The Effect of Compaction on Buried Flexible Pipes
This contribution presents an analysis of the installation of flexible pipes in granular soil. The deformation of the pipe cross section is measured in field and laboratory tests. It is...
A Proposed Methodology for Validating Performance Assessment Models for the DOE Office of Civilian Radioactive Waste Management Program
The Department of Energy (DOE) has developed a draft methodology for validating performance assessment models that will be used in the licensing of high-level waste repository systems....
Dry Spent Fuel Storage Compatibility at the Back End of the Fuel Cycle
The U.S. Nuclear Regulatory Commission (NRC) has publicly called for dry storage designs to be compatible with the back end of the fuel cycle, to achieve overall fuel cycle efficiency....
TN28V High Capacity Cask for the Transport and Storage of Vitrified Wastes
When the option of reprocessing has been selected, closing of the fuel cycle implies the return shipment of reprocessing wastes back to the country of origin of the spent fuel, in particular...
A Numerical Study of Some Effects of Nuclear Fuel Waste Vault Construction and Closure on Evolution of Groundwater Flow Paths in the Geosphere
We have performed a series of three dimensional finite-element simulations on the sensitivity of the groundwater flow paths and travel times in a conceptual hydrogeological model with...
A Stratified Percolation Model for Saturated and Unsaturated Flow Through Natural Fractures
The geometry of the asperities of contact between the two surfaces of a fracture and of the adjacent void spaces determines fluid flow through a fracture and the mechanical deformation...
The Analysis of Horizontal Cooling Enhancement for Nuclear Waste Container Emplacement
This paper presents a novel method for distributing the heat generated by waste containers emplaced in the proposed high-level nuclear waste site at Yucca Mountain, Nevada. The method...
Optimization Method for Dimensioning a Geological HLW Waste Repository
This method was developed by the CEA to optimize the dimensions of a geological repository by taking account of technical and economic parameters. It involves optimizing radioactive waste...
Trends in Waste Management Program Costs: An Evolution of Estimating Methods and Results
The purpose of this paper is to present a summary of how the program cost projections contained in the five TSLCC analyses performed to-date and the estimating methods used to make these...
Experience with Certifying Borated Stainless Steel as a Shipping Cask Basket Material
The original cask designs for a cask demonstration project featured fuel baskets constructed of borated stainless steel (bss) as a structural material. The project is intended to demonstrate...
Application of Geophysical Methods for Fracture Characterization
One of the most crucial needs in the design and implementation of an underground waste isolation facility is a reliable method for the detection and characterization of fractures in zones...
Dispute Resolution ? A New Approach for Public Acceptance of the High-Level Radioactive Waste Mamagement Regulatory System
This paper examines the feasibility of utilizing Dispute Resolution to significantly reduce the numbers of technical disputes subject to litigation in civil courts or before the NRC to...
The Public Consultation Program on Nuclear Fuel Waste Management in Canada
Atomic Energy of Canada Limited has conducted a public consultation program (PCP) with public interest groups broadly representative of Canadian society to identify the issues of public...
Beyond NEPA: A Look at Socioeconomic Impact Assessments Required Under the Nuclear Waste Policy Act, as Amended
The Department of Energy's Office of Civilian Radioactive Waste Management (OCRWM) has been charged by Congress, through the Nuclear Waste Policy Act, as amended (the Act),...
Spent Fuel Storage Requirements for Nuclear Utilities and OCRWM
Projected spent fuel generation at U.S. power reactors exceeds estimated aggregate pool storage capacity by approximately 30,000 metric tons of uranium (MTU). Based on the current repository...
Site Selection Criteria for Constructing an Independent Spent Fuel Storage Installation (ISFSI) at a Commercial Nuclear Power Plant
Commercial nuclear power plants in the U.S. are responsible for providing their own interim storage for excess spent fuel. A facility located onsite, acting as a buffer between in-pool...
Choosing AT-Reactor Spent Fuel Storage Technologies
Need for expansion of the spent fuel storage capability of reactor sites was first caused by delays in construction of reprocessing facilities, later by cessation of commercial reprocessing...
Concrete Cask Storage Technology
The paper presents the design and operation of the new dry storage system for nuclear waste. The system was designed by complete nuclear, thermal-hydraulic and structural analysis to the...
Size and Transportation Capabilities of the Existing U.S. Cask Fleet
This study investigates the current spent nuclear fuel cask fleet capability in the United States. In addition, it assesses the degree to which the current fleet would be available, as...
Assuring Data Quality for Use in Waste Management System Trade-Off Studies
This paper details the systems engineering approach developed to ensure the integrity of a large data library throughout its development and application. The paper assesses the benefits...
Return to search