Numerical Prediction of Maximum Load-Carrying Capacity of Cracked Alloy 690TT Steam Generator Tubes

Author:

Jeon Jun-Young1,Kim Yun-Jae1,Kim Jin-Weon2,Lee Kuk-Hee3,Kim Jong-Sung4

Affiliation:

1. Department of Mechanical Engineering, Korea University, Sungbuk-Ku, Seoul 136-701, Korea e-mail:

2. Department of Nuclear Engineering, Chosun University, Dong-Gu, Gwngju 501-759, Korea e-mail:

3. Korea Hydro and Nuclear Power Company, Yusung-Gu, Daejeon 34101, Korea e-mail:

4. Department of Mechanical Engineering, Sunchon National University, Suncheon, Jwollanam-do 540-742, Korea e-mail:

Abstract

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.

Publisher

ASME International

Subject

Mechanical Engineering,Mechanics of Materials,Safety, Risk, Reliability and Quality

Reference29 articles.

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