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Salt Creep Design Consideration for Underground Nuclear Waste Storage

Published online by Cambridge University Press:  21 February 2011

William T. Li
Affiliation:
Bechtel National, Inc., P.O. Box 3965, San Francisco, Ca 94119
Ching L. Wu
Affiliation:
Bechtel National, Inc., P.O. Box 3965, San Francisco, Ca 94119
Nicholas J. Antonasc
Affiliation:
Bechtel National, Inc., P.O. Box 3965, San Francisco, Ca 94119
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Abstract

This paper summarizes the creep consideration in the design of nuclear waste storage facilities in salt, describes the non-linear analysis method for evaluating the design adequacy, and presents computational results for the current storage design. The application of rock mechanics instrumentation to assure the appropriateness of the design is discussed.

It also describes the design evolution of such a facility, starting from the conceptual design, through the preliminary design, to the detailed design stage The empirical design method, laboratory tests and numerical analyses, and the underground in situ tests have been incorporated in the design process to assure the stability of the underground openings, retrievability of waste during the operating phase and encapsulation of waste after decommissioning.

Type
Research Article
Copyright
Copyright © Materials Research Society 1983

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References

REFERENCES

1. U.S. Department of Energy, Waste Isolation Pilot Plant Safety Analysis Report, (Sept. 1980).Google Scholar
2. Sandia National Laboratory, “Waste Isolation Pilot Plant Conceptual Design Report”, SAND 77–0274, (1977).Google Scholar
3. Bechtel, “WIPP Title I Design Report”, (July, 1979).Google Scholar
4. Li, W. T. and Wu, C. L., “Analysis of Creep for a Nuclear Waste Storage in Salt Formation”, Nuclear Technology, Vol. 61, No. 1, to be published, (April, 1983).CrossRefGoogle Scholar
5. MARC Analysis Research Corp., “MARC General Purpose Finite Element Program User Information Manual”, Rev. J.2, (1981).Google Scholar
6. Reum, J. W. and Howes, E. V., “Geotechnical Instrumentation and Data Acquisition System for Site and Preliminary Design Validation at the DOE Waste Isolation Pilot Plant”, IEEE proc. on Nuclear Science, (Feb. 1982).Google Scholar