Overall risk estimation for nonreactor nuclear facilities and implementation of safety goals [electronic resource].

Published: Washington, D.C. : United States. Dept. of Energy, 1992.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description: Pages: (34 pages) : digital, PDF file
Additional Creators: Westinghouse Savannah River Company, United States. Department of Energy, and United States. Department of Energy. Office of Scientific and Technical Information

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Summary

A typical safety analysis report (SAR) contains estimated frequencies and consequences of various design basis accident (DBA) analyses. However, the results are organized and presented in such a way that they are not conducive for summing up with mathematical rigor to give total or overall risk. This paper describes a simple protocol and mathematical formalism to derive overall risk indicators. These indicators provide some insight into the capability of confinement barriers with characteristics of source terms, and provide comparison to the Safety Goals. The protocol makes maximum use of the results of DBA analyses typically available from an SAR. The mathematical formalism is based on the cumulative complementary distribution function (CCDF) or exceedance probability of radioactivity release fraction and individual radiation dose. An example case analysis is presented to illustrate how to use the proposed protocol and mathematical formalism. A discussion of the result is also presented in terms of confinement characteristic and compliance to Safety Goals.

Report Numbers

E 1.99:wsrc-ms-92-276
E 1.99: conf-9208117--9
conf-9208117--9
wsrc-ms-92-276

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Note

Published through SciTech Connect.
01/01/1992.
"wsrc-ms-92-276"
" conf-9208117--9"
"DE92040049"
1992 safety analysis workshop, Salt Lake City, UT (United States), 11-13 Aug 1992.
Bradley, R.F.; Kim, Kyo S.

Funding Information

AC09-89SR18035

View MARC record | catkey: 14359362