The behavior of defects like cracks in nuclear components operating at high temperature, where creep is significant, must be under control. There exists the need to have a practical method of analysis, which can be used by engineers, to calculate the time of initiation for defects existing at the start of life of nuclear components. This study presents the background, the development, the application, and results concerning validation work made for a simplified method named σd of prediction of initiation for nuclear structures made of 316L austenitic steel and operating at temperature where creep is significant. This method relies on the evaluation of real stress-strain history on a small distance d (d = 0.05 mm) close to the crack front and material characteristics (limiting stresses) that are available in nuclear codes like ASME Code cases or RCC-MR.

1.
Ainsworth
R. A.
,
1982
, “
The Initiation of Creep Crack Growth
,”
International Journal of Solids and Structures
, Vol.
18
, No.
10
, pp.
873
881
.
2.
Ainsworth, R. A., 1986, CEGB Report—TPRD/B/0784/R86, “Assessment Procedure for Defects in Plant Operating in the Creep Range.”
3.
ASME, 1986, Class 1, “Components in Elevated Temperature Service,” Code Case N47-23, ASME, New York, NY.
4.
ASTM E399-83, “Standard Test Method for Plane Strain Fracture Toughness of Metallic Materials.”
5.
Autrusson, B., Moulin, D., and Acker, D., 1990, “Validation of Crack Like Defect Fatigue Analysis. Fatigue, Degradation and Fracture,” 1990, PVP, Vol. 195, MPC Vol. 30.
6.
Autrusson, B., Moulin, D., Barrachin, B., and Acker, D., 1988, “Fatigue Analysis of Crack Like Defect: Experimental Verification of Practical Rules to Predict Initiation,” 6th ICPVT, Beijing, P.R.C.
7.
Creager, M., 1966, “The Elastic Stress Field Near the Tip of a Blunt Crack,” thesis, Lehigh University, Lehigh, PA.
8.
Heywood, R. B., 1955, “Stress Concentration Factors: Relating Theoretical and Practical Factors in Fatigue Design,” Engineering, February 4.
9.
Laiarinandrasana, L., 1994, “Crack Initiation at Elevated Temperature on an Austenitic Stainless Steel,” thesis, Ecole Nationale Supe´rieure des Mines de Paris, France.
10.
Langer, B. F., 1971, “Design of Vessels Involving Fatigue in Pressure Vessel Engineering Technology,” ed; R. W. Nichols, Applied Science Pub. Ltd., London, U.K., pp. 59–100.
11.
Merkle, J. G., and Corten, H. T., 1974, “A J Integral Analysis for the Compact Specimen, Considering Axial Force as Well as Bending Effects,” ASME JOURNAL OF PRESSURE VESSEL TECHNOLOGY, Nov., pp. 286–292.
12.
Moulin, D., Autrusson, B., and Barrachin, B., 1987, “Fatigue Analysis Methods of Crack Like Defects: Strain Range Evaluation,” 9th SMIRT, Lausanne, Switzerland.
13.
Moulin, D., 1991, “A Simplified Method to Predict Initiation of Crack Under Creep Conditions,” SMIRT 11, Trans. Vol. G (Aug.) Tokyo, Japan.
14.
Neuber, H., 1961, “Theory of Stress Concentration for Shear Strained Prismatic Bodies with Arbitrary Nonlinear Stress Strain Law,” ASME JOURNAL OF APPLIED MECHANICS, Dec., pp. 544–550.
15.
Peterson, R. E., 1938, “Methods of Correlating Data from Fatigue Tests on Stress Concentration Factor,” S. Timoshenko anniversary volume, MacMillan, New York, NY.
16.
Piques, R., 1989, “Mechanics and Mecanisms to Crack Initiation and Growth Under Viscoplastic Conditions in an Austenitic Stainless Steel,” thesis, Ecole Nationale Supe´rieure des Mines de Paris, France.
17.
RCC-MR, 1985, Design and Construction Rules for Mechanical Components of FBR Nuclear Islands, First Edition (AFCEN, Paris, France.
18.
Rice, J. R., 1976, “Elastic-Plastic Fracture Mechanics. The Mechanics of Fracture,” ASME AMD-Vol. 19, Winter Annual Meeting, New York, NY, December 5–10.
19.
Riedel, H., and Rice, J. R., 1980, “Tensile Cracks in Creeping Solids,” Fracture Mechanics, ASTM STP 700, pp. 112–130.
20.
Roche, R., 1987, “The Use of Elastic Computation for Analysing Fatigue Damage,” 9th SMIRT, Lausanne, Switzerland.
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