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Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Glass strategy: Hanford’s enhanced waste glass program
The mission of the Department of Energy’s Office of River Protection (ORP) is to complete the safe cleanup of waste resulting from decades of nuclear weapons development. One of the most technologically challenging responsibilities is the safe disposition of approximately 56 million gallons of radioactive waste historically stored in 177 tanks at the Hanford Site in Washington state.
ORP has a clear incentive to reduce the overall mission duration and cost. One pathway is to develop and deploy innovative technical solutions that can advance baseline flow sheets toward higher efficiency operations while reducing identified risks without compromising safety. Vitrification is the baseline process that will convert both high-level and low-level radioactive waste at Hanford into a stable glass waste form for long-term storage and disposal.
Although vitrification is a mature technology, there are key areas where technology can further reduce operational risks, advance baseline processes to maximize waste throughput, and provide the underpinning to enhance operational flexibility; all steps in reducing mission duration and cost.
Kari Korpiola, Joonas Järvinen, Karri Penttilä, Petri Kotiluoto
Nuclear Technology | Volume 172 | Number 2 | November 2010 | Pages 230-236
Technical Note | Radioactive Waste Management and Disposal | doi.org/10.13182/NT10-A10908
Articles are hosted by Taylor and Francis Online.
Incineration of spent ion exchange resin was simulated using the ChemSheet chemical calculation program. The simulation of the incineration was modeled for typical spent resin produced by pressurized water reactors (PWRs) and boiling water reactors (BWRs) in Finland. The objective of the study was to find the volume and mass reduction and the chemical compounds formed during incineration. The simulation showed that active elements did not play any role in incineration owing to small amount of Cs, Co, etc. The ash contained metal oxides - mainly hematite, iron oxide Fe2O3. Other products of the incineration were water, carbon dioxide, sulfuric acid, and nitrogen oxides. The volume reductions 1/100 and 1/14 of the spent resin were obtained for PWRs and BWRs, respectively. The annual ash production from incineration was calculated to be 408 kg and 746 kg for the currently operating Finnish PWR and BWR plants in Loviisa and Olkiluoto, respectively.
