This paper presents a finite element (FE) simulation technique to predict maximum load-carrying capacity of cracked steam generator tubes and its application to Alloy 690TT tubes. The simulation method is based on a simplified version of the stress modified fracture strain model. The damage model is determined from tensile test and one cracked tube test data. Predicted maximum pressures are compared with 23 test data of axial through-wall and surface cracked Alloy 690TT steam generator tubes. Comparison with experimental data shows good agreement.
Issue Section:
Operations, Applications and Components
References
1.
Scott
, P.
, Combrade
, P.
, Kilian
, R.
, Roth
, A.
, Andresen
, P.
, and Kim
, Y.
, 2005
, “Status Review of Initiation of Environmentally Assisted Cracking and Short Crack Growth
,” Electric Power Research Institute, Palo Alto, CA, EPRI Report No. 1011788.2.
Ford
, F.
, and McGehee
, A.
, 2006
, “Repair and Replacement Applications Center: Stress Corrosion Cracking in Closed Cooling Water Systems
,” Electric Power Research Institute, Palo Alto, CA, EPRI Report No. 1013563.3.
Hahn
, G. T.
, Sarrate
, M.
, and Rosenfield
, A. R.
, 1969
, “Criteria for Crack Extension in Cylindrical Pressure Vessels
,” Int. J. Fract. Mech.
, 5
(3
), pp. 187
–210
.4.
Erdogan
, F.
, 1976
, “Ductile Failure Theories for Pressurized Pipes and Containers
,” Int. J. Pressure Vessels Piping
, 4
(4
), pp. 253
–283
.5.
Ranganath
, S.
, and Mehta
, H. S.
, 1983
, “Engineering Methods for the Assessment of Ductile Fracture Margin in Nuclear Power Plant Piping
,” Elastic–Plastic Fracture: Second Symposium
, Louisville, KY, Apr. 20-22, Vol. 2, pp. 309
–330
.6.
Cochet
, B.
, 1991
, “Steam Generator Tube Integrity Volume 1: Burst Test Results and Validation of Rupture Criteria (Framatome Data)
,” Electric Power Research Institute, Palo Alto, CA, EPRI Report No. NP-6865-L.7.
Majumdar
, S.
, 1999
, “Prediction of Structural Integrity of Steam Generator Tubes Under Severe Accident Conditions
,” Nucl. Eng. Des.
, 194
(1
), pp. 31
–55
.8.
Majumdar
, S.
, Kasza
, K.
, Franklin
, J.
, and Muscara
, J.
, 2000
, “Pressure and Leak-Rate Tests and Models for Predicting Failure of Flawed Steam Generator Tubes
,” U.S. Nuclear Regulatory Commission, Washington, DC, Report No. NUREG/CR-6664.9.
Schomeker
, C. E.
, 1981
, “Workshop Proceedings: U-Bend Tube Cracking in Steam Generators
,” Electric Power Research Institute, Palo Alto, CA, EPRI Report No. WS-80-136.10.
Elng
, O.
, 2011
, “Assessment and Management of Ageing of Major Nuclear Power Plant Components Important to Safety: Steam Generators (2011 Update)
,” IAEA Safety Series, International Atomic Energy Agency, Vienna, Austria, Report No. IAEA-TECDOC-1668.11.
Miyajima
, Y.
, Kikuchi
, M.
, and Takahashi
, A.
, 2013
, “Ductile Fracture Simulation of a Pipe of Steam Generator in PWR
,” ASME
Paper No. PVP2013-97582.12.
Gurson
, A. L.
, 1977
, “Continuum Theory of Ductile Rupture by Void Nucleation and Growth. Part 1—Yield Criteria and Flow Rules for Porous Ductile Media
,” ASME J. Eng. Mater. Technol.
, 99
(1
), pp. 2
–15
.13.
Tvergaard
, V.
, and Needleman
, A.
, 1984
, “Analysis of the Cup–Cone Fracture in a Round Tensile Bar
,” Acta Metall.
, 32
(1
), pp. 157
–69
.14.
Schuler
, X.
, Seidenfuss
, M.
, Gehrlicher
, S.
, and Mahlke
, J.
