Abstracts 6) 40275 – Next Generati<strong>on</strong> Waste Glass Melters in the U.S. DOE Waste Processing Program Steven P. Schneider, Gary Smith, US DOE (USA) <str<strong>on</strong>g>The</str<strong>on</strong>g> USA Department of Energy (U.S. DOE) Office of Envir<strong>on</strong>mental Management (EM) is evaluating alternative opti<strong>on</strong>s for waste glass melting technologies. Specifically, DOEEM is assessing advanced melter technologies and developing a comprehensive research plan for next generati<strong>on</strong> waste glass melter design and dem<strong>on</strong>strati<strong>on</strong>. Resoluti<strong>on</strong> of the USA nuclear waste legacy requires the design, c<strong>on</strong>structi<strong>on</strong> and operati<strong>on</strong> of large and technically complex <strong>on</strong>e-of-a-kind processing facilities coupled to equally complex waste treatment and vitrificati<strong>on</strong> facilities. <str<strong>on</strong>g>The</str<strong>on</strong>g> loading of nuclear waste into glass and the glass producti<strong>on</strong> rates at U.S. vitrificati<strong>on</strong> facilities are limited by the current melter technology. Significant reducti<strong>on</strong>s in glass volumes for disposal and missi<strong>on</strong> life are <strong>on</strong>ly possible with advancements in melter technology and glass formulati<strong>on</strong>s. Melters with higher throughput rate may shorten cleanup missi<strong>on</strong>, in additi<strong>on</strong> melters that allow for higher waste loading in glass may significantly reduce lifecycle costs. To help focus the next generati<strong>on</strong> waste glass melter program, DOE-EM c<strong>on</strong>vened an internati<strong>on</strong>al workshop to assess nuclear waste melter technologies and have used the melter workshop to help develop a comprehensive research plan for melter design and dem<strong>on</strong>strati<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> workshop included both oral presentati<strong>on</strong>s and discussi<strong>on</strong> sessi<strong>on</strong>s from waste glass melter experts from around the world to assess the "state of the art" in melter technology and to lay the groundwork for a program plan that includes evoluti<strong>on</strong>ary changes to existing Joule-heated ceramic-lined liquid fed melters, as well as transformati<strong>on</strong>al melter technologies such as inducti<strong>on</strong> and hybrid-heated systems. At that workshop, representatives from many nati<strong>on</strong>s and internati<strong>on</strong>al organizati<strong>on</strong>s (IAEA, China, France, Germany, India, Japan, Korea, Russia, UK, and the USA), universities (Catholic University of America, Missouri University of Science and Technology), and private companies (EnergySoluti<strong>on</strong>s, Kuri<strong>on</strong>, URS) met to assess advanced melter technologies which helped the U.S. develop a comprehensive research plan for advanced waste glass melter design and dem<strong>on</strong>strati<strong>on</strong> with the goal of improved performance and reduced cost. <str<strong>on</strong>g>The</str<strong>on</strong>g> U.S. DOE Next Generati<strong>on</strong> Waste Glass Melter Program is discussed in this paper. SESSION L2: Solidificati<strong>on</strong> and Package (1) 1) 40021 – Commercializati<strong>on</strong> Project of Ulchin Vitrificati<strong>on</strong>� Hyun-jun Jo, Che<strong>on</strong>-Woo Kim, KHNP (Korea Rep.); Tae-W<strong>on</strong> Hwang, Nuclear Engineering & Technology Institure (Korea Rep.) <str<strong>on</strong>g>The</str<strong>on</strong>g> Ulchin Vitrificati<strong>on</strong> Facility (UVF), to be used for the vitirificati<strong>on</strong> of low-and intermediate-level radioactive waste (LILW) generated by nuclear power plants (NPPs), is the world’s first commercial facility using Cold Crucible Inducti<strong>on</strong> Melter (CCIM) technology. <str<strong>on</strong>g>The</str<strong>on</strong>g> c<strong>on</strong>structi<strong>on</strong> of the facility was begun in 2005 and was completed in 2007. From December 2007 to September 2009, all key performance tests, such as the system functi<strong>on</strong>al test, the cold test, the hot test, and the real waste test, were successfully carried out. <str<strong>on</strong>g>The</str<strong>on</strong>g> UVF commenced commercial operati<strong>on</strong> in October 2009 for the vitrificati<strong>on</strong> of radioactive waste. 