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Waste Package Reliability / Nalysis*

Published online by Cambridge University Press:  25 February 2011

C. Pescatore  and
C. Sastre
C. Pescatore
Affiliation:
Brookhaven National Laboratory, Upton, N.Y. 11973
C. Sastre
Affiliation:
Brookhaven National Laboratory, Upton, N.Y. 11973
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Abstract

Proof of future performance of a complex system such as a high-level nuclear waste package over a period of hundreds to thousands of years cannot be had in the ordinary sense of the word. The general method of probabilistic reliability analysis could provide an acceptable framework to identify, organize, and convey the information necessary to satisfy the criterion of reasonable assurance of waste package performance according to the regulatory requirements set forth in 10 CFR 60. General principles which may be used to evaluate the qualitative and quantitative reliability of a waste package design are indicated and illustrated with a sample calculation of a repository concept in basalt.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 26: Symposium D – Scientific Basis for Nuclear Waste Management VII , 1983 , 1069
Copyright
Copyright © Materials Research Society 1984

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Footnotes

*

This work was performed under the auspices of the United States Nuclear Regulatory Commission.

References

REFERENCES

1. US – NRC, 10 CFR Part 60 , Federal Register, 48. 120, June 21, 1983.Google Scholar
2. IEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Protection Systems, IEEE Std. 352 , Published by IEEE, New York, NY, 1975.Google Scholar
3. Reilly, J. T., A Review of Methods for the Integration of Reliability and Design Engineering, GA-A14748/UC-77, General Atomic Company (1978).Google Scholar
4. Sastre, C. and Pescatore, C., Draft Technical Position on Waste Package Reliability, Brookhaven National Laboratory, NUREG 0997, September 1983.Google Scholar
5. U.S. Dept. of the Navy, Procedures for Performing a Failure Mode and Effect Analysis for Shipboard Equipment, MIL-STD-1629 (SHIPS), Dept. of the Navy (1974).Google Scholar
6. INTERA Environmental Consultants, Inc., A Proposed Approach to Uncertainty Analysis. ONWI-488, Office of Nuclear Waste Isolation (1983).Google Scholar
7. Iman, R. L., et al, Latin Hypercube Sampling (Program User´s Guide), SAND-79-1973, Sandia National Laboratory (1980).Google Scholar
8. Rockwell Hanford Operations, Site Characterization Report for the Basalt Waste Isolation Proiect, DOE/RL82-3, Vol. II, U.S. Dept. of Energy (1982).Google Scholar