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Perspectives on the Science Advisor Program at Sandia National Laboratories

Development Status of the GA-4 and GA-9 Casks

A Comparison of a New Generation of Spent Fuel Cask Designs with Current Cask Design Characteristics

Shipping Cask Development Loaded 4 PWR Fuel Assemblies

The Thermal Analysis of BR-100: A Barge/Rail Nuclear Spent Fuel Transportation Container

Routine Methods for Post-Transportation Accident Recovery of Spent Fuel Casks

System Selection of Concepts for Direct Disposal of Spent Fuel

Development of Functional Requirements for a Monitored Retrievable Storage Installation

MRS Using a FUELSTOR^MT Vault

Issues Influencing Colocation and Integration of Cask Maintenance and MRS Facilities

Interfacing the Existing Cask Fleet with the MRS or Fitting Round Pegs Into Square Holes

MRS Project Management

Economic Analysis of Including an MRS Facility in the Waste Management System: A Revisit

Mandated Public Participation in Siting of Hazardous and Conventional Waste Facilities: The Illinois Experience

Towards Earning Public Trust and Confidence Through Accountability

Towards Confidence in Transport Safety: Demonstrating an Extraordinary Safety Program

Nuclear Waste Repository Program Oversight: Strategies of the Situs Jurisdiction

A Context for Understanding the Significance of Radiation Exposures from the MRS

Diffusion of Carbon Dioxide and Iodine Through Yucca Mountain Tuffs?Effects of Temperature and Moisture Content

Characterization of the Topopah Spring and Tiva Canyon Tuffs at Yucca Mountain

 

 

 

 

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