, 2013
, “Damage Modeling of the Load-Bearing Capacity of Damaged Steam Generator Tubes in Nuclear Power Plants
,” ASME
Paper No. PVP2013-97196.15.
Rousselier
, G.
, 1987
, “Ductile Fracture Models and Their Potential in Local Approach of Fracture
,” Nucl. Eng. Des.
, 105
(1
), pp. 97
–111
.16.
ASTM
, 2006
, “Standard Test Method for Measurement of Fracture Toughness
,” Annual Book of ASTM Standards
, American Society for Testing and Materials
, Philadelphia, PA
, Standard No. ASTM E08-09.17.
Lee
, K. H.
, Kim
, H. D.
, Kang
, Y. S.
, Nam
, M. W.
, and Cho
, N. C.
, 2014
, “Burst Pressure Tests of Axial Part-Through-Wall Steam Generator Tubes
,” Trans. Kor. Soc. Pressure Vessel Piping
, 10
(1
), pp. 56
–63
(in Korean).18.
Keating
, R. F.
, and Begley
, J. A.
, 2001
, “Effect of Pressurization Rate on Degraded Steam Generator Tubing Burst Pressure: Revision 1
,” Electric Power Research Institute, Palo Alto, CA, EPRI Report No. 1006252.19.
McClintock
, F. A.
, 1968
, “A Criterion of Ductile Fracture by the Growth of Holes
,” ASME J. Appl. Mech.
, 35
(2
), pp. 363
–371
.20.
Rice
, J. R.
, and Tracey
, D. M.
, 1969
, “On the Ductile Enlargement of Voids in Triaxial Stress Fields
,” J. Mech. Phys. Solids
, 17
(3
), pp. 201
–217
.21.
Hancock
, J. W.
, and Mackenzie
, A.
, 1976
, “On the Mechanisms of Ductile Failure in High-Strength Steels Subject to Multi-Axial Stress States
,” J. Mech. Phys. Solids
, 24
(2
), pp. 147
–169
.22.
Garrison
, W. M.
, Jr., and Moody
, N. R.
, 1987
, “Ductile Fracture
,” J. Phys. Chem. Solids
, 48
(11
), pp. 1035
–1074
.23.
Bao
, Y.
, 2005
, “Dependence of Ductile Crack Formation in Tensile Test on Stress Triaxiality, Stress and Strain Ratios
,” Eng. Fract. Mech.
, 72
(4
), pp. 505
–522
.24.
Bao
, Y.
, and Wierzbicki
, T.
, 2004
, “On Fracture Locus in the Equivalent Strain and Stress Triaxiality Space
,” Int. J. Mech. Sci.
, 46
(1
), pp. 81
–98
.25.
Oh
, C. K.
, Kim
, Y. J.
, Baek
, J. H.
, and Kim
, W. S.
, 2007
, “Development of Stress-Modified Fracture Strain for Ductile Failure of API X65 Steel
,” Int. J. Fract.
, 143
(2
), pp. 119
–133
.26.
Oh
, C. S.
, Kim
, N. H.
, Kim
, Y. J.
, Baek
, J. H.
, Kim
, Y. P.
, and Kim
, W. S.
, 2011
, “A Finite Element Ductile Failure Simulation Method Using Stress-Modified Fracture Strain Model
,” Eng. Fract. Mech.
, 78
(1
), pp. 124
–137
.27.
Kim
, N. H.
, Oh
, C. S.
, Kim
, Y. J.
, Yoon
, K. B.
, and Ma
, Y. H.
, 2011
, “Comparison of Fracture Strain Based Ductile Failure Simulation With Experimental Results
,” Int. J. Pressure Vessels Piping
, 88
(10
), pp. 434
–447
.28.
Dassault
, 2011
, ABAQUS Version 6.11. User's Manual, Dassault Systemes Simulia
, Providence, RI.29.
Marini
, B.
, Mudry
, F.
, and Pineau
, A.
, 1985
, “Ductile Rupture of A508 Steel Under Nonradial Loading
,” Eng. Fract. Mech.
, 22
(3
), pp. 375
–386
.Copyright © 2016 by ASME
You do not currently have access to this content.