Numerical validation of burst pressure estimation equations for steam generator tubes with multiple axial surface cracks

Ji Seok Kim; Myeong Woo Lee; Yun Jae Kim; Jin Weon Kim

doi:10.1016/j.net.2018.10.013

Numerical validation of burst pressure estimation equations for steam generator tubes with multiple axial surface cracks

Ji Seok Kim, Myeong Woo Lee, Yun Jae Kim, Jin Weon Kim

Research output: Contribution to journal › Article › peer-review

2 Citations (Scopus)

Abstract

This paper provides further validation of the burst pressure estimation equations for multiple axial surface cracked steam generator tubes, recently proposed by the authors based on analytical local collapse load approach against systematic FE damage analysis results of Alloy 690 tubes with twin axial surface cracks. Wide ranges of the relative crack depth and multiple crack configurations are considered. Comparison shows good agreements, giving sufficient confidence of the proposed equations.

Original language	English
Pages (from-to)	579-587
Number of pages	9
Journal	Nuclear Engineering and Technology
Volume	51
Issue number	2
DOIs	https://doi.org/10.1016/j.net.2018.10.013
Publication status	Published - 2019 Apr
Externally published	Yes

Keywords

Alloy 690 steam generator tube
Burst pressure estimation equations
Finite element damage analysis
Multiple axial surface cracks

ASJC Scopus subject areas

Nuclear Energy and Engineering

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10.1016/j.net.2018.10.013

Cite this

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title = "Numerical validation of burst pressure estimation equations for steam generator tubes with multiple axial surface cracks",

abstract = "This paper provides further validation of the burst pressure estimation equations for multiple axial surface cracked steam generator tubes, recently proposed by the authors based on analytical local collapse load approach against systematic FE damage analysis results of Alloy 690 tubes with twin axial surface cracks. Wide ranges of the relative crack depth and multiple crack configurations are considered. Comparison shows good agreements, giving sufficient confidence of the proposed equations.",

keywords = "Alloy 690 steam generator tube, Burst pressure estimation equations, Finite element damage analysis, Multiple axial surface cracks",

author = "Kim, {Ji Seok} and Lee, {Myeong Woo} and Kim, {Yun Jae} and Kim, {Jin Weon}",

note = "Funding Information: This research was supported by National Research Foundation of Korea funded by the Ministry of Science, ICT and Future Planning. ( NRF-2016M2A8A1952771 ) Publisher Copyright: {\textcopyright} 2018",

year = "2019",

month = apr,

doi = "10.1016/j.net.2018.10.013",

language = "English",

volume = "51",

pages = "579--587",

journal = "Nuclear Engineering and Technology",

issn = "1738-5733",

publisher = "Korean Nuclear Society",

number = "2",

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T1 - Numerical validation of burst pressure estimation equations for steam generator tubes with multiple axial surface cracks

AU - Kim, Ji Seok

AU - Lee, Myeong Woo

AU - Kim, Yun Jae

AU - Kim, Jin Weon

N1 - Funding Information: This research was supported by National Research Foundation of Korea funded by the Ministry of Science, ICT and Future Planning. ( NRF-2016M2A8A1952771 ) Publisher Copyright: © 2018

PY - 2019/4

Y1 - 2019/4

N2 - This paper provides further validation of the burst pressure estimation equations for multiple axial surface cracked steam generator tubes, recently proposed by the authors based on analytical local collapse load approach against systematic FE damage analysis results of Alloy 690 tubes with twin axial surface cracks. Wide ranges of the relative crack depth and multiple crack configurations are considered. Comparison shows good agreements, giving sufficient confidence of the proposed equations.

AB - This paper provides further validation of the burst pressure estimation equations for multiple axial surface cracked steam generator tubes, recently proposed by the authors based on analytical local collapse load approach against systematic FE damage analysis results of Alloy 690 tubes with twin axial surface cracks. Wide ranges of the relative crack depth and multiple crack configurations are considered. Comparison shows good agreements, giving sufficient confidence of the proposed equations.

KW - Alloy 690 steam generator tube

KW - Burst pressure estimation equations

KW - Finite element damage analysis

KW - Multiple axial surface cracks

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JO - Nuclear Engineering and Technology

JF - Nuclear Engineering and Technology

IS - 2

ER -

Numerical validation of burst pressure estimation equations for steam generator tubes with multiple axial surface cracks

Abstract

Keywords

ASJC Scopus subject areas

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