Yucca Mountain Site Characterization Project Performance Based Q List
In mid-1992, the Yucca Mountain Site Characterization Project (YMP) initiated a performance based 'Q' List development effort. This effort is intended to evolve a 'Q' List based upon the...
Development of the Office of Civilian Radioactive Waste Management's Self-Assessment Program
This paper describes the development and implementation of the Self-Assessment (SA) Program of the Office of Civilian Radioactive Waste Management (RW). The basis for RW's SA program is...
Application of Quality Assurance to Site Characterization
Siting studies for nuclear power plants are conducted for the purpose of determining the suitability of the site (a natural system) on plant systems that prevent the release of radioactive...
Potential Nuclear Material Safeguards Applied to the Department of Energy's Civilian Radioactive Waste Management System
The Office of Civilian Radioactive Waste Management (OCRWM) within the U.S. Department of Energy is charged with the responsibility of safe and efficient disposal of this Nation's civilian...
Safeguards Issues of Radioactive Wastes at DOE Sites
Radioactive waste management is not regarded as a safeguard-sensitive step in the nuclear fuel cycle. However, the accumulation of large amounts of fissile materials in wastes over a period...
Safeguards and Security Issues at the MRS Facility
The U.S. Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM) is responsible for disposing of the nation's high level radioactive waste in a way that ensures...
Borehole Security on the Yucca Mountain Project
A borehole security plan was developed and is being implemented to address safety, environmental protection and restoration, waste isolation, and security concerns related to boreholes...
Safety Envelope Input: Nuclear Facility Isotopic Content (NFIC) Management System
The Westinghouse Savannah River Company (WSRC) is aggressively applying environmental remediation and radioactive waste management activities at the U. S. Department of Energy's (DOE)...
Cost and Schedule Baseline Management in the OCRWM Program
The Department of Energy's Office of Civilian Radioactive Waste Management has established a baseline change control system to support their program control system. The program control...
The Independent Cost Estimating Process
The United States Department of Energy (DOE) requires that an Independent Cost Estimate (ICE) be prepared for all Major Systems Acquisitions (MSAs); that is, projects or programs expected...
Managing the Nuclear Waste Fund
Through September 30, 1992, the Nuclear Waste Fund had received $5.8 billion in fee payments, earned $1.5 billion in interest, and disbursed $3.4 billion. The book value of investments...
Financing the Canadian Nuclear Fuel Waste Disposal Concept
This paper describes an approach to the financial analysis of the Canadian concept for the disposal of high-level nuclear fuel waste. The work was conducted on behalf of Environment Canada...
Factors Affecting Performance of Vitrified Wasteforms
The acceptability and usefulness of mathematical models for predicting the performance of vitrified wasteforms can be enhanced by their validation using laboratory data generated under...
Evaluation of Borosilicate Glass as a High-Level Radioactive Waste Form
The choice of a borosilicate glass as a high-level nuclear waste form is evaluated base on observations of natural and artifical glass hydration and reaction, experimental results of glass...
The Effect of Gamma Irradiation on the Volatility and Redox State of Simulated DWPF High-Level Nuclear Waste Glasses
Gamma-induced volatility of simulated DWPF high-level nuclear waste glasses is highly dependent upon the redox state of the glass. For oxidized glasses with an Fe2+/(Fe2+...
Hanford Ferrocyanide Reactivity: Effects of Other Tank Constituents
In this study simulated wastes were used to determine the effect of potential waste constituents on the reactivity and explosivity of Hanford ferrocyanide-bearing wastes. Test results...
Corrosion Life-Time Assessment of Carbon Steel and Stainless Alloys for Geological Disposal Facility
The disposal facility for radioactive wastes, requires long-term integrity. Metal is considering to use as the engineered barrier which constructs the outer walls in such a facility, in...
Localized Corrosion Prediction for Nuclear Waste Disposal Container Materials
When the bentonite is used in the geological disposal of high-level wastes as a buffer material to stand between containers and host rocks, thereby turning the pH of the groundwater slightly...
A Numerical Analysis of Spent Nuclear Fuel Thermal Characteristics
A numerical analysis is presented comparing the thermal behavior of a spent boiling water reactor fuel pin and an electric heating element intended to simulate the fuel pin in an experimental...
Heat Transfer in Vertical Concentric Cylinders in a High Level Nuclear Waste Repository
Modeling free convection heat transfer in an cylindrical annular enclosure is still an active area of research and an important problem to be addressed in the high level nuclear waste...
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