2) 40023 – Plasma Gasificati<strong>on</strong>/Vitrificati<strong>on</strong> of Wet ILW Gary Hanus, John Williams, Matt Zirbes, Phoenix Soluti<strong>on</strong>s Co. (USA) Magnox South Ltd has authorized a variety of decommissi<strong>on</strong>ing programmes to evaluate various technologies for timely and cost-effective remediati<strong>on</strong> of a spectrum of waste streams resulting from the operati<strong>on</strong> of their reactors. Of particular current interest is wet, intermediate level waste (ILW) in the form of solids, sludges and liquids. Hinkley Point A has over 137,000 litres of ILW organic cati<strong>on</strong> resin c<strong>on</strong>taining significant quantities of radio-cesium (Cs). In 2009 Phoenix Soluti<strong>on</strong>s Co was awarded a c<strong>on</strong>tract by Magnox South Ltd to dem<strong>on</strong>strate the effectiveness of thermal plasma treatment of this wet ILW resin waste stream. <str<strong>on</strong>g>The</str<strong>on</strong>g> objective of the wet ILW plasma treatment project was to feed organic resin sludge (c<strong>on</strong>taining a cesium surrogate) and a borosilicate glass frit simultaneously into a thermal plasma reactor to dem<strong>on</strong>strate the gasificati<strong>on</strong> of the organic c<strong>on</strong>tent of the resin while capturing the cesium within a molten glass bath. A total of approximately 200 litres of glass product were produced. Approximately 5 metric t<strong>on</strong>nes of organic resin simulant were provided to Phoenix Soluti<strong>on</strong>s Co c<strong>on</strong>sisting of a mixture of 68% water / NaOH soluti<strong>on</strong>, 30% organic cati<strong>on</strong> resin material with bound Cs and 2% other, including a small proporti<strong>on</strong> of cesium in soluti<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> off-gas species from the plasma reactor exhaust were sampled by an independent, qualified sampling organizati<strong>on</strong> focusing <strong>on</strong> VOCs, HCl, NOx, SOx, CO, CO2, dioxins and furans as well as particulate levels. Glass samples were obtained and analyzed for crystalline inclusi<strong>on</strong>s, elemental identificati<strong>on</strong>, and viscosity characteristics at temperatures near the process melt c<strong>on</strong>diti<strong>on</strong>s. <str<strong>on</strong>g>The</str<strong>on</strong>g> process temperature was maintained near 1000 ºC while the molten glass bath was held between 1100 and 1200 ºC. <str<strong>on</strong>g>The</str<strong>on</strong>g> processing produced 200 litres of glass, 150 litres of which were successfully tapped from the plasma reactor into a standard Sellafield vitrified HLW disposal canister. This paper will describe the basic waste processing approach, the process hardware utilized, the process c<strong>on</strong>trol features and the test results. Several trial tests were c<strong>on</strong>ducted, the l<strong>on</strong>gest of which processed over 2 metric t<strong>on</strong>nes of 54
Abstracts dewatered resin waste together with 400 kg of glass. Further testing with improved process c<strong>on</strong>trols dem<strong>on</strong>strated an increase in cesium retenti<strong>on</strong> in the glass product. 3) 40026 – Solidificati<strong>on</strong> Of Simulated Liquid Waste Of Primary Loop Resin Eluti<strong>on</strong> Process Of PWR Masamichi Obata, Michitaka Saso, Masaaki Kaneko, Nobuhito Ogaki, Taichi Horimoto, Toshiba corporati<strong>on</strong> (Japan);Toshikazu Waki, <str<strong>on</strong>g>The</str<strong>on</strong>g> Kansai Electirc Power Co., Inc. (Japan) Primary loop resin waste is eluted by sulfuric acid in <str<strong>on</strong>g>The</str<strong>on</strong>g> Kansai Electic Company Mihama,Takahama and Oi nuclear power stati<strong>on</strong>. Waste soluti<strong>on</strong> from this eluti<strong>on</strong> process is planned to be solidified by cement. This study bring out a range of chemical compositi<strong>on</strong> and crud c<strong>on</strong>centrati<strong>on</strong> of waste soluti<strong>on</strong> from this eluti<strong>on</strong> process, and examine the properties of alumina cement solidificati<strong>on</strong> process and solidified material. Test for sulfate i<strong>on</strong>, borate, lithium, amm<strong>on</strong>ium i<strong>on</strong> was carried out. Volume reducti<strong>on</strong> ratio of over 0.5 was archieved for 5 to 25wt% of sulfate i<strong>on</strong> and
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