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Title: Development of an Alternative Glass Formulation for Vitrification of Excess Plutonium

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Technical Report
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United States

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MARRA, JAMES. Development of an Alternative Glass Formulation for Vitrification of Excess Plutonium. United States: N. p., 2006. Web. doi:10.2172/882725.
MARRA, JAMES. Development of an Alternative Glass Formulation for Vitrification of Excess Plutonium. United States. doi:10.2172/882725.
MARRA, JAMES. Thu . "Development of an Alternative Glass Formulation for Vitrification of Excess Plutonium". United States. doi:10.2172/882725.
title = {Development of an Alternative Glass Formulation for Vitrification of Excess Plutonium},
author = {MARRA, JAMES},
abstractNote = {},
doi = {10.2172/882725},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Jan 19 00:00:00 EST 2006},
month = {Thu Jan 19 00:00:00 EST 2006}

Technical Report:

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  • This Glass Formulation Strategy describes development approaches to optimize glass compositions for Hanford`s low-level waste vitrification between now and the projected low-level waste facility start-up in 2005. The objectives of the glass formulation task are to develop optimized glass compositions with satisfactory long-term durability, acceptable processing characteristics, adequate flexibility to handle waste variations, maximize waste loading to practical limits, and to develop methodology to respond to further waste variations.
  • The primary focus of the current study is to determine allowable loadings of feed streams containing different ratios of plutonium, uranium, and minor components into the LaBS glass and to evaluate thermal stability with respect to the DWPF pour.
  • An alternative to the In Tank Precipitation and sodium titanate processes at the Savannah River Site is the removal of cesium, strontium, and plutonium from the tank supernate by ion exchange using crystalline silicotitanate (CST). This inorganic material has been shown to effectively and selectively sorb these elements from supernate. The loaded CST could then be immobilized with High-Level Waste (HLW) sludge during vitrification. Initial efforts on the development of a glass formulation for a coupled waste stream indicate that reasonable loadings of both sludge and CST can be achieved in glass.
  • As part of joint project between the Oak Ridge National Laboratory (ORNL) and the Savannah River Technology Center (SRTC), radioactive waste from four different ORNL tank farms will be immobilized. This work, which is funded by the DOE Office of Science and Technology, is designed to create a direct comparison between grouting and vitrification technologies. SRTC efforts have been focused on developing and testing glass formulations for the vitrification of the tank wastes. The radioactive waste is from four different ORNL tank farms: Melton Valley Storage Tanks (MVST), Bethel Valley Evaporator Service Tanks (BVEST), Gunite and Associated Tanks (GAAT), andmore » Old Hydrafracture Tanks (OHF). The sludges in these tanks contain transuranic radionuclides at levels which will make the final waste form (at reasonable waste loadings) TRU. Glass is an acceptable waste form because of its ability to accept a wide variety of components into its network structure. This is important since the waste varies significantly from tank to tank and from tank farm to tank farm. Therefore, glass formulation efforts have centered on developing a formulation that is robust enough to handle large fluctuations in waste composition. Crucible studies have been performed with simulated GAAT, MVST and BVEST sludges. The results of these tests indicate that high waste loadings can be obtained in the glass to significantly reduce the waste volume. This paper will present the results of the glass formulation efforts« less