Deterministic and probabilistic evaluations for uncertainty in pipe fracture parameters in leak-before-break and in-service flaw evaluations [electronic resource].

Published:: Rockville, Md. : U.S. Nuclear Regulatory Commission, 1996.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description:: 128 pages : digital, PDF file
Additional Creators:: U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology, U.S. Nuclear Regulatory Commission, and United States. Department of Energy. Office of Scientific and Technical Information

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Summary:

This report presents new results from deterministic and probabilistic analyses to evaluate the significance of a number of technical aspects that may affect LBB or in-service flaw evaluations. The following summarizes the objectives and results from both the deterministic and probabilistic studies. The reasons for including each technical aspect being evaluated are given first. Then a table is given that summarizes the relative significance of each technical aspect. In most cases there are both deterministic and probabilistic results. The deterministic analyses were conducted independently of the probabilistic analysis, which offered the opportunity to validate conclusions from each of these studies.

Report Numbers:

E 1.99:nureg/cr--6443
E 1.99: bmi--2191
bmi--2191
nureg/cr--6443

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Note:

Published through SciTech Connect.
06/01/1996.
"nureg/cr--6443"
" bmi--2191"
"TI96012372"
"NONE"
Choi, Y.H.; Rahman, S.; Ghadiali, N.; Wilkowski, G.

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