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Supervision and Automatic Control of Robotic Systems in Nuclear Environments

Graphical Models for Simulation and Control of Robotic Systems for Waste Handling

Robotics for Radioactive Waste Management in AEA Technology Facilities

Deterministic and Probabilistic Performance Assessment Methods Applied to Radionuclide Migration Through Fractured Geologic Medium

Demands Placed on Waste Package Performance Testing and Modeling by Some General Results of Reliability Analysis

The Impact of Thermal Loading on Repository Performance at Yucca Mountain

Probabilistic Assessment of Spent-Fuel Cladding Breach

Characterizing the Altered Zone at Yucca Mountain: The Beginning of a Testing Strategy

Use of Annotated Outlines to Prepare Guidance for License Applications for the MRS and MGDS

An Inside Look at the 40 CFR 191 Containment Requirements

Licensing Code-of-Practice

U.S. Department of Energy Issue Resolution Process

Preliminary Analysis of Repository Operational Criteria

Equivalence to 1,000 MTHM of Spent Fuel: Application of 40 CFR Part 191 to Other Wastes

Design and Construction of Two Major Experiments at the URL

In Situ Testing Program at the Waste Isolation Pilot Plant

Site Investigation Equipment Developed by Teollisuuden Voima Oy

X-Ray and Visible Light Transmission as Two-Dimensional, Full-Field Moisture-Sensing Techniques: A Preliminary Comparison

High Resolution Seismic Imaging for Characterizing Fractures in Potential Sites for Nuclear Waste Repositories

A System for Measuring Moisture Transients in Clay-Based Barrier Materials

 

 

 

 

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