Probabilistic analysis of core shroud cracks
Resource
Nuclear Engineering and Design 214,103-112
Journal
Nuclear Engineering and Design
Journal Volume
214
Journal Issue
1-2
Pages
103-112
Date Issued
2002
Date
2002
Author(s)
DOI
246246/2006111501254377
Abstract
Traditional limit load analysis & fracture mechanics analysis have been applied to evaluate the integrity of the degraded nuclear power plant components. Although these methodologies are generally accepted by the regulatory authorities in the nuclear industry, conservatism introduced by the uncertainties of inspection, material property, crack geometry, applied loading, neutron environment, etc. is recognized to have great impact on the evaluation accuracy. A probabilistic analysis may overcome this shortcoming & reveal some additional insight to the problem. The purpose of the present study is to apply probabilistic methods to analyze the degraded core shroud, & to predict the quantitative risk of the cracked shroud. In the analysis, the loading condition, crack growth rate, material properties & existing defects are all considered random. A sample analytical result shows that, based on some previously observed data & under certain assumptions, the crack-through probability of the studied core shroud is in the order of 10−7 after 13 cycles of operation. The probability will increase considerably through operation cycles or operation years if no repair action is taken.
SDGs
Type
journal article
File(s)![Thumbnail Image]()
Loading...
Name
8690.pdf
Size
23.19 KB
Format
Adobe PDF
Checksum
(MD5):838fabfc9c8ebb0d5c6d3b5ae2df0a77