scholarly journals Incorporating long-term climate change in performance assessment for the Waste Isolation Pilot Plant

1994 ◽  
Author(s):  
P.N. Swift ◽  
B.L. Baker ◽  
K. Economy ◽  
J.W. Garner ◽  
J.C. Helton ◽  
...  
Keyword(s):  
Climate Change ◽  
Performance Assessment ◽  
Pilot Plant ◽  
Waste Isolation Pilot Plant

Influence of Carbonate on Uranium Solubility in the WIPP

2012 ◽  
Vol 1444 ◽  
Author(s):  
Jean-Francois Lucchini ◽  
Sally Ballard ◽  
Hnin Khaing
Keyword(s):  
Performance Assessment ◽  
Pilot Plant ◽  
Solubility Limit ◽  
Experimental Results ◽  
Waste Isolation Pilot Plant ◽  
Long Term Experiments ◽  
Order Of Magnitude ◽  
Carbonate Complexation ◽  
Borate Complexation

ABSTRACTIn the performance assessment (PA) for the Waste Isolation Pilot Plant (WIPP), the solubility of uranium (VI) was conservatively set at 10-3 M for all expected WIPP conditions, including the potential and likely effects of carbonate complexation [1]. Under WIPP-relevant conditions, long-term experiments were performed to establish the uranium (VI) solubility limits in WIPP-simulated brine over a broad range of pCH+ values [7.5-12.5] and to evaluate the contribution of carbonate complexation and hydrolysis to uranium (VI) speciation. Data obtained in carbonate-free ERDA-6 brine, a simulated WIPP brine, were reported earlier [2]. In the absence of carbonate, uranium solubility approached 10-7 M at the expected pCH+ in the WIPP (~ 9.5). In the presence of a significant amount of carbonate (millimole levels), recent experimental results showed that uranium (VI) concentrations will not exceed 10-4M. This measured solubility limit is an order of magnitude lower than the uranium solubility value currently used in the WIPP PA [3]. A small effect of borate complexation was found in the pCH+ range [7.5-10]. At pCH+ ≥ 10, hydrolysis overwhelmed carbonate effects, and no amphoteric effect was observed.

scholarly journals Uranium (VI) Solubility in Carbonate-Free ERDA-6 Brine

2010 ◽  
Vol 1265 ◽  
Author(s):  
Jean-Francois Lucchini ◽  
Hnin Khaing ◽  
Donald T. Reed
Keyword(s):  
Nuclear Waste ◽  
Research Program ◽  
Pilot Plant ◽  
Nuclear Waste Repository ◽  
Ongoing Research ◽  
Waste Isolation Pilot Plant ◽  
Long Term Experiments ◽  
Carbonate Complexation ◽  
Waste Repository

AbstractWhen present, uranium is usually an element of importance in a nuclear waste repository. In the Waste Isolation Pilot Plant (WIPP), uranium is present in significant quantities, with about 647 metric tons to be placed in the repository [1]. Therefore, the chemistry of uranium, and especially its solubility, needs to be determined under WIPP-relevant conditions.Long-term experiments were performed to measure the solubility of uranium (VI) in carbonate-free ERDA-6 brine, a simulated WIPP brine, at pCH+ values between 8 and 12.5. These data, obtained from the over-saturation approach, were the first WIPP repository-relevant data for the VI actinide oxidation state. The solubility trends observed pointed towards low uranium solubility in WIPP brine and a lack of amphotericity. At the expected pCH+ in the WIPP (˜ 9.5), measured uranium solubility approached 10-7 M. The objective of these experiments was to establish a baseline solubility to further investigate the effects of carbonate complexation on uranium solubility in WIPP brines, during the ongoing research program in actinide solubility under WIPP-relevant conditions.

Resolution of the Long-Term Performance Issues at the Waste Isolation Pilot Plant

Risk Analysis ◽  
1999 ◽  
Vol 19 (5) ◽  
pp. 1003-1016 ◽  
Author(s):  
Matthew K. Silva ◽  
Dale F. Rucker ◽  
Lokesh Chaturvedi
Keyword(s):  
Pilot Plant ◽  
Waste Isolation Pilot Plant ◽  
Performance Issues ◽  
Long Term Performance ◽  
Term Performance
Sign in / Sign up

Export Citation Format

Share Document