Sensitivity Analyses for Total-System Performance Assessment
As a follow-on to Sandia's 1991 preliminary total-system performance assessment of the Yuc1ca Mountain site, this paper presents results of some sensitivity analyses that were done using...
The Development of the CRWMS Transportation System
The Transportation System of the Civilian Radioactive Waste Management System (CRWMS) is being developed using a system engineering approach to ensure it is properly integrated into the...
Development of the Planning and Control Segment, CRWMS Transportation System
This paper discusses the current plans for the development of the Planning and Control segment of the SRWMS Transportation System. Each of the four Planning and Control subsystems are...
Development of the Service & Maintenance Segment of the Transportation System
This paper discusses the progress to date in establishing the Service and Maintenance Segment of the Transportation System required to maintain the equipment required to transport spent...
Development of the Field Operations and Carrier Segments, CRWMS Transportation System
This paper discusses the current status and plans for the development of the Field Operations and Carriage segments of the Transportation System of the Civilian Radioactive Waste Management...
Site and Facility Waste Transportation Planning Documents (SPDs): Status and Findings
Site and Facility Waste Transportation Services Planning Documents (SPDs) are detailed desk-top reference documents that initiate planning for shipping commercial spent nuclear fuel (SNF)...
IAEA Activities in Long-Term Storage of Spent Fuel
According to its Statute, one of the main goals of the International Atomic Energy Agency (IAEA) is to accelerate and enlarge the contribution of Atomic Agency to peace, health and prosperity...
The Long Term Interim Storage of Spent AGR Fuel
This paper describes the work undertaken by Scottish Nuclear Ltd. on the proposal to construct a naturally cooled dry store for spent advanced gas cooled reactor fuel at Tornes Power Station,...
Interim Dry Storage of CANDU Fuel
The Canadian approach to permanent disposal of used CANDU fuel is directed toward its storage in suitable containers emplaced into an underground, stable, plutonic rock formation. Reprocessing...
Spent Fuel Interim Storage: French Experience with Dry Vaults
This paper explains the main criteria which are applied as well as measures taken to preserve cladding integrity for the foreseen duration of storage. It discusses in detail the double...
Cask Storage Verification Test?Full Scale Test
In Japan, the cask-storage method of spent fuel will be licensed in the near future and the related R&D works (partly of the Japanese Government have been carried out mainly by...
Hanford Waste Vitrification Project Overview and Status
The Hanford Waste Vitrification Project (HWVP) is being constructed at the U.S. Department of Energy's Hanford Site in Richland, Washington. The paper gives an overview of the HWVP which...
Human Factors Engineering Program Plan for the Hanford Waste Vitrification Plant
The paper describes the overall human factors program plan while providing more specific information regarding the critical areas of criteria development, dispersed control areas and key...
The Impact of Safety Analyses on the Design of the HWVP Vitrification Plant
Accident analyses are being performed to evaluate and document the safety of the Hanford Waste Vitrification Plant (HWVP). The effects of worst-case accident scenarios are evaluated by...
Rainfall and Net Infiltration Probabilities for Future Climate Conditions at Yucca Mountain
Performance assessment of repository integrity is a task rendered difficult because it requires predicting the future. This challenge has occupied many scientists who realize that the...
The Influence of Seasonal Climatic Variability on Shallow Infiltration at Yucca Mountain
To analyze infiltration and the redistribution of moisture in alluvial deposits at Yucca Mountain, water content profiles at a 13.5 m deep borehole were measured at monthly intervals using...
Using Environmental Tracers to Estimate Recharge Through an Arid Basin
Multiple tracer techniques were used to estimate recharge rates through unsaturated alluvium beneath the Greater Confinement Disposal site, a waste disposal site located in Frenchman Flat,...
The Most Likely Groundwater Flux Through the Unsaturated Tuff Matrix at USW H-1
Using a probabilistic inverse method, an estimate is made of the groundwater flux through the unsaturated tuff matrix at drill hole USW H-1 in Yucca Mountain. The most likely flux is found...
The Influence of Long Term Climate Change on Net Infiltration at Yucca Mountain, Nevada
Net infiltration and recharge at Yucca Mountain, Nevada, a potential site for a high level nuclear waste repository, are determined both by the rock properties and past and future changes...
Congressional-Executive Interaction and the Nuclear Waste Repository Site Selection Process
The Nuclear Waste Policy Act of 1982 (NWPA) (P.L. 97-425) and the Nuclear Waste Policy Amendments Act of 1987 (NWPAA) (Title V of P.L. 100-203) provide the framework for the Department...
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