Two-site equilibrium model for ion exchange between monovalent cations and zeolite-a in a molten salt.
A two-site model has been derived and tested against experimental data for monovalent species ion exchange in molten chloride salt/zeolite A. This system is of interest for the application of spent nuclear fuel treatment. Fission products and transuranics that accumulate in a molten salt electrorefining process can be preferentially removed and eventually stabilized in a waste form, using zeolite A. An excellent fit of Cs-Rb-Na-Li-K data to the model was found with different selectivity sequences for the two sites. Cesium was found to be the preferred cation in the ?-cage sites, while lithium was preferred in the framework sites.
- Research Organization:
- Argonne National Laboratory (ANL)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC02-06CH11357
- OSTI ID:
- 961100
- Report Number(s):
- ANL/ENT/JA-44603
- Journal Information:
- Ind. Eng. Chem. Res., Journal Name: Ind. Eng. Chem. Res. Journal Issue: 18 ; Sep. 3, 2003 Vol. 42; ISSN IECRED; ISSN 0888-5885
- Country of Publication:
- United States
- Language:
- ENGLISH
Similar Records
Equilibrium Model for Ion Exchange Between Multivalent Cations and Zeolite-A in a Molten Salt
Fission product removal from molten salt using zeolite
Performance of a zeolite column system in removing fission products from molten salt
Conference
·
Sat Oct 01 00:00:00 EDT 2005
·
OSTI ID:911756
Fission product removal from molten salt using zeolite
Conference
·
Tue Oct 01 00:00:00 EDT 1996
·
OSTI ID:379094
Performance of a zeolite column system in removing fission products from molten salt
Conference
·
Tue Oct 01 00:00:00 EDT 1996
·
OSTI ID:370523