Interpretative Modelling of Studies of Sorption of Radionuclides onto Geological Materials
An integrated modelling and experimental approach related to the quantification of the sorption of radionuclides onto geological materials is described. The primary role of the experimental...
Performance Assessment in Early Phases of the Repository Design Process
Assessments of post-closure performance are an integral part of the design process for a repository for high-level nuclear waste. They provide input to the establishment of design requirements...
Design Considerations for the Yucca Mountain Project Site Characterization
The Site Characterization Facilities (SCF) to be located in volcanic tuff at Yucca Mountain is a challenge to manage, design, and construct. This challenge is a result of a number of factors....
Application of QA Grading to Yucca Mountain Site Characterization Project Items and Activities
Grading is the act of selecting the quality assurance (QA) measures necessary to develop and maintain confidence in the quality of an item or activity. The list of QA measures from which...
Interpretation and Modelling Process of Bedrock Structures for Site Evaluation in Finland
The repository site for the final disposal of spent nuclear fuel in Finland will be selected by the end of the year 2000. Preliminary site investigations have been made in five areas since...
Assessment of Fracture-Sampling Techniques for Laboratory Tests on Core
As part of the site characterization work to be done at Yucca Mountain in Nye County, Nevada, a candidate site for the first mined-geologic repository for high-level nuclear waste, laboratory...
How Much Must the Geologic Barrier Contribute to Safe HLW Disposal?
As a prerequisite of a potential repository site, it is important to assess the role of each system component in providing safety and, in particular, to establish the specific geological...
Yucca Mountain Site Characterization Project Waste Package Plan
The goal of the U.S. Department Of Energy's (DOE) Yucca Mountain Site Characterization Project (YMP) waste package program is to develop, confirm the effectiveness of, and...
Formic Acid Requirement for Savannah River Site Defense Waste Processing Facility Melter Feed Preparation (U)
The Westinghouse Savannah River Company (WSRC) will vitrify the high-level radioactive waste into a borosilicate glass wasteform using a slurry-fed, joule-heated melter. Formic acid is...
How Can we Deal with NIMBY in Nuclear Waste Management?
The effects of the NIMBY Syndrome on the siting of nuclear waste disposal facilities are described, and its causes are examined. The failure of traditional siting approaches and communications...
Nagra's Information Strategy 1991
This paper discusses the acceptance problems faced by nagra, opinion research as a basis for action, the nagra message, transmission measures, communication levels, instruments of communication...
Mineralogic Alteration History and Paleohydrology at Yucca Mountain, Nevada
The importance of paleohydrology to the Yucca Mountain Site Characterization Project derives from the role water will play in radioactive-waste repository performance. Changes in hydrologic...
Radionuclide Migration as a Function of Mineralogy
The migration of radionuclides is studied as a function of mineralogy utilizing batch sorption and column experiments. The transport behavior of alkaline, alkaline-earth, and transition...
Development of Preliminary Nevada Transportation Accident Characteristics
The U.S. Department of Energy (DOE), Yucca Mountain Site Characterization Project Office (YMSCPO) has been given the responsibility for characterization of the potential repository site...
Development of Rail Access to the Proposed Repository Site at Yucca Mountain
In accordance with the Nuclear Waste Policy Amendments Act of 1987, Yucca Mountain was designated as the initial site to be investigated as a potential repository for the disposal of high-level...
Transportation Access to Yucca Mountain: Critical Issues
Transportation planning for a repository at Yucca Mountain is complicated because of uncertainty about the modes and numbers of nuclear waste shipments and because of uncertainty about...
Exclusion of Foreign Materials from the Savannah River Site (SRS) Canistered Waste Forms: Characterization of the Gas within the Free Volume
Glass-filled canisters, produced at the SRS Defense Waste Processing facility, must meet the Waste Acceptance Preliminary Specifications (WAPS) developed by DOE's Office of...
Dry Drilling and Coring Development for Unsaturated Zone Studies
Two areas of major difficulty associated with characterization of any unsaturated zone are the conventional drilling and coring processes used to acquire the samples. These processes are...
Geologic Sample Handling and Logging at Apache Leap, Arizona
Early in 1990, the Yucca Mountain Project Office (Project Office; presently the Yucca Mountain Site Characterization Project Office) of the U.S. Department of Energy (DOE) completed two...
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...
Return to search