A Computer-Generated Film of Repository Operations
For the past fifteen years, the same types of questions concerning nuclear waste repository operations have kept coming up over and over again. What should be the average throughput for...
TVO-92 Safety Analysis of Spent Fuel Disposal
Spent fuel from the TVO I and TVO II reactors is planned to be disposed of in a repository to be constructed at a depth of about 500 meters in crystalline bedrock. The fuel will be encapsulated...
Radionuclide Migration to the Aquifer Through the Porous Medium
Time dependent doses of radionuclides from a waste container to the aquifer through porous medium are analyzed for (1) congruently released transuranic elements such as Np-237 and (2)...
Modeling Gas and Brine Migration for Assessing Compliance of the WIPP
The U.S. Department of Energy (DOE) is developing the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico as a facility for the long-term disposal of defense-related transuranic...
Results from the Second Performance Assessment Iteration for the Greater Confinement Disposal Facility
The Greater Confinement Disposal (GCD) facility was established by the Nevada office of the Department of Energy (DOE) in Area 5 at the Nevada Test Site for containment of waste inappropriate...
Groundwater Impacts of Foreseeable Human Activities on a HLW Repository
The Nuclear Regulatory Commission (NRC) staff has begun a program of Systematic Regulatory Analysis (SRA) to help ensure that all important technical issues related to the disposal of...
The Impact of Using Reduced-Capacity Baskets on Cask Fleet Size and Cask Fleet Mix
The Civilian Radioactive Waste Management System transportation system will encounter a wide range of spent fuel characteristics. Since the Initiative I casks are being designed to transport...
Impact of More Conservative Cask Designs on the CRWMS Transportation System
The Office of Civilian Radioactive Waste Management has been working since the mid-1980s to develop a cask fleet, which will include legal weight truck and rail/barge casks, for the transport...
The DOE Tansportation Management Division's Motor Carrier Evaluation Program
The movement of hazardous materials and wastes over the nation's highways by commercial motor carriers presents a challenge for the purchaser of transportation services. During the next...
Marginal Overweight Operating Scenario for DOE's Initiative I Highway Casks
This paper assesses the potential transport of high-capacity Initiative I highway casks under development by the Office of Civilian Radioactive Waste Management (OCRWM) as permitted marginal...
A Note on Physical Modeling Approach for Assessment of Excavation Techniques
With the growing interest in utilizing underground space, the need for quantitative and qualitative assessment of excavation techniques to dictate the best choice for mining is now becoming...
Selection of the Initial Access for the Yucca Mountain Exploratory Studies Facility
This paper describes the activities undertaken to examine relevant factors and select the initial access for the Yucca Mountain exploratory studies facility. To aid their decision, the...
Application of Monte Carlo Neutron Photon to Hanford Waste Vitrification Plant Design Analysis
The Monte Carlo Neutron Photon (MCNP) computer program ('MNCP - A General Monte Carlo Code for Neutron and Photon Transport, Version 3A') (in PC and mainframe versions) has been used for...
Installation and Routing of Critical Embedments at the Hanford Waste Vitrification Plant
During the preliminary design phase of the project, a study was conducted to develop concepts for routing embedded piping and conduit between the remote cells and the service corridors...
Glass Melter Assembly for the Hanford Waste Vitrification Plant
The Hanford Waste Vitrification Plant (HWVP) is designed to solidify high level radioactive waste by converting it into stable borosilicate glass after mixing with glass frit and water....
Mechanical Design of the Storage Tubes in the HWVP Canister Storage Building
Canisters of high-level waste from the Hanford Waste Vitrification Plant (HWVP) will be stored in an adjacent facility, the Canister Storage Building (CSB). The canisters are stored vertically...
Investigation of Fracture-Matrix Interaction: Preliminary Experiments in a Simple System
Paramount to the modeling of unsaturated flow and transport through fractured porous media is a clear understanding of the processes controlling fracture-matrix interaction. As a first...
Testing Models of Flow and Transport in Unsaturated Porous Media
The design of an intermediate-scale flow and transport experiment in an unsaturated porous media is described. This experiment will be conducted a 3-m-diameter by 6-m-long caisson filled...
Preliminary Characterization of Materials for a Reactive Transport Model Validation Experiment
The geochemical properties of a porous sand and several tracers (Ni, Br, and Li) have been characterized for use in a caisson experiment designed to validate sorption models used in models...
Finnsjon Site (Sweden)?Interpretation of Interference Tests
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