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...
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...
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...
Risk Assessments for the Design of Subsurface Openings
A probabilistic approach was introduced to assess the risk of structural instability due to rock joint systems in rock mass, where subsurface openings are excavated, such openings as shafts,...
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...
GA-4/GA-9 Honeycomb Impact Limiter Tests and Analytical Model
General Atomics (GA) has a test program underway to obtain data on the behavior of a honeycomb impact limiter. The program includes testing of small samples to obtain basic information,...
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...
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