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...
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...
Educational Programs at Penn State Breazeale Reactor?A Focus on Waste
Discussions about energy policy and issues focus on environmental impact of energy production and the generation of waste. When dealing specifically with nuclear energy, one of the major...
Minds for the Future
Successful long-term implementation of the Office of Civilian Radioactive Waste Management's (OCRWM) program depends on its ability to recruit qualified individuals educated and trained...
High Level Waste Management Research and the University Educational Programs
The University of Florida is one of sixteen qualified University programs participating in the Civilian Radioactive Waste Management fellowship program of the Office of Civilian Radioactive...
Is An Institute for the Study of High-Level Radioactive Waste Disposal Needed in Southern Nevada?
This paper examines key questions about the need for a formal institute that would study storage and disposal concepts for high-level radioactive waste (HLW) in the United States and throughout...
Modelling Gas Migration Experiments in Repository
In response to concerns over the possibility of hydrogen gas generation within an underground repository for high-level radioactive waste, and its implications for repository safety, a...
Carbon Isotopic Data from Test Hole USW UZ-1, Yucca Mountain, Nevada
Rock-CO2-gas analyses in test hole USW UZ-1 at Yucca Mountain indicate that gas movement in the unsaturated zone is likely through a dry-fracture...
Carbon-14: Some Evidence of Migration and Experiments on Immobilisation
Carbon-14 that is produced in nuclear reactors by reactions on C, N and O is one of the most biologically dangerous nuclides that are subject to global dispersion (H-3, 85-Kr, 129-I)....
Diffusion of Carbon Dioxide Through Layers of the Unsaturated Zone at Yucca Mountain
The estimation of diffusive transport of gases through tuffs is important in order to asses the Yucca Mountain as an environmentally safe and acceptable repository for spent fuel and high-level...
The Nagra-DOE Cooperative Project
Tne Nagra-DOE Cooperative (NDC-I) research program was sponsored by the U.S. Department of Energy (DOE) through the Lawrence Berkeley Laboratory (LBL), and the Swiss Nationale Genossenschaft...
Simulation of Fracture Flow to the Kamaishi Validation Drift
The Power Reactor and Nuclear Fuel Development Corporation (PNC) has developed an in-situ test facility in the Kamaishi Mine to resolve technical issues in disposal of radioactive wastes...
Review of International Near-Field Modelling for High-Level Waste Disposal
An international survey and review is being conducted on the latest developments in modelling of near-field performance, with particular emphasis on the conceptual and mathematical models...
AREST: The Next Generation
Simple mass transport models using constant boundary conditions at the waste form surface and at the host rock boundary do not always results in realistic predictions of the performance...
WAPPA Modeling of Post-Emplacement Performance of the AECL HLNW Package
Environment Canada (EC) is anticipating, in the near future, a review of the EIS document released by AECL which addresses the performance of their HLNW disposal concept. This paper presents...
Scenario Development for Performance Assessment?Some Questions for the Near-Field Modelers
In an attempt to achieve completeness and consistency, the performance-assessment analyses developed by the Yucca Mountain Project are tied to scenarios described in event trees. Development...
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