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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...

The Integrated Performance Assessment in SKI Project-90
The SKI Project-90 is a performance assessment of a hypothetical repository system with KBS-3 features in crystalline rock. A large part of the effort has been to identify and characterize...

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...

Application of TQM to the Waste Management QA Regulatory Arena
Over the past several years, a number of the scientists involved with the high-level radioactive waste repository project have expressed concern regarding the application of quality assurance...

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....

The Licensing Support System (LSS): Who Should Operate it and Will it Work?
The development of the mammoth Licensing Support System (LSS), a management information system intended to handle documentation relevant to the licensing application of the DOE for the...

The Licensing Support System: Institutional Challenges and Opportunities
The Licensing Support System (LSS) is an electronic information management system which will be used in the Nuclear Regulatory Commission's (NRC) review of the Department...

Regulatory Systems-Based Licensing Guidance Documentation
The U.S. Nuclear Regulatory Commission (NRC) has developed a series of licensing guidance documents based on the regulatory requirements in Part 60 of Title 10 of the Code of Federal Regulations...

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...

Scoping Experimental Analysis of Factors Affecting Cask Contamination Weeping
One issue of particular concern to both the US Nuclear Regulatory Commission (NRC) and the US Department of Energy (DOE) involves the control of in-transit 'weeping'...

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,...

 

 

 

 

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