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Burst pressure estimation of Alloy 690 axial cracked steam generator U-bend tubes using finite element damage analysis

Authors
Kim, Ji-SeokKim, Yun-JaeLee, Myeong-WooJeon, Jun-YoungKim, Jong-Sung
Issue Date
2월-2021
Publisher
KOREAN NUCLEAR SOC
Keywords
Alloy 690 steam generator U-bend tube; Burst pressure; Finite element damage analysis; Strain hardening due to the U-bending process
Citation
NUCLEAR ENGINEERING AND TECHNOLOGY, v.53, no.2, pp.666 - 676
Indexed
SCIE
SCOPUS
KCI
Journal Title
NUCLEAR ENGINEERING AND TECHNOLOGY
Volume
53
Number
2
Start Page
666
End Page
676
URI
https://scholar.korea.ac.kr/handle/2021.sw.korea/50023
DOI
10.1016/j.net.2020.07.024
ISSN
1738-5733
Abstract
This paper presents numerical estimation of burst pressures of axial cracked U-bend tubes, considering the U-bending process analysis. The validity of the FE simulations is confirmed by comparing with published experimental data. From parametric analyses, it is shown that existing EPRI burst pressure estimation equations for straight tubes can be conservatively used to estimate burst pressures of the U-bend tubes. This is due to the increase in yield strength during the U-bending process. The degree of conservatism would decrease with increasing the bend radius and with increasing the crack depth. (c) 2020 Korean Nuclear Society, Published by Elsevier Korea LLC. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).
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공과대학 (기계공학부)
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