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Deterministic and probabilistic evaluations for uncertainty in pipe fracture parameters in leak-before-break and in-service flaw evaluations
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Deterministic and probabilistic evaluations for uncertainty in pipe fracture parameters in leak-before-break and in-service flaw evaluations

N Ghadiali, G Wilkowski, S Rahman and Y.H Choi
U.S. Nuclear Regulatory Commission
06/01/1996
DOI: 10.2172/256412
url
https://doi.org/10.2172/256412View
Published (Version of record) Open Access

Abstract

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.
Materials Science Nuclear Power Plants FAILURES IN-SERVICE INSPECTION LEAKS NUCLEAR REACTOR TECHNOLOGY P CODES PIPES PRIMARY COOLANT CIRCUITS PROBABILISTIC ESTIMATION

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