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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...

Preliminary Calculations of Release Rates from Spent Fuel in a Tuff Repository
Time-dependent release rates of Tc-99, I-129, Cs-135, and Np-237 have been calculated for wet-drip and moist-continuous release modes from the engineered barrier system of a potential...

Mechanical Excavator Performance in Yucca Mountain Tuffs
A research effort of four phases is in progress at the Colorado School of Mines. The overall program will evaluate the cutability of welded tuff and other lithologies likely to be excavated...

Principles of the NATM and Other Uses of the Geologic Monitoring Techniques
The NATM (New Austrian Tunneling Method) differs in several respects from other construction methods. Also referred to as the 'sequential support method' or the...

The Standard Contract's Delivery Commitment Schedule Process
The Standard Contract for the Disposal of Spent Nuclear Fuel and/or High-Level Radioactive Waste specifies various activities necessary for the eventual acceptance of spent nuclear fuel...

A Comparison of High-Level Waste Form Characteristics
The U.S. Department of Energy is responsible for the eventual disposal in a repository of spent fuels, high-level waste (HLW) and other radioactive wastes that may require long-term isolation....

Effects of Spent Fuel Aging on Repository Disposal Requirements
A study has been carried out to analyze the effects of extended spent fuel aging on spent fuel disposal requirements. The analysis considers additional spent fuel aging up to a maximum...

Evaluation of Alternative MGDS Development Strategies
A methodology has been developed to explicitly and quantitatively evaluate acceptable alternative repository development strategies, in terms of the degree to which they are likely to...

Determination of Cost Effective Waste Management System Receipt Rates
A comprehensive logistics and cost analysis has been carried out to determine if there are potential benefits to the high-level waste management system for receipt rates other than the...

Conclusions from Project-90 With Regard to a Regulatory Framework
A five year performance assessment program, Project-90 [1], has been concluded by the Swedish Nuclear Power Inspectorate, SKI. The project was defined to develop independent assessment...

CALIBRE and CRYSTAL: Near-field and Geosphere Models for Project-90
A new near-field model (CALIBRE) and a fractured geosphere model (CRYSTAL) have been developed in support of the Swedish Nuclear Power Inspectorate's Project-90 safety assessment...

Status of WIPP Compliance with EPA 40 CFR 191, December 1990?SAND90-2424C
Sandia National Laboratories is conducting performance assessments for the United States Department of Energy to use in evaluating compliance of the Waste Isolation Pilot Plant with EPA...

Performance Assessment Calculational Exercises (PACE-90): Overview and Summary
PACE-90 was undertaken by the Yucca Mountain Site Characterization Project in order to develop expertise in computational capabilities and to aid in identification of critical elements...

Preliminary Performance Assessment of a Nevada Test Site Waste Disposal Facility
The performance of the Nevada Test Site Greater Confinement Disposal (GCD) site was assessed against the Environmental Protection Agency's (EPA) requirements for disposal...

 

 

 

 

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