Development of iodine waste forms using low-temperature sintering glass.
This presentation will describe our recent work on the use of low temperature-sintering glass powders mixed with either AgI or AgI-zeolite to produce a stable waste form. Radioactive iodine ({sup 129}I, half-life of 1.6 x 10{sup 7} years) is generated in the nuclear fuel cycle and is of particular concern due to its extremely long half-life and its effects on human health. As part of the DOE/NE Advanced Fuel Cycle Initiative (AFCI), the separation of {sup 129}I from spent fuel during fuel reprocessing is being studied. In the spent fuel reprocessing scheme under consideration, the iodine is released in gaseous form and collected using Ag-loaded zeolites, to form AgI. Although AgI has extremely low solubility in water, it has a relatively high vapor pressure at moderate temperatures (>550 C), thus limiting the thermal processing. Because of this, immobilization using borosilicate glass is not feasible. Therefore, a bismuth oxide-based glasses are being studied due to the low solubility of bismuth oxide in aqueous solution at pH > 7. These waste forms were processed at 500 C, where AgI volatility is low but the glass powder is able to first densify by viscous sintering and then crystallize. Since the glass is not melted, a more chemically stable glass can be used. The AgI-glass mixture was found to have high iodine leach resistance in these initial studies.
- Research Organization:
- Sandia National Laboratories (SNL), Albuquerque, NM, and Livermore, CA (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC04-94AL85000
- OSTI ID:
- 1021093
- Report Number(s):
- SAND2010-4324C; TRN: US1103922
- Resource Relation:
- Conference: Proposed for presentation at the Materials Challenges in Alternative & Renewable Energy held February 21-24, 2010 in Cocoa Beach, FL.
- Country of Publication:
- United States
- Language:
- English
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Radioactive iodine separations and waste forms development.
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Related Subjects
12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
AQUEOUS SOLUTIONS
BISMUTH
BISMUTH OXIDES
BOROSILICATE GLASS
FUEL CYCLE
GLASS
HALF-LIFE
IODINE
MIXTURES
NUCLEAR FUELS
PROCESSING
REPROCESSING
SINTERING
SOLUBILITY
SPENT FUELS
VAPOR PRESSURE
VOLATILITY
WASTE FORMS
WATER
ZEOLITES