Development, Application, and Evaluation of a Methodology to Estimate Distributed Slip on Fractures due to Future Earthquakes for Nuclear Waste Repository Performance Assessment

2002 ◽  
Vol 92 (3) ◽  
pp. 923-944 ◽  
Author(s):  
P. R. La Pointe
Keyword(s):  
Performance Assessment ◽  
Nuclear Waste ◽  
Nuclear Waste Repository ◽  
Waste Repository ◽  
Development Application

Stability constants of uranium(IV)-α-isosaccharinic acid and gluconic acid complexes

2004 ◽  
Vol 92 (12) ◽  
Author(s):  
Peter Warwick ◽  
Nick Evans ◽  
Tony Hall ◽  
Sarah Vines
Keyword(s):  
Performance Assessment ◽  
Stability Constants ◽  
Nuclear Waste ◽  
Gluconic Acid ◽  
Solubility Product ◽  
Nuclear Waste Repository ◽  
Waste Repository ◽  
Isosaccharinic Acid

SummaryConditional and pH independent stability constants have been determined for U(IV) α-isosaccharinic acid (ISA) and gluconic acid (Gl) complexes, under anaerobic and carbonate-free conditions, from pH 3 to 14. The constants are needed for nuclear waste repository performance assessment purposes. The constants were obtained by developing an approach based on the solubility product of amorphous UO

The Solubility Limited Source Term for Cement - Conditioned Wastes: A Status Report

1999 ◽  
Vol 556 ◽  
Author(s):  
F. P. Glasser
Keyword(s):  
Performance Assessment ◽  
Nuclear Waste ◽  
Thermodynamic Functions ◽  
Experimental Work ◽  
Source Term ◽  
Status Report ◽  
Nuclear Waste Repository ◽  
Nickel Chromium ◽  
Quantitative Performance ◽  
Waste Repository

AbstactAn important function of the cement backfill in a nuclear waste repository is to react with aqueous waste species and reduce their solubility. However, to quantify backfill performance it is first necessary to prove the existence and establish the nature of the chemical solubility controls. This can be done by characterising the solubility-limiting phases, determining their solubility and thermodynamic functions, and assessing their stability and persistence and solubility during backfill degradation. Much of the necessary data must be acquired experimentally. The title paper describes briefly the progresss of experimental work on selected species including nickel, chromium(III,VI), tin(IV) molybdenum(VI), uranium(VI), Ce(III,IV), thorium, actinide simulants (III, IV) and chloride. Data needs are assessed and although much experimental work remains to be done, methodologies have been developed which will expedite progress. The expectation of a more quantitative performance assessment of cement barriers is, therefore, attainable.

Isotope-Based Analysis of Nuclear Waste Repository Performance

2010 ◽  
Author(s):  
Joosep Pata ◽  
Alan H. Tkaczyk
Keyword(s):  
Performance Assessment ◽  
Nuclear Waste ◽  
Fission Products ◽  
Nuclear Waste Repository ◽  
Total System ◽  
Exposed Individual ◽  
Order Of Magnitude ◽  
Waste Repository ◽  
And Performance ◽  
High Level

It is necessary to consider the complexities of both natural and engineered components of a nuclear waste repository since fission products and minor actinides remain harmful to the environment for tens of thousands of years. In safety and performance assessments often used in decision-making about repository designs, the effect of uncertain initial guesses on the models’ output must be understood. As the necessary safe times and hence the simulated times are often in the order of magnitude of hundreds of thousands of years, uncertain initial values become increasingly important. To minimize the danger from high-level radioactive waste and to make informed decisions over designs, sensitivity analysis of the models used should be performed. The Simplified Total System Performance Assessment (STSPA) model developed by Golder Associates Inc., Booz-Allen Hamilton, Stone and Webster and the University of Nevada Reno and used in the Yucca Mountain nuclear waste repository performance assessment is analyzed for sensitivity by varying the activities of technetium-99 and iodine-129 by several orders of magnitude. The resultant dose to a maximally-exposed individual over time periods of 100,000 and 1,000,000 years is compared to the relevant regulatory limits. Incorrect estimates can be seen to have large effects on the behavior of the model while the method used allows conclusions to be drawn about the robustness of the model.

Chemical, Physical and Engineering Characterization Of Candidate Backfill Clays and Clay Admixtures for a Nuclear Waste Respository-Part I

1981 ◽  
Vol 6 ◽  
Author(s):  
Sudesh K. Singh
Keyword(s):  
Nuclear Waste ◽  
Morphological Changes ◽  
Deionized Water ◽  
Engineering Properties ◽  
Nuclear Waste Repository ◽  
Exchange Cation ◽  
Mineral Components ◽  
Waste Repository ◽  
Mineralogical Compositions

ABSTRACTFourteen Canadian clays and clay admixtures were subjected to simulated nuclear waste repository environments. The present work is concerned with the montmorillonite-dominant materials only. The montmorillonite-dominant samples showed significant leaching on interaction with deionized water. On heating the samples at 200°C for 500 hours, montmorillomites lost intermicellar water completely and acquired cusp-like to cylindrical morphologies. The loss of water and the morphological changes in montmorillonites significantly altered the engineering characteristics. Permeability, shrinkage limits, compactability and shear strength varied in response to the dominant exchange cation in the structure of montmorillonites and the presence of other mineral components in the materials. The synthetic granite water reacted with montmorillonites and led to changes in chemical and mineralogical compositions, crystalline state and engineering properties.

Modelling of thermal rock mass properties at the potential sites of a Swedish nuclear waste repository

2009 ◽  
Vol 46 (6) ◽  
pp. 1042-1054 ◽  
Author(s):  
Jan Sundberg ◽  
Pär-Erik Back ◽  
Rolf Christiansson ◽  
Harald Hökmark ◽  
Märta Ländell ◽  
...  
Keyword(s):  
Rock Mass ◽  
Nuclear Waste ◽  
Nuclear Waste Repository ◽  
Rock Mass Properties ◽  
Mass Properties ◽  
Waste Repository
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