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Field Investigations for Seismic Effects on Mechanical and Geohydrologic Response of Underground Structures in Jointed Rock
An exploratory Seismic Rock Mechanics research program has been initiated by the U.S. Nuclear Regulatory Commission at the Center for Nuclear Waste Regulatory Analyses (CNWRA) to study...

Boundary Integral Methods for Unsaturated Flow
A boundary integral equation method (BIEM) is described for numerical analysis of quasilinear steady unsaturated flow in homogeneous material. The applicability of the exponential model...

Analysis of Solute Transport in an Intermediate-Scale Unsaturated Flow Experiment
A simplified stochastic model was derived and applied to two unsaturated flow experiments conducted in an intermediate-scale caisson. Parameters for the flow and transport models were...

Theory of Matrix and Fracture Flow Regimes in Unsaturated, Fractured Porous Media
The flow behavior of a two-dimensional, unsaturated fracture-matrix system is characterized by a critical flux q_f^*...

Effect of a Low-Permeability Layer on Calculated Gas Flow at Yucca Mountain
Yucca Mountain is being studied to determine its suitability as a location for a high-level nuclear waste repository. The mountain is a steep-sided linear ridge which is underlain by a...

Performance Assessment: The Bridge Between Regulatory Decision-Making and Scientific Uncertainties
NRC has the responsibility for evaluating the license application for a repository against the regulations it has promulgated. Performance assessment is the bridge between regulatory decision-making...

Key Scientific Issues for Near-Field Performance Assessment
This paper reviews key scientific issues related to the performance assessment of engineered barrier systems. In contrast to the inherent uncertainties associated with inhomogeneous geologic...

Advances in the Study of Far-Field Phenomena Affecting Repository Performance
Studies of far-field phenomena affecting repository performance have focussed on the role of fractures and other heterogeneities in the potential transport of radioactive solutes from...

Process and Criteria for Valuation of the Ground-Water Flow Models in the OECD/NEA International Stripa Project
In 1986, the Site Characterization and Validation (SCV) Program was initiated as part of Phase III of the OECD/NEA International Stripa Project. The principal intent of the SCV Program...

Some Conclusions from a Biospheric Model Validation Study (BIOMOVS)
BIOMOVS (BIOspheric MOdel Validation Study) is an international co-operative effort to test biospheric models designed to calculate the environmental transfer and bioaccumulation of radionuclides...

Demonstration of a Repository Performance Assessment Capability at the U.S. Nuclear Regulatory Commission
In order to better review licensing submittals for a High-Level Waste Repository, the U.S. Nuclear Regulatory Commission staff has expanded and improved its capability to conduct performance...

Monitoring Compliance with Requirements During Site Characterization
The question of when a program of Regulatory Compliance should be applied and what it should be applied to, when the subject of compliance is a High Level Radioactive Waste Repository,...

Regulatory Requirements and Long-Term Repository Host Rock Performance
The regulatory requirements governing the disposal of high-level radioactive wastes in mined geologic repositories acknowledge the long-lived nature of the wastes and require the consideration...

Test and Evaluation of Natural Barriers at Yucca Mountain, Nevada: Management of the Site Characterization Program
The U.S. Department of Energy (DOE) is responsible for managing a characterization program for the Yucca Mountain site to collect data needed to determine if the site is suitable for recommendation...

Degradation Mode Surveys of High Performance Candidate Container Materials
Corrosion resistant materials are being considered for the metallic barrier of the Yucca Mountain Project's high-level radioactive waste disposal containers. Nickel-chromium-molybdenum...

An Electrochemical Approach to Predicting Corrosion Performance of Container Materials
The pitting potentials of nickel-rich Alloy 825 are measured in chloride-containing solutions at different temperatures and adjusted to different pH values. The pitting potentials were...

Potential Uses of Lead in Nuclear Waste Disposal
In order for lead to be considered as a nuclear waste packaging material, it must be shown that it has adequate corrosion resistance, and that it does not degrade the properties of other...

Modelling Studies for the Assessment of the Advanced Cold Process Canister
The Advanced Cold Process Canister (ACPC) is a new concept for the encapsulation of spent nuclear fuel for geological disposal. It consists of steel canister encased in a copper overpack....

Activities Aimed at Qualification of a HLW Disposal Container
A container is being developed for the permanent disposal of used fuel from CANDU nuclear reactors in a deep underground disposal vault. The container is required to isolate the fuel from...

Future Supply of, and Demand for, Titanium, Copper and Lead
A literature survey has been conducted to assess the future world supply of, and demand for, titanium, copper and lead. These metals are candidates for the fabrication of containers for...

 

 

 

 

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