Degradation Mode Surveys of High Performance Candidate Container Materials
Corrosion resistant materials are being considered for the metallic barrier of the Yucca Mountain Project's high-level radioactive waste disposal containers. Nickel-chromium-molybdenum...

An Electrochemical Approach to Predicting Corrosion Performance of Container Materials
The pitting potentials of nickel-rich Alloy 825 are measured in chloride-containing solutions at different temperatures and adjusted to different pH values. The pitting potentials were...

Potential Uses of Lead in Nuclear Waste Disposal
In order for lead to be considered as a nuclear waste packaging material, it must be shown that it has adequate corrosion resistance, and that it does not degrade the properties of other...

Modelling Studies for the Assessment of the Advanced Cold Process Canister
The Advanced Cold Process Canister (ACPC) is a new concept for the encapsulation of spent nuclear fuel for geological disposal. It consists of steel canister encased in a copper overpack....

Activities Aimed at Qualification of a HLW Disposal Container
A container is being developed for the permanent disposal of used fuel from CANDU nuclear reactors in a deep underground disposal vault. The container is required to isolate the fuel from...

Future Supply of, and Demand for, Titanium, Copper and Lead
A literature survey has been conducted to assess the future world supply of, and demand for, titanium, copper and lead. These metals are candidates for the fabrication of containers for...

Research Program to Develop and Validate Conceptual Models for Flow and Transport Through Unsaturated, Fractured Rock
As part of the Yucca Mountain Project, our research program to develop and validate conceptual models for flow and transport through unsaturated fractured rock integrates fundamental physical...

Variation of Permeability with Temperature in Fractured Topopah Spring Tuff Samples
Fractures will play an important role in the near-field hydrology of a nuclear-waste package in a mined repository. Our previous studies showed that the water permeability of fractured...

An Alternative Method to Mariotte Reservoir System for Maintaining Constant Hydraulic Pressure
Several problems with the Mariotte reservoir system were discovered when it was used to apply a constant water pressure as a boundary condition for a prolonged period. The constant-pressure...

Pore-Water Extraction from Unsaturated Tuffs Using One-Dimensional Compression
To support the study of the unsaturated-zone hydrochemistry at Yucca Mountain, Nevada, a one-dimensional compression system was developed and tested to extract unaltered and uncontaminated...

Solving the High-Level (and Low-Level) Radioactive Waste Puzzle
Finding sites for both high-level and low-level radioactive wastes (LLRW and HLRW) has come to a virtual halt. The present system is based on a 'command-and-control'...

The Chemical Stockpile Intergovernmental Consultation Program: Lessons for High Level Waste Public Involvement
This paper assesses the appropriateness of the U.S. Army's Chemical Stockpile Disposal Program's (CSDP) Intergovernmental Consultation and Coordination Boards...

A Model for Effective Intergovernmental Planning
Effective intergovernmental planning processes are essential to the resolution of potential affects created by federal projects. In this paper, two successful planning efforts are described....

Opting for Cooperation?A Case Study in Siting a Low Level Radioactive Waste Management Facility
In 1986, the Canadian federal government called a halt to efforts by a crown corporation to site a low-level radioactive waste management facility when it became apparent that continuation...

Building Consensus in Developing Radioactive Waste Management Systems
To successfully develop radioactive waste management systems, national authorities must work to establish consensus on numerous complex issues among many affected and interested parties....

Source Term Model for Radioactive Waste Repository
A radioactive waste repository source term model is developed to predict radionuclide release rates from solidified waste packages disposed of in underground repository. Leach rates, i.e.,...

Near-Field Transport of Radioactive Chains
Much attention has been given to predicting the near-field mass transfer of a single radioactive species from a waste solid into surrounding porous material, but only limited consideration...

Validation of Source-Term Models Using Natural Analogues
A comparison is made between the predicted distribution of copper calculated by the AREST source-term code and the measured profiles for copper surrounding a bronze cannon that was emplaced...

Potential ?4CO2 Releases from Spent Fuel Containers at Yucca Mountain
The potential release of gaseous 14CO2 from small perforations in spent fuel containers has been evaluated...

MARNIE, a Near Field Transport Model for Radioactive Waste Repositories
The long term safety of a final repository for radioactive waste disposal has to be demonstrated. A number of scenarios can be postulated that could lead to a considerable release of radionuclides...

 

 

 

 

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