Thermal analysis for ion-exchange column system

Conference · Sun Jul 01 00:00:00 EDT 2012

OSTI ID:22107871

Lee, S. Y.; King, W. D. ^[1]

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1. Savannah River National Laboratory, Savannah River Site, Aiken, SC 29808 (United States)

Models have been developed to simulate the thermal characteristics of Crystalline Silico-titanate (CST) ion exchange media fully loaded with radioactive cesium in a column configuration and distributed within a waste storage tank. This work was conducted to support the Small Column Ion Exchange (SCIX) program which is focused on processing dissolved, high-sodium salt waste for the removal of specific radionuclides (including Cs-137, Sr-90, and actinides) within a High Level Waste (HLW) storage tank at the Savannah River Site. A two-dimensional computational modeling approach for the in-column ion-exchange domain was taken to include conservative, bounding estimates for key parameters such that the results would provide the maximum centerline temperatures achievable under the design configurations using a feed composition known to promote high cesium loading on CST. A primary objective of these calculations was to estimate temperature distributions across packed CST beds immersed in waste supernate or filled with dry air under various accident scenarios. Accident scenarios evaluated included loss of salt solution flow through the bed, inadvertent column drainage, and loss of active cooling in the column. The modeling results demonstrate that the baseline design using one central and four outer cooling tubes provides a highly efficient cooling mechanism for reducing the maximum column temperature. (authors)

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 22107871
• Resource Relation: Conference: ICAPP '12: 2012 International Congress on Advances in Nuclear Power Plants, Chicago, IL (United States), 24-28 Jun 2012; Other Information: Country of input: France; 6 refs.; Related Information: In: Proceedings of the 2012 International Congress on Advances in Nuclear Power Plants - ICAPP '12| 2799 p.
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
22 GENERAL STUDIES OF NUCLEAR REACTORS
ACTINIDES
CESIUM
CESIUM 137
CESIUM COMPOUNDS
COOLING
DESIGN
DRAINAGE
HIGH-LEVEL RADIOACTIVE WASTES
HYPOTHETICAL ACCIDENTS
ION EXCHANGE
SALTS
SAVANNAH RIVER
SIMULATION
SODIUM
STRONTIUM 90
TANKS
THERMAL ANALYSIS
TITANATES
TWO-DIMENSIONAL CALCULATIONS
WASTE STORAGE