The thermal stratification phenomenon widely exists in the pressurizer surge line (PSL) during the steady-state conditions and transient conditions, which could result an unexpected stress distribution. Especially, the maximum stress range is most likely to appear nearby the weld joint area on the PSL. This paper mainly focuses on the pressurizer surge line stress distribution variation caused by the weld joint. The temperature distribution and stress distribution of the surge line are calculated by using the finite element method (FEM) and finite volume method (FVM). Steady-state operating conditions are considered. The conclusion of this work is that the stress distribution is quite different from the traditional stress profile merely caused by the upper and lower temperature stratification. Moreover, the stress is much higher in the interact-area between PSL matrix and the weld joint than in any other areas.
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2014 22nd International Conference on Nuclear Engineering
July 7–11, 2014
Prague, Czech Republic
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4589-9
PROCEEDINGS PAPER
Numerical Analysis of the Weld Joint Resulting Influence on the Pressurizer Surge Line Stress Distribution
Yang Yang,
Yang Yang
Harbin Engineering University, Harbin, China
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Hong Xia,
Hong Xia
Harbin Engineering University, Harbin, China
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Xian Zeng,
Xian Zeng
Harbin Engineering University, Harbin, China
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Dali Yu
Dali Yu
Harbin Engineering University, Harbin, China
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Yang Yang
Harbin Engineering University, Harbin, China
Hong Xia
Harbin Engineering University, Harbin, China
Xian Zeng
Harbin Engineering University, Harbin, China
Dali Yu
Harbin Engineering University, Harbin, China
Paper No:
ICONE22-30470, V001T01A008; 5 pages
Published Online:
November 17, 2014
Citation
Yang, Y, Xia, H, Zeng, X, & Yu, D. "Numerical Analysis of the Weld Joint Resulting Influence on the Pressurizer Surge Line Stress Distribution." Proceedings of the 2014 22nd International Conference on Nuclear Engineering. Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues. Prague, Czech Republic. July 7–11, 2014. V001T01A008. ASME. https://doi.org/10.1115/ICONE22-30470
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