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Remaining life prediction of the core shroud due to stress corrosion cracking failure in BWRs using numerical simulations
Y. K.; Lu Li, S. P.; Li, D. Z.; Kaji, Y.
2015
Source PublicationJournal of Nuclear Science and Technology
ISSN0022-3131
Volume52Issue:1Pages:96-103
AbstractStress corrosion cracking (SCC) of the welded joints in a reactor core shroud is the primary result of the residual stresses caused by welding, corrosion and neutron irradiation in a boiling water reactor (BWR). Therefore, the evaluation of SCC propagation is important for the safe maintenance of the core shroud. This paper attempts to predict the remaining life of the core shroud due to SCC failures in BWR conditions via SCC propagation time calculations. First, a two-dimensional finite element method model containing H6a girth weld in the core shroud was constructed, and the weld processing was simulated to determine the weld's residual stress distribution. Second, using a basic weld residual stress field, the SCC propagation was simulated using a node release option and the stress redistribution was calculated. Combined with the J-integral method, the stress intensity factors were calculated at depths of 2, 3, 4, 8, 12, 16, 19, 22, 25 and 30mm in the crack setting inside the core shroud; then, the SCC propagation rates were determined using the relation between the SCC propagation rate and the stress intensity factor. The calculations show that the core shroud could safely remain in service after 9.29years even when a 1-mm-deep SCC has been detected.
description.department[li, yongkui ; lu, shanping ; li, dianzhong] chinese acad sci, inst met res, shenyang natl lab mat sci, shenyang 110016, peoples r china. [kaji, yoshiyuki] japanese atom energy agcy, grp radiat mat engn, ibaraki 3191195, japan. ; lu, sp (reprint author), chinese acad sci, inst met res, shenyang natl lab mat sci, shenyang 110016, peoples r china. ; shplu@imr.ac.cn
KeywordStress Corrosion Cracking Boiling Water Reactor Life Prediction 316l Stainless Steel Finite Element Methods Core Shroud
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Document Type期刊论文
Identifierhttp://ir.imr.ac.cn/handle/321006/73852
Collection中国科学院金属研究所
Recommended Citation
GB/T 7714
Y. K.,Lu Li, S. P.,Li, D. Z.,et al. Remaining life prediction of the core shroud due to stress corrosion cracking failure in BWRs using numerical simulations[J]. Journal of Nuclear Science and Technology,2015,52(1):96-103.
APA Y. K.,Lu Li, S. P.,Li, D. Z.,&Kaji, Y..(2015).Remaining life prediction of the core shroud due to stress corrosion cracking failure in BWRs using numerical simulations.Journal of Nuclear Science and Technology,52(1),96-103.
MLA Y. K.,et al."Remaining life prediction of the core shroud due to stress corrosion cracking failure in BWRs using numerical simulations".Journal of Nuclear Science and Technology 52.1(2015):96-103.
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