An Analytical Method of Determining Damage Initiation for Potential Use in Establishing Strain-Based Failure Criteria

Wu, Tsu-Te

doi:10.1115/pvp2009-77435

Cited by 1 publication

(3 citation statements)

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“…8, the following regressions were proposed: 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 þ 0:0919 ðthe section average approachÞ (15) where Eq. (14) does not include results for the V-notched bar because its expected damage initiation location is different from the others due to very high strain concentration at the notch tip.…”

Section: 2mentioning

confidence: 99%

“…The design philosophy of the ASME B&PV Code, Section III for the structural integrity of safety class 1 nuclear components is to prevent plastic instability or ductile tearing initiation before fracture. In accordance with this design philosophy, some researchers have proposed strain-based acceptance criteria on the basis of the damage acceleration point corresponding to the maximum load-carrying capability [14,15]. However, EPRI calculated the strain at the damage initiation point using Cooper's approximate solutions for pressurized thin-walled cylinders and spheres, which could be inaccurate [14].…”

Section: Introductionmentioning

confidence: 99%

“…However, EPRI calculated the strain at the damage initiation point using Cooper's approximate solutions for pressurized thin-walled cylinders and spheres, which could be inaccurate [14]. Wu [15] proposed the strain-based acceptance criteria aimed at shipping package design, but the criteria is not systematic and realistic because real tensile test results were not used.…”

Section: Introductionmentioning

confidence: 99%

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Strain-based plastic instability acceptance criteria for ferritic steel safety class 1 nuclear components under level D service loads

Kim¹,

Lee²,

Kim³

et al. 2015

Nuclear Engineering and Technology

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a b s t r a c tThis paper proposes strain-based acceptance criteria for assessing plastic instability of the safety class 1 nuclear components made of ferritic steel during level D service loads. The strain-based criteria were proposed with two approaches: (1) a section average approach and (2) a critical location approach. Both approaches were based on the damage initiation point corresponding to the maximum load-carrying capability point instead of the fracture point via tensile tests and finite element analysis (FEA) for the notched specimen under uni-axial tensile loading. The two proposed criteria were reviewed from the viewpoint of design practice and philosophy to select a more appropriate criterion. As a result of the review, it was found that the section average approach is more appropriate than the critical location approach from the viewpoint of design practice and philosophy. Finally, the criterion based on the section average approach was applied to a simplified reactor pressure vessel (RPV) outlet nozzle subject to SSE loads. The application shows that the strain-based acceptance criteria can consider cumulative damages caused by the sequential loads unlike the stress-based acceptance criteria and can reduce the overconservatism of the stress-based acceptance criteria, which often occurs for level D service loads.

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Section: 2mentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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