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Establishment of Uncertainty Ranges and Probability Distributions of Actinide Solubilities for Performance Assessment in the Waste Isolation Pilot Plant

Published online by Cambridge University Press:  01 February 2011

Yongliang Xiong ,
Jim Nowak ,
Laurence H. Brush ,
Ahmed E. Ismail  and
Jennifer Long
Yongliang Xiong
Affiliation:
[email protected], sandia national laboratories, Carlsbad, New Mexico, United States
Jim Nowak
Affiliation:
[email protected], Sandia National Laboratories, Carlsbad, New Mexico, United States
Laurence H. Brush
Affiliation:
[email protected], Sandia National Laboratories, Repository Performance Dept. 6712, 4100 National Parks Hwy., Carlsbad, New Mexico, 88220, United States, 575 234 0105, 575 234 0061
Ahmed E. Ismail
Affiliation:
[email protected], Sandia National Laboratories, Carlsbad, New Mexico, United States
Jennifer Long
Affiliation:
[email protected], Sandia National Laboratories, Carlsbad, New Mexico, United States
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Abstract

The Fracture-Matrix Transport (FMT) code developed at Sandia National Laboratories solves chemical equilibrium problems using the Pitzer activity coefficient model with a database containing actinide species. The code is capable of predicting actinide solubilities at 25 °C in various ionic-strength solutions from dilute groundwaters to high-ionic-strength brines. The code uses oxidation state analogies, i.e., Am(III) is used to predict solubilities of actinides in the +III oxidation state; Th(IV) is used to predict solubilities of actinides in the +IV state; Np(V) is utilized to predict solubilities of actinides in the +V state. This code has been qualified for predicting actinide solubilities for the Waste Isolation Pilot Plant (WIPP) Compliance Certification Application in 1996, and Compliance Re-Certification Applications in 2004 and 2009.

We have established revised actinide-solubility uncertainty ranges and probability distributions for Performance Assessment (PA) by comparing actinide solubilities predicted by the FMT code with solubility data in various solutions from the open literature. The literature data used in this study include solubilities in simple solutions (NaCl, NaHCO3, Na2CO3, NaClO4, KCl, K2CO3, etc.), binary mixing solutions (NaCl+NaHCO3, NaCl+Na2CO3, KCl+K2CO3, etc.), ternary mixing solutions (NaCl+Na2CO3+KCl, NaHCO3+Na2CO3+NaClO4, etc.), and multi-component synthetic brines relevant to the WIPP.

Keywords

actinidegeologicwaste management
Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 1265: Symposium AA – Scientific Basis for Nuclear Waste Management XXXIV , 2010 , 1265-AA01-03
Copyright
Copyright © Materials Research Society 2010

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References

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