Burst pressure estimation of Alloy 690 axial cracked steam generator U-bend tubes using finite element damage analysis |
Kim, Ji-Seok
(Korea University, Department of Mechanical Engineering)
Kim, Yun-Jae (Korea University, Department of Mechanical Engineering) Lee, Myeong-Woo (Korea Atomic Energy Research Institute, Innovative SMR System Development Division) Jeon, Jun-Young (Korea Institute of Materials Science, Authorized Nuclear Inspection Department) Kim, Jong-Sung (Sejong University, Department of Nuclear Engineering) |
1 | J. Baron, W. Cullen, J. Smith, L. Genutis, K. Colgan, Steam Generator Management Program: Steam Generator Degradation Specific Management Flaw Handbook, Revision 2, Cranberry Township (PA), Westinghouse Electric Company, Palo Alto, CA, 2015 Nov 03. Report No. 3002005426. Sponsored by Electric Power Research Institute. |
2 | C.B. Bahn, Y.J. Oh, S. Majumdar, Ligament rupture and unstable burst behaviors of axial flaws in steam generator U-bends, Nucl. Eng. Des. 293 (17-19) (2015) 228-237. DOI |
3 | J.Y. Jeon, Y.J. Kim, J.W. Kim, K.H. Lee, J.S. Kim, Numerical prediction of maximum load-carrying capacity of cracked alloy 690TT steam generator tubes, J. Pressure Vessel Technol. 138 (4) (2016), 041601. DOI |
4 | H.S. Nam, Y.R. Oh, Y.J. Kim, J.S. Kim, N. Miura, Application of engineering ductile tearing simulation method to CRIEPI pipe test, Eng. Fract. Mech. 153 (2016) 128-142. DOI |
5 | C.S. Oh, N.H. Kim, Y.J. Kim, J.H. Baek, Y.P. Kim, W.S. Kim, A finite element ductile failure simulation method using stress-modified fracture strain model, Eng. Fract. Mech. 78 (1) (2011) 124-137. DOI |
6 | F.A. McClintock, A criterion of ductile fracture by the growth of holes, J. Appl. Mech. 35 (2) (1968) 363-371. DOI |
7 | G.R. Jonson, W.H. Cook, Fracture characteristics of three metals subjected to various strains, strain rates, temperatures and pressures, Eng. Fract. Mech. 21 (1) (1985) 31-48. DOI |
8 | B. Flesch, B. Cochet, Leak-before-break in steam generator tubes, Int. J. Pres. Ves. Pip. 43 (1990) 165-179. DOI |
9 | J. Allan, S. Kaufmann, E. Murphy, J. Strosnider, M. Gamborini, D. Lu, T. Sullivan, T. Pitterle, T. Esselman, A. Neff, J. Mark, J. Parry, J. Baumstark, D. Mcadam, D. Adanonis, G. Henry, Official Transcript of Proceedings United States of America Nuclear Regulatory Commission: NRC and Consolidated Edison Technical Meeting Regarding IP2 Steam Generator, U.S. Nuclear Regulatory Commission, Washington, DC, 2000 May 3. |
10 | T.J. McGinty, Crack-like Indication in the U-Bend Region of a Thermally Treated Alloy 600 Steam Generator Tube, 2010 Oct 6. NRC information notice 2010-21. |
11 | J.R. Rice, D.M. Tracey, On the ductile enlargement of voids in triaxial stress fields, J. Mech. Phys. Solid. 17 (3) (1969) 201-217. DOI |
12 | J.W. Hancock, A.C. Mackenzie, On the mechanisms of ductile failure in highstrength steels subject to multi-axial stress states, J. Phys. Mech. Solids 24 (2-3) (1976) 147-160. DOI |
13 | P.E. MacDonald, V.N. Shah, L.W. Ward, P.G. Ellison, Steam Generator Tube Failures. Idaho Falls (ID): Idaho National Engineering Lab, Div. Of Safety Programs, U.S. Nuclear Regulatory Commission, Washington, DC, 1996 Apr 1. Report No. NUREG/CR-6365, INEL-95/0383. |
14 | M.W. Lee, J.S. Kim, J.Y. Jeon, Y.J. Kim, J.W. Kim, J.S. Kim, Comparison of numerical predictions with experimental burst pressures of tubes with multiple surface cracks, Eng. Fract. Mech. 201 (2018) 176-195. DOI |
15 | J.S. Kim, M.W. Lee, Y.J. Kim, J.W. Kim, Numerical validation of burst pressure estimation equations for steam generator tubes with multiple axial surface cracks, Nucl. Eng. Technol. 51 (2) (2019) 579-587. DOI |
16 | K.H. Eom, J.W. Kim, Evaluation of tensile properties of alloy 690TT steam generator tube at room temperature and 343℃, Trans. Kor. Soc. Mech. Eng. A 38 (6) (2014) 655-662 [Korean]. DOI |
17 | S. Newberry, J. Donoghue, R. Ennis, L. Lund, A. Rubin, J. Yerokun, Indian point 2 steam generator tube failure lessons-learned report, in: TAC No. MA9163, U.S. Nuclear Regulatory Commission, Washington, DC, 2000 Oct 23. |
18 | Dassault, ABAQUS Version 6.18. User's Manual, Dassault Systemes Simulia, Providence, RI, 2018. |
19 | Ph. Berge, H.D. Bui, J.R. Donati, D. Villard, Residual stresses in bent tubes for nuclear steam generators, Corrosion 32 (9) (1976) 357-364. DOI |
20 | H.W. Ryu, K.D. Bae, Y.J. Kim, J.J. Han, J.S. Kim, P.J. Budden, Ductile tearing simulation of Battelle pipe test using simplified stress-modified fracture strain concept, Fatig. Fract. Eng. Mater. Struct. 39 (11) (2016) 1391-1406. DOI |
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