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Deliquescence Behavior of Multicomponent Salts: Effects on the Drip Shield and Waste Package Chemical Environment of the Proposed Nuclear Waste Repository at Yucca Mountain, Nevada

Published online by Cambridge University Press:  21 March 2011

Roberto T. Pabalan ,
Lietai Yang  and
Lauren Browning
Roberto T. Pabalan
Affiliation:
Center for Nuclear Waste Regulatory Analyses, San Antonio, TX 78238-5166, U.S.A.
Lietai Yang
Affiliation:
Center for Nuclear Waste Regulatory Analyses, San Antonio, TX 78238-5166, U.S.A.
Lauren Browning
Affiliation:
Center for Nuclear Waste Regulatory Analyses, San Antonio, TX 78238-5166, U.S.A.
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Abstract

Thermodynamic calculations were conducted to determine the deliquescence behavior of salt mixtures and to simulate the evaporation of Yucca Mountain groundwaters. The results are consistent with published experimental data that show the deliquescence points of salt mixtures are lower than that of individual salts. For mixtures of NaCl and KCl salts, the deliquescence point of pure NaNO3 salt is an appropriate lower bound. However, mixtures containing magnesium and calcium salts have much lower deliquescence points than pure NaNO3. If magnesium and calcium salts are deposited on waste package and drip shield surfaces, it could lead to earlier initiation of aqueous corrosion than assumed by the DOE in its performance assessment abstractions. Such salt mixtures can be formed by evaporation of waters with compositions similar to some Yucca Mountain porewaters and would be characterized by low deliquescence relative humidity, high chloride concentration, and low concentrations of anions such as free (uncomplexed) nitrate and sulfate that could mitigate against the chloride-enhanced corrosion of the waste package. Evaporation of Yucca Mountain groundwaters also could lead to fluoride concentrations that are above the threshold for accelerated corrosion of the titanium drip shield.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 713: Symposium JJ – Scientific Basis for Nuclear Waste Management XXV , 2002 , JJ1.4
Copyright
Copyright © Materials Research Society 2002

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