Salt-Zeolite Ion Exchange Equilibrium Studies for Complete Set of Fission Products in Molten LiCl-KCl
Journal Article
·
· Nuclear Technology Journal
OSTI ID:985951
This paper presents results on LiCl-KCl based molten salts/zeolite-A contact experiments and the associated equilibrium ion exchange model. Experiments examine the contact behaviors of various ternary salts (LiCl-KCl-YCl3, LiCl-KCl-LaCl3, and LiCl-KCl-PrCl3) and quaternary salts (LiCl-KCl-CsCl-NdCl3 and LiCl-KCl-CsCl-SrCl2) with the zeolite-A. The developed equilibrium model assumes that there are ion exchange and occlusion sites, both of which are in equilibrium with the molten salt phase. A systematic approach in estimating total occlusion capacity of the zeolite-A is developed. The parameters of the model, including the total occlusion capacity of the zeolite-A, were determined from fitting experimental data collected via multiple independent studies including the ones reported in this paper. Experiments involving ternary salts were used for estimating the parameters of the model, while those involving quaternary salts were used to validate the model.
- Research Organization:
- Idaho National Laboratory (INL)
- Sponsoring Organization:
- DOE - NE
- DOE Contract Number:
- AC07-05ID14517
- OSTI ID:
- 985951
- Report Number(s):
- INL/JOU-08-14943
- Journal Information:
- Nuclear Technology Journal, Journal Name: Nuclear Technology Journal Journal Issue: 3 Vol. 171
- Country of Publication:
- United States
- Language:
- English
Similar Records
Equilibrium Model for Ion Exchange Between Multivalent Cations and Zeolite-A in a Molten Salt
Investigation of Fission Product Transport into Zeolite-A for Pyroprocessing Waste Minimization
Effects of composition and canister centerline cooling on microstructure, phase distribution, and chemical durability of dehalogenated iron phosphate waste forms
Conference
·
Sat Oct 01 00:00:00 EDT 2005
·
OSTI ID:911756
Investigation of Fission Product Transport into Zeolite-A for Pyroprocessing Waste Minimization
Journal Article
·
Thu Jan 31 23:00:00 EST 2013
· Nuclear Technology
·
OSTI ID:1062743
Effects of composition and canister centerline cooling on microstructure, phase distribution, and chemical durability of dehalogenated iron phosphate waste forms
Journal Article
·
Mon Feb 28 23:00:00 EST 2022
· Journal of Non-crystalline Solids
·
OSTI ID:1872430