The Adoption of Mechanized Excavation Techniques for the Superconducting Super Collider
The Superconducting Super Collider (SSC) is the latest and largest in a line of high-energy physics accelerator projects. The five increasingly energetic accelerators which make up the...
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...
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...
Application of QA Program for Yucca Mountain Site Characterization Project Geologic Investigations
The High Level Waste Program requires safe disposal of nuclear waste in a geologic medium for thousands of years. Traditionally, the nuclear industry relies heavily on engineered items....
Drafting of an ISO Standard for Leakage Tests on Packaging for the Transport of Radioactive Material
A working group (TC85/SC5/WG 10) has been formed by ISO for the drafting of an international standard covering the leak testing of radioactive material transport containers. A certain...
Cask Systems Development Program Seal Technology
General design or test performance requirements for radioactive materials (RAM) packages are specified in Title 10 of the U.S. Code of Federal Regulations Part 71 (10 CFR 71). Seals that...
Testing of Materials and Scale Models for Impact Limiters
Aluminum Honeycomb and Polyurethane foam specimens were tested to obtain experimental data on the material's behavior under different loading conditions. This paper reports...
Modelling of Excavation, Thermal Loading and Bentonite Swelling Pressure for a Waste Repository
For the performance assessment of a future nuclear waste repository, the excavation of the tunnel and deposition hole, thermal loading from waste heat release and the swelling pressure...
Apparent and Simple Diffusion Coefficients in Compacted Bentonite
Diffusion coefficients were experimentally determined in bentonite to evaluate the effectiveness of bentonite layers as a diffusion barrier to ionic transport away from high-level radioactive...
Estimating Geochemical Behavior of Cocnretes to be Placed at Yucca Mountain
The interactions of J-13 water with cementitious materials were examined at 25?C using the geochemical code EQ3NR/EQ6. Results of the modeling suggested the following conclusions: (1)...
Management and Research of Desert Tortoises for the Yucca Mountain Project
A program has been developed for the Yucca Mountain Project (YMP) to manage and study the desert tortoise (Gopherus agassizi), a threatened species that occurs at low densities at Yucca...
Preliminary Assessment of the Impact of Conceptual Model Uncertainty on Site Performance
Performance assessment modeling for high-level radioactive waste (HLW) disposal incorporates three different types of uncertainty. These include data and parameter uncertainty, modeling...
An Approach to Assessing the Impacts of Incident-Free Air and Highway Transportation of Radioactive Materials
Annual radiation doses and risks were calculated for shipments of radioactive materials both in passenger aircraft and on highways, under accident-free and incident-free conditions, i.e.,...
Emplacement Drift Temperature Reduction by Cooling Enhancement and Ventilation
The application of cooling enhancement in a short vertical container emplacement layout is analyzed. Two 25 m-long heat pipes upward oriented at 45 degrees are installed at each emplacement...
The Constructive Use of Heat in an Unsaturated Tuff Repository
By designing the engineered barrier system in an unsaturated tuff repository to constructively use heat, the waste containers can be kept dry for hundreds of years. Without water, the...
Uncertainty Analysis of Preclosure Accident Doses for the Yucca Mountain Repository
This study presents a generic methodology that can be used to evaluate the uncertainty in the calculated accidental offsite doses at the Yucca Mountain repository during the preclosure...
Site-Generic Approach for Performance Assessment of HLW Disposal System in Japan
This paper presents an overview of the preliminary performance analyses and description of R&D activities designed based upon the results of the analyses, which are to be incorporated...
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