Optimal Route Selection for High Level Nuclear Waste Transport Based Upon Radiological Risk
The purpose of this paper is to demonstrate route optimization based directly upon the minimization of radiological risk as computed from local conditions. An operational impact analysis...
Optimizing Spent Fuel Cask Designs for Use in the Federal Waste Management System
The DOE will design and develop a new fleet of casks to transport spent fuel using innovative approaches to optimize the cask design. Preliminary casks designs indicate capacity increases...
BR-100 Spent Fuel Shipping Cask Development
Continued public acceptance of commercial nuclear power is contingent to a large degree on the U.S. Department of Energy (DOE) establishing an integrated waste management system for spent...
Systems Engineering Applied to a Regulatory Program
The Nuclear Waste Policy Act directs the Nuclear Regulatory Commission to complete the licensing hearing process for the High-Level Radioactive Waste Geologic Repository within three years,...
Regulatory Considerations for Designing Surface Facilities for Yucca Mountain High-Level Waste Repository
This paper outlines U.S. Nuclear Regulatory Commission's (NRC's) key regulations applicable to U.S. Department of Energy's (DOE's) design...
Defining the Need for and Functions of the Monitored Retrievable Storage (MRS) Facility
A series of system studies of the Civilian Radioactive Waste Management System were conducted by the Department of Energy (DOE) to determine the role for a Monitored Retrievable Waste...
A Demonstration of the Systems Integration Modeling System (SIMS) as a Decision-Support Tool
In April 1989, the Office of Civilian Radioactive Waste Management (OCRWM) Integration Branch completed major demonstration of the Systems Integration Modeling System (SIMS). That system...
Facility Interface Capability Assessment (FICA) Project
The U.S. Department of Energy-Office of Civilian Radioactive Waste Management (DOE-OCRWM) is sponsoring the Facility Interface Capability Assessment Project to determine current and potential...
Acceptance of Spent Fuel of Varying Characteristics
This paper is a preliminary overview of a study with the primary objective of establishing a set of acceptance selection criteria and corresponding spent fuel characteristics to be incorporated...
Materials Selection Issues for Structural Components of Transportation Casks
Sandia National Laboratories (SNL) is evaluating the use of alternate materials (i.e. other than stainless steel) as structural components in nuclear spent fuel transportation casks. This...
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...
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...
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...
Systems Integration During the Development of a Federal Waste Management System
Systems integration in the development of the Federal Waste Management System for spent nuclear fuel and high-level radioactive waste involves not only the activities traditional to development...
Important Factors in Developing a Nuclear Waste Management System
The nuclear waste management system provides unique challenges for a large and diverse segment of our society. For the politician there is the blending of national policy and the interests...
Computed Distributions of Residual Shaft Drilling and Drift Construction Water in the Exploratory Facilities at Yucca Mountain, Nevada
The Yucca Mountain Project is studying the feasibility of constructing a high-level nuclear waste repository at Yucca Mountain in southwest Nevada. One activity of site characterization...
Site Specific Geologic Interpretations of Richton Salt Dome
There have been numerous investigations into the geological and hydrological aspects of the Richton Salt Dome area since its selection as a preferred site for a nuclear waste repository....
Postclosure Safety Assessment of Radioactive Waste Disposal Systems: Current State of Understanding and International Consensus
Approximately ten years have passed since the first comprehensive safety assessments of radioactive waste disposal systems appeared. Through intensive efforts in practically all countries...
Institutional Status, Challenges, and Plans Related to the MRS Program
This paper analyzes the role of institutional considerations in the Monitored Retrievable Storage (MRS) program. Among the issues that will be discussed are: the present focus of the MRS...
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...
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