Testing of Crystalline Silicotitanate to Support Tank-Side Cesium Removal System Operations - 20458
Creators
- 1. Pacific Northwest National Laboratory, Richland, WA 99352 (United States)
- 2. Washington River Protection Solutions, LLC, Richland, WA 99352 (United States)
Description
The direct feed of waste from the Hanford tank farms to the Low-Activity Waste Facility at the Hanford Waste Treatment and Immobilization Plant requires an intermediate treatment step that prepares the waste for vitrification. Washington River Protection Solutions (WRPS) selected a near-tank treatment system known as the Tank-Side Cesium Removal (TSCR) system to perform the required intermediate treatment functions. The approach in the TSCR system is to filter waste supernatant with a sintered metal dead-end filter and then use a series of ion exchange columns to remove cesium; this system has several similarities to the Tank Closure Cesium Removal system that has been deployed on the Savannah River Site. The ion exchange media proposed for use is crystalline silicotitanate (CST), which is a non-elutable media with a high affinity for cesium. Because the media is non-elutable, loaded columns will be blown down with compressed air, moved into interim storage, and replaced with new columns when cesium capacity is reached. The assumed extent and rate of drying that could be achieved in the TSCR column geometry lacked confirmation by experimental data. In addition, once the columns are loaded with cesium, they generate flammable gases (primarily hydrogen) via radiolysis acting on any resident liquids, i.e., moisture, remaining in the media bed. An assessment of available information on CST concluded that gas generation data that bounds expected operational conditions were needed to support the TSCR system safety basis and planned operations. Working with WRPS, Pacific Northwest National Laboratory (PNNL) designed and conducted testing with CST media to address the need for (a) representative in-column drying data, and (b) bounding flammable gas generation data. Drying testing was performed using a full-height column with a diameter of approximately 2 inches with injected air at temperatures of 18 deg. C and 30 deg. C. Gas generation testing was conducted in an engineered bunker that allowed simultaneous irradiation of up to eight samples at a time. These two experimental approaches used at PNNL for the CST testing are summarized and the major outcomes are presented. (authors)
Availability note (English)
Available from: WM Symposia, Inc., PO Box 27646, 85285-7646 Tempe, AZ (US)Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 33 p.
- Report number
- INIS-US--21-WM-20458
Conference
- Title
- 46. Annual Waste Management Conference
- Acronym
- WM2020
- Dates
- 8-12 Mar 2020
- Place
- Phoenix, AZ (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 52070900
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S37: INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CESIUM; COMPRESSED AIR; DRYING; FILTERS; GEOMETRY; HUMIDITY; HYDROGEN; ION EXCHANGE; IRRADIATION; LIQUIDS; RADIOACTIVE WASTE PROCESSING; RADIOACTIVE WASTE STORAGE; RADIOACTIVE WASTES; RADIOLYSIS; SAVANNAH RIVER PLANT; TANKS; TESTING; VITRIFICATION
- Descriptors DEC
- AIR; ALKALI METALS; CHEMICAL RADIATION EFFECTS; CHEMICAL REACTIONS; COMPRESSED GASES; CONTAINERS; DECOMPOSITION; ELEMENTS; FLUIDS; GASES; MANAGEMENT; MATERIALS; MATHEMATICS; METALS; MOISTURE; NATIONAL ORGANIZATIONS; NONMETALS; PROCESSING; RADIATION EFFECTS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTE MANAGEMENT; STORAGE; US AEC; US DOE; US ERDA; US ORGANIZATIONS; WASTE MANAGEMENT; WASTE PROCESSING; WASTE STORAGE; WASTES
Optional Information
- Notes
- 18 refs.; available online at: https://www.xcdsystem.com/wmsym/2020/index.html