ASME 2010 Pressure Vessels and Piping Conference: Volume 6, Parts a and B 2010
DOI: 10.1115/pvp2010-25162
|View full text |Cite
|
Sign up to set email alerts
|

Advanced Finite Element Analysis (AFEA) Evaluation for Circumferential and Axial PWSCC Defects

Abstract: The Advanced Finite Element Analysis (AFEA) methodology has been developed by the US NRC and the nuclear industry to evaluate the natural crack growth of primary water stress corrosion cracking (PWSCC) in nickel-based alloy materials. The AFEA methodology allows the progression of a planar crack subjected to typical SCC-type growth laws by calculating stress intensity factors at every nodal point along the crack front, and incrementally advancing the crack front in a more natural manner. This paper describes t… Show more

Help me understand this report

Search citation statements

Order By: Relevance

Paper Sections

Select...
1
1

Citation Types

0
2
0

Year Published

2011
2011
2025
2025

Publication Types

Select...
3
2

Relationship

1
4

Authors

Journals

citations
Cited by 5 publications
(2 citation statements)
references
References 0 publications
0
2
0
Order By: Relevance
“…In doing so, an iterative FE analysis was conducted with the worst-case SCC crack growth rate observed in any nuclear plant (even though those materials were not used in the Argentina plant). The iterative FE approach crack shape modelling and some validations are described in detail in References [Shim et al 2012 andShim et al 2010]. The high crack growth rate was used since the design was for 80 years of life.…”
Section: Fe Analysis Of a Full Nuclear Steam Supply System (Nsss)mentioning
confidence: 99%
“…In doing so, an iterative FE analysis was conducted with the worst-case SCC crack growth rate observed in any nuclear plant (even though those materials were not used in the Argentina plant). The iterative FE approach crack shape modelling and some validations are described in detail in References [Shim et al 2012 andShim et al 2010]. The high crack growth rate was used since the design was for 80 years of life.…”
Section: Fe Analysis Of a Full Nuclear Steam Supply System (Nsss)mentioning
confidence: 99%
“…The standard of validation required depends on the sensitivity of subsequent structural integrity assessments to the presence of residual stress. Thus, high levels of validation may be required for assessments of safety-critical plant with the potential for brittle fast fracture, or where stress corrosion cracking is a concern (for example, see 30,47,[55][56][57][58][59] ). Three validation standards are defined:…”
Section: Step 8: Analysis Validationmentioning
confidence: 99%