Salt-occluded zeolites as an immobilization matrix for chloride waste salt
Abstract
The pyrometallurgical processing of spent fuel from the integral fast reactor (IFR), an advanced reactor under development at Argonne National Laboratory, will generate a chloride salt waste containing the alkali-metal, alkaline-earth, and some of the rare-earth fission products. Salt-occluded zeolite A, formed by equilibrating simulated molten waste salt and zeolite A, has been investigated as an immobilization matrix for this salt waste. In this concept, the chloride waste salt is loaded into the zeolite cavities, and cesium and strontium from the salt are preferentially sorbed by the zeolite. Experiments showed that the salt occluded zeolite powders are leach resistant and radiation stable. The conclusion is that the salt-occluded zeolite is a promising immobilization matrix for the IFR waste salt.
- Authors:
-
- Argonne National Lab., IL (United States). Chemical Technology Div.
- Publication Date:
- OSTI Identifier:
- 5535109
- Resource Type:
- Journal Article
- Journal Name:
- Journal of the American Ceramic Society; (United States)
- Additional Journal Information:
- Journal Volume: 76:11; Journal ID: ISSN 0002-7820
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; SPENT FUELS; PYROCHEMICAL REPROCESSING; ZEOLITES; SOLIDIFICATION; CHLORIDES; FAST REACTORS; SALTS; CHLORINE COMPOUNDS; ENERGY SOURCES; EPITHERMAL REACTORS; FUELS; HALIDES; HALOGEN COMPOUNDS; INORGANIC ION EXCHANGERS; ION EXCHANGE MATERIALS; MATERIALS; MINERALS; NUCLEAR FUELS; PHASE TRANSFORMATIONS; REACTOR MATERIALS; REACTORS; REPROCESSING; SEPARATION PROCESSES; SILICATE MINERALS; 050800* - Nuclear Fuels- Spent Fuels Reprocessing
Citation Formats
Lewis, M A, Fischer, D F, and Smith, L J. Salt-occluded zeolites as an immobilization matrix for chloride waste salt. United States: N. p., 1993.
Web. doi:10.1111/j.1151-2916.1993.tb04023.x.
Lewis, M A, Fischer, D F, & Smith, L J. Salt-occluded zeolites as an immobilization matrix for chloride waste salt. United States. https://doi.org/10.1111/j.1151-2916.1993.tb04023.x
Lewis, M A, Fischer, D F, and Smith, L J. 1993.
"Salt-occluded zeolites as an immobilization matrix for chloride waste salt". United States. https://doi.org/10.1111/j.1151-2916.1993.tb04023.x.
@article{osti_5535109,
title = {Salt-occluded zeolites as an immobilization matrix for chloride waste salt},
author = {Lewis, M A and Fischer, D F and Smith, L J},
abstractNote = {The pyrometallurgical processing of spent fuel from the integral fast reactor (IFR), an advanced reactor under development at Argonne National Laboratory, will generate a chloride salt waste containing the alkali-metal, alkaline-earth, and some of the rare-earth fission products. Salt-occluded zeolite A, formed by equilibrating simulated molten waste salt and zeolite A, has been investigated as an immobilization matrix for this salt waste. In this concept, the chloride waste salt is loaded into the zeolite cavities, and cesium and strontium from the salt are preferentially sorbed by the zeolite. Experiments showed that the salt occluded zeolite powders are leach resistant and radiation stable. The conclusion is that the salt-occluded zeolite is a promising immobilization matrix for the IFR waste salt.},
doi = {10.1111/j.1151-2916.1993.tb04023.x},
url = {https://www.osti.gov/biblio/5535109},
journal = {Journal of the American Ceramic Society; (United States)},
issn = {0002-7820},
number = ,
volume = 76:11,
place = {United States},
year = {Mon Nov 01 00:00:00 EST 1993},
month = {Mon Nov 01 00:00:00 EST 1993}
}