Stress Corrosion Analysis of Steam Generator Tube of Nuclear Power Plant by Finite Elements

Author:

Jiang Shuang1,Cai Jun2,Zhang J.W.1,Wang Y.D.3

Affiliation:

1. North China Electric Power University

2. School of Nuclear Science and Engineering, North China Electric Power University, Beijing, China

3. Beijing University of Science and Technology

Abstract

The steam generator is operated under the pressure of 15.5MPa and the temperature 327°C. Under this working condition the junction of the heat transfer tube and tube-sheet is accident-prone areas of the steam generator. By using ANSYS to carry out a thermal structure coupling analysis on the junction, it is found that a large tensile stress along axial and tangential directions occurs on outer surface of the heat transfer tube and is located at the region of 2.0 mm to 6.0 mm high over the tube-sheet. The stress attributes to the rapidly change of temperature on the tube outer surface and leads to the stress corrosions.

Publisher

Trans Tech Publications, Ltd.

Reference11 articles.

1. Su L S, Yang H. Y, Wang F S: Systems and Equipment of Nuclear Power Plant for 900MW PWR. Beijing:Atomic Energy Press, 2004: 87(in Chinese).

2. Dai P K, Wu Z Q, Zhang C: Materials and its Welding of Key Equipment in Nuclear Island for PWR Nuclear Power Plant. Shanghai: ShangHai Scientific and Technological Literature Publishing House, 2009, 115(in Chinese).

3. Din X S: Journal of Chinese Society for Corrosion and Protection, 2000; 21(1): 15(in Chinese).

4. Ryu K S, Son D, Park D G, Jung J K: IEEE Transactions on Magnetics, 2009; 45(6): 2733.

5. Kumar R, Idvorian N: International Journal of Pressure Vessels and Piping, 2001; 78: 359.

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