Estimation of Elastic Crack Opening Displacement for Thin Elbows With Circumferential Through-Wall Cracks

Published on Jul 19, 2015
· DOI :10.1115/PVP2015-45461
Min Kyu Kim1
Estimated H-index: 1
 (SKKU: Sungkyunkwan University), Min Kyu Kim9
Estimated H-index: 9
 (SKKU: Sungkyunkwan University)+ 3 AuthorsJae-Boong Choi20
Estimated H-index: 20
 (SKKU: Sungkyunkwan University)
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Abstract
Leak-before-break (LBB) is an important concept that could confirm design and integrity evaluation of nuclear power plant piping. For the LBB analysis, the detective leakage rate should be calculated for a through-wall cracked pipes. For this calculation, the crack opening displacement (COD) calculation is essential.Recently, sodium faster reactor (SFR) which has thin-walled pipes with Rm/t ranged 30–40 was introduced and then the investigation of these thin walled pipes and elbows has received great attention in the LBB evaluation. In this context, the three-dimensional finite element (FE) analyses for thin elbows with circumferential crack under in-plane bending are carried out to investigate the elastic COD values.Finally, the solution for elastic COD which can cover sufficiently thin elbow is successfully addressed.Copyright © 2015 by ASME
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Sep 1, 2020·Nuclear Engineering and Technology1.85
#1Min Kyu Kim (SKKU: Sungkyunkwan University)H-Index: 1
#1Min Kyu Kim (SKKU: Sungkyunkwan University)H-Index: 9
Last. Moon Ki Kim (SKKU: Sungkyunkwan University)H-Index: 18
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Abstract Many damages due to flow-accelerated corrosion and cracking have been observed during recent in-service inspections of nuclear power plants. To determine the operability or repair for damaged pipes, an integrity evaluation related to the damaged piping system should be performed by using already proven code and standards. One of them, the ASME Code Case is most popularly used to integrity assessment in nuclear power plants. However, the recent version of CC N-513 still recommends the si...
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