Yucca Mountain Near Field Environment Considerations for Engineered Barrier System Design and Performance
Waste emplacement environment will be essentially dry for at least 300 years and will likely continue to be dry for more than 1000 years, both as a result of the unsaturated ambient conditions...
An Analysis of Buffering in Bentonite-Groundwater Systems
Chemical buffering by bentonite can potentially simplify assessments of the performance of engineered barriers to radionuclide migration by decoupling near-field and far-field geochemical...
Isotopic Discontinuities in Ground Water Beneath Yucca Mountain, Nevada
Analytical data for stable isotopes in ground water from beneath Yucca Mountain, when examined in map view, show areal patterns of heterogeneity that can be interpreted in terms of mixing...
Distribution of Rubidium, Strontium, and Zirconium in Tuff From Two Deep Coreholes at Yucca Mountain, Nevada
Variations in concentrations of trace elements Rb, Sr, and Zr within the sequence of high-silica tuff and dacitic lava beneath Yucca Mountain reflect both primary composition and secondary...
General Circulation Models: Applications for Nuclear Waste Repositories
Numerical models have long been used to relate causal and response functions in the natural environment. Some 20 years ago, one-dimensional, multi-causal models of earth temperature evolved,...
Characterization Uncertainty and its Effects on Models and Performance
Geostatistical simulation is being used to develop multiple geologic models of rock properties at the proposed Yucca Mountain repository site. Because each replicate model contains the...
Transportation Capabilities of the Existing Cask Fleet
This paper describes a number of scenarios estimating the amount of spent nuclear fuel that could be transported to a Monitored Retrievable Storage (MRS) Facility by various combinations...
A Preliminary Evaluation of the Ability of From-Reactor Casks to Geometrically Accommodate Commercial LWR Spent Nuclear Fuel
The Department of Energy has sponsored a number of cask design efforts to define several transportation casks to accommodate the various assemblies expected to be accepted by the Federal...
The Radiological Capacity of Transport Casks Loaded in a 2-Region Non-Uniform Pattern
The radiological capacity of spent fuel storage and transport casks can be increased by the use of non-uniform cask loading. There are many possible combinations of spent fuel burnup and...
Some Political Logistics of Nuclear Waste
The need for a centralized, federal, interim storage facility for nuclear waste, or MRS, alledgedly has become more urgent because the date for the opening of the permanent repository...
The Constructive Use of Heat in an Unsaturated Tuff Repository
By designing the engineered barrier system in an unsaturated tuff repository to constructively use heat, the waste containers can be kept dry for hundreds of years. Without water, the...
Recent Development in the Design of Hard Rock Tunnel Boring Machines for the Mining Industry
Underground development for nuclear waste storage will possibly require tunnels to be excavated in a variety of rock conditions and configurations. Recent innovations in Tunnel Boring...
Dry Spent Fuel Storage in the 1990's
In the United States, for the decade of the 1990's, at-reactor-site dry spent fuel storage has become the predominant option outside of reactor spent fuel pools. This development...
A Proposed Regulatory Guide Basis for Spent Fuel Decay Heat
A proposed revision to Regulatory Guide 3.54, 'Spent Fuel Heat Generation in an Independent Spent Fuel Storage Installation' has been developed for the U.S. Nuclear...
Evaluation of Storage/Transportation Options to Support Criteria Development for the Phase I MRS
The Department of Energy's (DOE) Office of Civilian Waste Management (OCRWM) plans to develop an interim storage facility to enable acceptance of spent fuel in 1998. It is...
Interim Storage of Solidified High Level Wastes
Indian approach to the problem of interim storage of vitrified high level wastes, indicating design philosophy adopted for air cooled vault at Tarapur has been described. Important design...
Interim Waste Storage for the Integral Fast Reactor Fuel Cycle Demonstration
An interim storage system design and operating strategy were developed for implementation in the Integral Fast Reactor Fuel Cycle Demonstration. Waste characteristics and thermal power...
A Decision Support System for Performance-Based Site Characterization
The complex and dynamic requirements of site characterization present a major management challenge. ParaTrac, a regulatory and technical information system, is described as a valuable...
Site-Generic Approach for Performance Assessment of HLW Disposal System in Japan
This paper presents an overview of the preliminary performance analyses and description of R&D activities designed based upon the results of the analyses, which are to be incorporated...
Fear of Trying
Conventional methods for cleaning up hazardous-waste sites are expensive, subject to increasing restrictions, and don't work that well for certain types of waste. Innovative...
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