Development of Rail Access to the Yucca Mountain Site: Technical and Publc Issues
The Yucca Mountain site, located on the southwestern edge of the Nevada Test Site (NTS), is an undeveloped area under investigation as a potential site for high-level nuclear waste (HLW)...
Selecting Preferred Routes for Highway Route Controlled Quantity Shipments of Radioactive Materials
The amount of spent nuclear fuel move in the U.S. in recent years has increased due to a number of government actions. One such action was the passage of the Nuclear Waste Policy Act which...
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...
The SKI Regulatory Strategy and Performance Assessment Program in Relation to Final Disposal of Spent Nuclear Fuel and High Level Radioactive Waste
Important steps are planned to be made during the 1990s in the Swedish program for final disposal of spent nuclear fuel and high level radioactive wastes. Site selection will be done in...
PAGIS & PACOMA: Performance Evaluations of Deep Geological Disposal. Results and Conclusions
Two coordinated research projects were undertaken by the Commission of the European Communities to study the safety performances of geological radwaste disposal systems in the post-operational...
Outline of Performance Assessment Study on Geological Isolation System in Japan
The goals of current R&D activities are to ensure the feasibility of geological isolation of HLW in Japan and then to establish the social acceptance. In order to attain these...
Nagra Performance Assessment of Radioactive Waste Disposal in Crystalline and Sedimentaly Host Rocks
Nagra has evaluated disposal of vitrified HLW in both the crystalline basement of Northern Switzerland and in overlying argillaceous sedimentary formations. Although indicating that both...
Performance Assessment at the NRC: Current Issues and Recent Progress
Performance assessment plays a major role in the NRC's licensing program for the disposal of high-level radioactive waste. Planned and recent performance assessment activities...
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....
Initiating Event Identification and Screening for Nuclear Waste Repository Preclosure Risk Assessment
This paper describes a method to identify potential initiating events that might occur during the preclosure phase at a nuclear waste repository proposed for the Yucca Mountain area of...
Preclosure Safety Analysis for a Prospective Yucca Mountain Conceptual Design Repository
A preliminary probabilistic risk assessment was performed for the prospective Yucca Mountain conceptual design repository. A new methodology to quantify radioactive source terms was developed...
Status of Integrated Performance Assessment of the Waste Packages and Engineered Barrier System
Performance assessment of the engineered barrier system for a nuclear waste repository combines information from relevant disciplines and predicts the net long-term performance of the...
Mass-Transfer Analysis of Waste Packages Containing Defense Waste Processing Facility Glass as a Waste Form
The fractional release rates of selected radionuclides from waste packages containing Defense Waste Processing Facility (DWPF) glass are calculated using the AREST code, assuming a continuous-diffusive...
Diffusion Barrier Transport Properties of Unsaturated Paintbrush Tuff Rubble Backfill
Diffusion coefficients (D) were experimentally determined in unsaturated tuff gravel to evaluated the effectiveness of tuff gravel and rubble as a diffusion barrier to ionic transport...
Evaluation of Near-Field Thermal Environmental Conditions for a Spent Fuel Repository in Tuff
A repository heat transfer analysis is being performed by the Pacific Northwest Laboratory (PNL)a for the U.S. Department of Energy's...
Technical Considerations and Approcah for Evaluating Substantially Complete Containment of High-Level Nuclear Waste
The current Federal Regulations, Title 10 Part 60.113(a)(1)(i)(A) require that, for at least 300 years, nuclear waste containment within a waste package shall be substantially complete....
A Gas-Flow Source Term from a Nuclear Waste Container in an Unsaturated Medium
The potential nuclear waste repository at Yucca Mountain is to be in partially saturated rock. Released radioactive gases would have a direct pathway to the biosphere. The entry of air...
?4C Release From Failed Spent Fuel Containers
Partially failed containers may provide a meaningful barrier to the release of gaseous radionuclides. A modeling approach is outlined and sample calculations are provided that show the...
A Waste Package Strategy for Regulatory Compliance
This paper summarizes the strategy given in the Site Characterization Plan (SCP) for demonstrating complicance with the post closure performance objectives for the waste package and the...
Container Material Selection, Modeling and Testing
Virtually all of the approximately 40,000 high-level nuclear wast containers to be emplaced at Yucca Mountain must remain intact for 1,000 years to satisfy Nuclear Regulatory Commission...
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