scholarly journals Climax Granite, Nevada Test Site, as a host for a rock mechanics test facility related to the geologic disposal of high level nuclear wastes

10.2172/59217 ◽  
1981 ◽  
Author(s):  
F.E. Heuze
Keyword(s):  
Rock Mechanics ◽  
Test Site ◽  
Test Facility ◽  
Nuclear Wastes ◽  
Nevada Test Site ◽  
Geologic Disposal ◽  
High Level

Numerical Simulation of Flow and Transport in Fractured Tuff

1983 ◽  
Vol 26 ◽  
Author(s):  
B. J. Travis ◽  
S. W. Hodson ◽  
H. E. Nuttall ◽  
T. L. Cook ◽  
R. S. Rundberg
Keyword(s):  
Numerical Simulation ◽  
Heat Flow ◽  
Radioactive Waste ◽  
Numerical Models ◽  
Test Site ◽  
Yucca Mountain ◽  
Nevada Test Site ◽  
Flow And Transport ◽  
Geologic Storage ◽  
High Level

ABSTRACTThe unsaturated, fractured tuff of Yucca Mountain in the Nevada Test Site is one of the potential sites for geologic storage of high-level radioactive waste. A modeling study of flow and transport in this geologically complex site is presented. Numerical models of mass and heat flow in conjunction with analytical solutions are being used for sensitivity and pathway analysis studies and to aid in design and interpretation of laboratory and field flow and transport tests in tuff.

scholarly journals The Hydrothermal Stability of Cement Sealing Materials in the Potential Yucca Mountain High Level Nuclear Waste Repository

1991 ◽  
Vol 245 ◽  
Author(s):  
J. L. Krumhansl ◽  
T. E. Hinkebein ◽  
J. Myers
Keyword(s):  
Geochemical Modeling ◽  
Test Site ◽  
Cementitious Materials ◽  
Yucca Mountain ◽  
Nuclear Waste Repository ◽  
X Ray Diffraction ◽  
Nevada Test Site ◽  
Post Test ◽  
High Level ◽  
Modeling Code

ABSTRACTCementitious materials, together with other materials, are being considered to seal a potential repository at Yucca Mountain. A concern with cementitious materials is the chemical and mineralogic changes that may occur as these materials age while in contact with local ground waters. A combined theoretical and experimental approach was taken to determine the ability to theoretically predict mineralogic changes. The cementitious material selected for study has a relatively low Ca:Si ratio approaching that of the mineral tobermorite. Samples were treated hydrothermally at 200°C with water similar to that obtained from the J-13 well on the Nevada Test Site. Post-test solutions were analyzed for pH as well as dissolved K, Na, Ca, Al, and Si. Solid phases formed during these experiments were characterized by scanning electron microscopy and X-ray diffraction. These findings were compared with predictions made by the geochemical modeling code EQ3NR/EQ6. It was generally found that there was good agreement between predicted and experimental results.

scholarly journals Insights to Repository Performance through Study of a Nuclear Test Site

2000 ◽  
Vol 663 ◽  
Author(s):  
D.K. Smith ◽  
A.B. Kersting ◽  
J.L. Thompson ◽  
D.L. Finnegan
Keyword(s):  
Tectonic Setting ◽  
Test Site ◽  
Yucca Mountain ◽  
Nuclear Test ◽  
High Level Waste ◽  
Radionuclide Transport ◽  
Source Terms ◽  
Nevada Test Site ◽  
Waste Repository ◽  
High Level

ABSTRACTUnderground nuclear test sites offer an unprecedented opportunity to evaluate processes relevant to high-level waste repository performance in the absence of engineered barriers. Radionuclide migration programs at the Nevada Test Site represent a twenty-five year systematic investigation of the diverse radiologic source terms residual from weapons testing and the evolution of the hydrologic source term which comprises those radionuclides dissolved in or otherwise available for transport by groundwater. The Nevada Test Site shares actinide source terms, correlative geology, an identical tectonic setting, similar climate, and a thick unsaturated zone with the adjacent potential Yucca Mountain high-level waste repository and provides a natural laboratory to assess long-term radionuclide transport in the near field. Analog studies may ultimately help validate predictions of radionuclide transport from the potential Yucca Mountain repository.

The Effects of Carbonate-Bicarbonate Concentration on Empirical Corrosion Diagram of Mild Steel as a Material of Geological Disposal Package for High Level Nuclear Wastes

1996 ◽  
Vol 451 ◽  
Author(s):  
Guen Nakayama ◽  
Yuichi Fukaya ◽  
Masatsune Akashi
Keyword(s):  
Mild Steel ◽  
Human Life ◽  
General Corrosion ◽  
Nuclear Wastes ◽  
Bicarbonate Concentration ◽  
Sulfate Ions ◽  
Geological Disposal ◽  
Groundwater Environment ◽  
High Level ◽  
Corrosion Diagram

ABSTRACTIn the scheme for geological disposal of high level radioactive nuclear wastes, the burial pit is to be isolated from the sphere of human life by a multiple-barrier system, which consists of an artificial barrier, composed of a canister, an overpack and a bentonite cushioning layer, and a natural barrier, which is essentially the bedrock. As the greatest as well as essentially the sole detriment to its integrity would be corrosion by groundwater. The groundwater comes to it seeping through the bentonite zone, thereby attaining conceivably the pH of transition from general corrosion to passivity, pHd, the behaviors of mild steel in such a groundwater environment have been examined. It has been shown that the pHd is lowered (enlargement of the passivity domain) with rising temperature and carbonate-bicarbonate concentration, while it is raised (enlargement of the general corrosion region) with increasing concentrations of chloride and sulfate ions.

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