after the same test time is thinner at higher S/V than at lower S/V. The relative glass durability measured by the thickness of the reacted layer is 165/42S> 131/11S> 200S, which is consistent with solution analyses. In general, the reacted layers on all glass compositions are poorly crystallized which makes the clay identification difficult. The diffraction spacings and EDS compositions for 131/11S and 200S, although not unique to, are consistent with Na (or Ca- ) montmorillonite or nontronite. Both of these are dioctahedral smectite.
Download or read book Envoi à feu Ferry written by and published by . This book was released on with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Leaching Behavior of Nuclear Waste Glasses Under Laboratory Simulated Repository Conditions by : Rajani Adiga
Download or read book Leaching Behavior of Nuclear Waste Glasses Under Laboratory Simulated Repository Conditions written by Rajani Adiga and published by . This book was released on 1984 with total page 246 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Effects of Temperature and Radiation on the Nuclear Waste Glass Product Consistency Leach Test by :
Download or read book Effects of Temperature and Radiation on the Nuclear Waste Glass Product Consistency Leach Test written by and published by . This book was released on 1993 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: Previous leach studies carried out with monolithic glass samples have shown that glass dissolution rates increase with increasing temperature and may or may not increase on exposure to external gamma radiolysis. In this study we have investigated the effects of temperature (70--1200[degrees]C) and radiation on the dissolution of simulated radioactive waste glasses using the Product Consistency Test (PCT). The PCT is a seven day, crushed glass leach test in deionized water that is carried out at 9OO[degrees]C. To date our results indicate no significant effect of external Co--60 gamma radiation when testing various simulated waste glasses at 90[degrees]C in a wellinsulated compartment within a Gammacell 220 irradiation unit. The temperature dependence for glass dissolution clearly exhibits Arrheniustype behavior for two of the three glasses tested. For the third glass the dissolution decreases at the higher temperatures, probably due to saturation effects. Actual radioactive waste glasses will be investigated later as part of this study.
Book Synopsis Repeated Leaching of a Simulated Borosilicate Waste Glass by : Jane E. Robbins
Download or read book Repeated Leaching of a Simulated Borosilicate Waste Glass written by Jane E. Robbins and published by . This book was released on 1982 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Leaching of Actinide-doped Nuclear Waste Glass in a Tuff-dominated System by :
Download or read book Leaching of Actinide-doped Nuclear Waste Glass in a Tuff-dominated System written by and published by . This book was released on 1987 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt: A laboratory leaching test has been performed as part of a project to evaluate the suitability of tuff rocks at Yucca Mountain, Nevada, as a site for a high-level nuclear waste repository. Glass samples were placed in water inside tuff vessels, and then the tuff vessels were placed in water inside Teflon containers. Glass-component leach rates and migration through the tuff were measured for samples of the ATM-8 actinide glass, which is a PNL 76-68 based glass doped with low levels of 99Tc, 237Np, 238U, and 239Pu to simulate wastes. Disc samples of this glass were leached at 90°C for 30, 90, and 183 days inside tuff vessels using a natural groundwater (J-13 well-water) as the leachant. At the end of each leaching interval, the J-13 water present inside and outside the rock vessel was analyzed for glass components in solutions. Boron, molybdenum, and technetium appear to migrate through the rock at rates that depend on the porosity of each vessel and the time. The actinide elements were found only in the inner leachate. Normalized elemental mass loss values for boron, molybdenum, and technetium were calculated using concentrations of the inner and outer leachates and assuming a negligible retention on the rock. The maximum normalized release was 2.3 g/m2 for technetium. Boron, molybdenum, technetium, and neptunium were released linearly with respect to each other, with boron and molybdenum released at about 85% of the technetium rate, and neptunium at 5 to 10% of the technetium rate. Plutonium was found at low levels in the inner leachate but was strongly sorbed on the steel and Teflon supports. Neptunium was sorbed to a lesser extent. 8 refs., 6 figs., 6 tabs.
Book Synopsis Leaching Fully Radioactive SRP Nuclear Waste Glass in Tuff Groundwater in Stainless Steel Vessels by :
Download or read book Leaching Fully Radioactive SRP Nuclear Waste Glass in Tuff Groundwater in Stainless Steel Vessels written by and published by . This book was released on 1986 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: SRP glass containing actual radioactive waste was leached in static tests at 90°C in a tuffaceous groundwater (J-13 water at pH (approximately)7.4) at a SA/V ratio of 100m−1 in 316 stainless steel vessels. Tests were performed for time periods up to 134 days. Normalized mass losses were calculated for 137Cs, 9°Sr, and 238Pu. The 137Cs in the leachate appeared to reach a steady value of (approximately)3 g/m2, corresponding to a steady-state concentration of only 1.0 ppB for total cesium. The mass losses based on 9°Sr and 238Pu appearing in solution were low (
Download or read book Energy Research Abstracts written by and published by . This book was released on 1983 with total page 756 pages. Available in PDF, EPUB and Kindle. Book excerpt: Includes all works deriving from DOE, other related government-sponsored information and foreign nonnuclear information.
Book Synopsis Initial Comparison of Leach Behavior Between Fully Radioactive and Simulated Nuclear Waste Glasses Through Long-term Testing by :
Download or read book Initial Comparison of Leach Behavior Between Fully Radioactive and Simulated Nuclear Waste Glasses Through Long-term Testing written by and published by . This book was released on 1992 with total page 10 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Radioactive Waste Processing and Disposal by : U.S. Nuclear Regulatory Commission
Download or read book Radioactive Waste Processing and Disposal written by U.S. Nuclear Regulatory Commission and published by . This book was released on 1980 with total page 908 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Vaporization of Simulated Nuclear Waste Glass by : John W. Hastie
Download or read book Vaporization of Simulated Nuclear Waste Glass written by John W. Hastie and published by . This book was released on 1983 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
