The development of a deep geologic repository system in the United States has progressed to the preparation of an application for a license from the U.S. Nuclear Regulatory Commission. The project received site recommendation approval from the U.S. President in early 2002. The next phase of the project involves development of the license application (LA) utilizing the vast body of information accumulated in study of the site at Yucca Mountain, Nevada. Development of the license application involves analyses of the total system performance assessment (TSPA) of the repository, the TSPA-LA. The TSPA includes the available relevant information and model analyses from the various components of the system (e.g., unsaturated geologic zone, engineered system (waste packaging and drift design), and saturated geologic zone) (see Fig. 1 for nominal condition components), and unites that information into a single computer model used for evaluating the potential future performance or degradation of the repository system. The primary regulatory guidance for the repository system is found in 10 CFR 63, which indicates the acceptable risk to future populations from the repository system. The performance analysis must be traceable and transparent, with a defensible basis. The TSPA-LA is being developed utilizing state-of-the-art modeling software and visualization techniques, building on a decade of experience with such analyses. The documentation of the model and the analyses will be developed with transparency and traceability concepts to provide an integrated package for reviewers. The analysis relies on 1000’s of pages of supporting information, and multiple software and process model analyses. The computational environment represents the significant advances in the last 10 years in computer workstations. The overall approach will provide a thorough, transparent compliance analysis for consideration by the U.S. Nuclear Regulatory Commission in evaluating the Yucca Mountain repository.
Skip Nav Destination
ASME 2003 9th International Conference on Radioactive Waste Management and Environmental Remediation
September 21–25, 2003
Oxford, England
Conference Sponsors:
- Nuclear Engineering Division and Environmental Engineering Division
ISBN:
0-7918-3732-7
PROCEEDINGS PAPER
Proceeding Toward a License Application for U.S. Nuclear Waste Repository: Total System Performance Assessment Approach
Jerry McNeish,
Jerry McNeish
Bechtel SAIC, LLC, Las Vegas, NV
Search for other works by this author on:
David Sevougian,
David Sevougian
Sandia National Laboratories
Search for other works by this author on:
Donald Kalinich,
Donald Kalinich
Sandia National Laboratories
Search for other works by this author on:
Robert MacKinnon
Robert MacKinnon
Sandia National Laboratories
Search for other works by this author on:
Jerry McNeish
Bechtel SAIC, LLC, Las Vegas, NV
Peter Swift
Sandia National Laboratories
Rob Howard
Bechtel SAIC, LLC, Las Vegas, NV
David Sevougian
Sandia National Laboratories
Donald Kalinich
Sandia National Laboratories
Robert MacKinnon
Sandia National Laboratories
Paper No:
ICEM2003-4956, pp. 1651-1658; 8 pages
Published Online:
February 24, 2009
Citation
McNeish, J, Swift, P, Howard, R, Sevougian, D, Kalinich, D, & MacKinnon, R. "Proceeding Toward a License Application for U.S. Nuclear Waste Repository: Total System Performance Assessment Approach." Proceedings of the ASME 2003 9th International Conference on Radioactive Waste Management and Environmental Remediation. 9th ASME International Conference on Radioactive Waste Management and Environmental Remediation: Volumes 1, 2, and 3. Oxford, England. September 21–25, 2003. pp. 1651-1658. ASME. https://doi.org/10.1115/ICEM2003-4956
Download citation file:
6
Views
Related Proceedings Papers
Related Articles
Editorial
J. Comput. Inf. Sci. Eng (December,2007)
Assessment of CHF Enhancement Mechanisms in a Curved, Rectangular Channel Subjected to Concave Heating
J. Heat Transfer (May,1999)
A Multiscale Materials Modeling Method With Seamless Zooming Capability Based on Surfacelets
J. Comput. Inf. Sci. Eng (June,2017)
Related Chapters
Use of PSA in Lisencing of EPR 1600 in Finland (PSAM-0160)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
QRAS Approach to Phased Mission Analysis (PSAM-0444)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Development of Nuclear Boiler and Pressure Vessels in Taiwan
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 3, Third Edition