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Linkage Between Site Characterization Program and Performance and Design Data Needs

by Maxwell B. Blanchard, U.S. Dep of Energy, United States,
David C. Dobson, U.S. Dep of Energy, United States,
Jean L. Younker, U.S. Dep of Energy, United States,
Michael D. Voegele, U.S. Dep of Energy, United States,



Document Type: Proceeding Paper

Part of: High Level Radioactive Waste Management 1990

Abstract:

The basis for identifying site-specific data needs for the Yucca Mountain site was a thorough review and evaluation of the regulatory requirements for a geologic repository. The U.S. Nuclear Regulatory Commission's (NRC) regulation governing disposal of high-level waste in a geologic repository (10 CFR Part 60)¹ utilizes a multiple barrier approach that includes reliance on both engineered and natural elements. Given an understanding of the regulatory requirements, the next step was to identify the natural features of the site and the components of the engineered barriers considered most likely to make significant contributions to isolation of waste at Yucca Mountain. The intent was to develop a site testing program that focused on (a) understanding those natural site characteristics and processes most likely to contribute to waste isolation; and (b) providing site data necessary to design and assess the performance of engineered barriers.

Subject Headings: Radioactive wastes | Site investigation | Waste sites | Geology | Waste disposal | Industrial wastes | Federal government | Nevada | United States

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