Development and properties of crystalline silicotitanate (CST) ion exchangers for radioactive waste applications

Miller, James E.; Brown, Nathan P.

doi:10.2172/469131

Cited by 33 publications

(29 citation statements)

References 22 publications

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“…The Department of Energy (DOE) has funded the development and commercialization of CST as an ion exchange media applicable to the treatment of wastes at multiple DOE sites (Miller, 1997). After B-10 development studies that demonstrated the effectiveness of CST to remove cesium from various aqueous solutions, UOP was selected as a technology transfer partner to commercialize CST (Miller, 1997).…”

Section: B-1 Backgroundmentioning

confidence: 99%

“…After B-10 development studies that demonstrated the effectiveness of CST to remove cesium from various aqueous solutions, UOP was selected as a technology transfer partner to commercialize CST (Miller, 1997). Starting in 1994, UOP has supplied CST for both testing and use at various DOE sites, including Savannah River, Oak Ridge National Laboratory, Los Alamos National Laboratory, the Pacific Northwest Laboratory and the INEEL (Miller, 1997).…”

Section: B-1 Backgroundmentioning

confidence: 99%

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Sodium-bearing Waste Treatment Technology Evaluation Report

Barnes¹,

Olson²,

Taylor³

2004

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A Settlement Agreement between the U.S. Department of Energy (DOE) and the State of Idaho mandates treatment of sodium-bearing waste (SBW) stored at the Idaho Nuclear Technology and Engineering Center located within the Idaho National Engineering and Environmental Laboratory (INEEL). One of the requirements of the Settlement Agreement is to complete treatment of SBW by December 31, 2012. Hence, SBW disposition is one of the Idaho Operation Office's (NE-ID) and State of Idaho's top priorities at the INEEL.The INEEL has been working over the past several years to identify a treatment technology that meets NE-ID and regulatory treatment requirements, including consideration of stakeholder input. Many studies, including the High-Level Waste and Facilities Disposition Environmental Impact Statement, have resulted in the identification of five treatment alternatives that form a short list of perhaps the most appropriate technologies for the DOE to select from. The alternatives are (a) calcination with maximum achievable control technology (MACT) upgrade, (b) steam reforming, (c) cesium ion exchange (CsIX) with immobilization, (d) direct evaporation, and (e) vitrification. Each alternative has undergone some degree of applied technical development and preliminary process design over the past four years.Applied technology development and preliminary process design activities have been required to provide the data necessary for informed decision making and evaluation of the treatment options. A technically defensible selection of a SBW treatment process has been a key driver for the collection of needed data. This document presents a summary of the data gathered in recent years and evaluates the technical maturity of each option by listing and discussing the identified higher-risk technical uncertainties. The SBW issue and the five alternatives are described, and their technical performance (throughputs, waste product descriptions and volumes, preliminary facility footprints, etc.) is summarized in the main body. Details of preliminary process design and applied development activities for three of the alternatives (steam reforming, CsIX with immobilization, and direct evaporation) are presented in three appendices; a recent feasibility study provides the details for calcination. There have been no recent activities performed with regard to vitrification; that section summarizes and references previous work.

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Section: B-1 Backgroundmentioning

confidence: 99%

Section: B-1 Backgroundmentioning

confidence: 99%

Sodium-bearing Waste Treatment Technology Evaluation Report

Barnes¹,

Olson²,

Taylor³

2004

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“…However, both cesium and strontium can be removed from alkaline solutions by ion exchange. 5 The feasibility study on the vitrification of calcine 6 proposes to run the ion exchange process after the acidic and caustic scrubber solutions are combined. In this case, the ion exchange takes place in an alkaline environment, which is normal operation at most other sites.…”

Section: Ion Exchange Media Disposalmentioning

confidence: 99%

Testing and Disposal Strategy for Secondary Wastes from Vitrification of Sodium-Bearing Waste at the Idaho Nuclear Technology and Engineering Center

Herbst¹

2002

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The Idaho National Engineering and Environmental Laboratory (INEEL) is considering vitrification to process liquid sodium-bearing waste. Preliminary studies were completed to evaluate the potential secondary wastes from the melter off-gas cleanup systems. Projected secondary wastes comprise acidic and caustic scrubber solutions, HEPA filters, activated carbon, and ion exchange media. Possible treatment methods, waste forms, and disposal sites are evaluated from radiological and mercury contamination estimates.iv v SUMMARYThe High-Level Waste Program is considering vitrification of the liquid sodium-bearing waste stored at the Idaho Nuclear Technology and Engineering Center, which is part of the Idaho National Engineering and Environmental Laboratory (INEEL). Several secondary wastes are anticipated from the melter off-gas treatment system, such as acidic and caustic scrubber solutions, HEPA filters, activated carbon, and ion exchange media. These wastes are expected to be designated as mixed low-level wastes. Scoping studies were completed to evaluate possible disposal paths for these wastes. Radiological and land disposal regulations as well as individual site waste acceptance criteria were considered to anticipate necessary treatment methods, waste forms, and disposal sites for each waste stream.

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“…(2.4) would indicate a solid density of 100 lb/ft 3 (1.602 g/cm 3 ), which seems low and could indicate void fractions greater than 0.35. The particle density of CST powder is reported by Miller and Brown (1997) to be ~2.9 g/cm 3 , with a bulk density of 0.85 g/cm 3 .…”

Section: Ionsiv ] ] Ie-911_ _mentioning

confidence: 99%

Thermal Conductivity of IONSIV(R) IE-911(TM) Crystalline Silicotitanate and Savannah River Waste Simulant Solutions

Spencer¹

2001

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Development and properties of crystalline silicotitanate (CST) ion exchangers for radioactive waste applications

Cited by 33 publications

References 22 publications

Sodium-bearing Waste Treatment Technology Evaluation Report

Sodium-bearing Waste Treatment Technology Evaluation Report

Testing and Disposal Strategy for Secondary Wastes from Vitrification of Sodium-Bearing Waste at the Idaho Nuclear Technology and Engineering Center

Thermal Conductivity of IONSIV(R) IE-911(TM) Crystalline Silicotitanate and Savannah River Waste Simulant Solutions

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