Nuclear Fuel Waste Disposal: The Canadian Consultative Approach
Over the past two decades society has demanded more public participation and public input into decision-making by governments. Accordingly, development of the Canadian concept for deep...

An Inverse Procedure for Estimating the Unsaturated Hydraulic Conductivities of Volcanic Tuffs
A procedure is developed for estimating the hydraulic conductivity function of unsaturated volcanic tuff, using measurements of the sorptivity and capillary pressure functions. The method...

Scale Dependence of Effective Media Properties
For problems where media properties are measured at one scale and applied at another, scaling laws or models must be used in order to define effective properties at the scale of interest....

Scenario Development for Safety Demonstration for Deep Geological Disposal in Switzerland
A scenario development procedure has been developed that is appropriate to the safety assessment approach chosen by Nagra and to the Swiss regulatory requirements. The procedure is seen...

A Working Definition of Scenario and a Method of Scenario Construction
The event-tree method of scenario construction has been chosen for the Yucca Mountain performance assessment. Its applicability and suitability to the problem are discussed and compared...

Flow and Transport in Hierarchically Fractured Systems
Preliminary results indicate that flow in the saturated zone at Yucca Mountain is controlled by fractures. A current conceptual model assumes that the flow in the fracture system can be...

Modeling Storage Behavior in a Fractured Rock Mass
To represent single bore hole injection tests in fractured rock masses, a transient model has been implemented, based on a three dimensional stochastic description of the fracture network....

Connectivity and the Continuum Approximation in Fracture Flow Modeling
The continuum assumption is frequently made when modeling flow in fractured media. The approach presented in this paper helps evaluating the validity of such an assumption. Two indices...

Radionuclide Transport in Fractured Media
Until recently, the classical advective-dispersive transport equation was considered to be an adequate model for describing the motion of a solute (e.g. radionuclides) in porous and fractured...

Procurement Quality Engineering
The 'Procurement Quality Function' is an element of the Body of Knowledge of Quality Engineering, as defined by the American Society for Quality Control (ASQC). This paper describes the...

The Use of Technical Specialists in Quality Assurance Audits
This paper provides a nontechnical discussion of the use of Technical Specialists in quality assurance audits by the Office of Civilian Radioactive Waste Management's Office of Quality...

Quality-Assurance Program Description Defense Waste Processing Facility
This paper describes the Westinghouse Savannah River Company's (WSRC) quality assurance program for defense-waste processing at the Savannah River Site (SRS). WSRC is the operating contractor...

A Job Performance Aid to Criticality Safety
The handling of hazardous materials is becoming more and more of a major concern to everyone. As a result the laws and restrictions regulating the handling, storage, disposal etc., of...

Perspectives on Out-of-Pool Spent Fuel Storage Requirements 1992-2036
The estimates of requirements for additional storage capacity for spent nuclear fuel from commercial LWRs in the United States are examined in this study. A comparison of this study's...

The MacCSITS Database: A Tool for Curating Samples
Geologic samples are a primary source of data for the Yucca Mountain Site Characterization Project (YMP). The collection and study of the samples is regulated by requirements which mandate...

Disposal of Defense Spent Fuel and HLW from the Idaho Chemical Processing Plant
Acidic high-level radioactive waste (HLW) resulting from fuel reprocessing at the Idaho Chemical Processing Plant (ICPP) for the U. S. Department of Energy (DOE) has been solidified to...

Throughput Rate Study
The Civilian Radioactive Waste Management System (CRWMS) Management and Operating (M&O) Contractor, has completed a study to analyze system wide impacts of operating the CRWMS...

The Effect of Certain Assumptions on the Number and Type of Spent Fuel Casks Required 1998-2000
The Office of Civilian Radioactive Waste Management M&O contractor is determining the number of spent fuel transportation cask systems required to transport fuel from reactors...

Systems Integration and Economic Aspects of the Universal Container System
Universal containers (UC) are multi-assembly spent fuel containers that are loaded and sealed at reactor sites or the first DOE facility. They are thereafter handled as clean containers...

Plutonium and Minor Actinide Transmutation by Long Irradiation in LWR
An investigation was made on the conceptual possibility of burning in a thermal reactor MOX fuel together with special pins containing plutonium, minor actinides and long-lived fission...

 

 

 

 

Return to search