Finite Element Analysis and Test Study on Restraint of High-energy Pipe Whip in Conventional Island
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The effects of high-energy pipe whipping after rupturing are very important in an AP1000 nuclear power plant’s conventional island and restraints of pipe whipping should be considered in the design. It is the first time in the country when reinforced concrete shear walls are used as restraint services. In this paper, the behaviors of walls and restraint services subjected to pipe whipping are analyzed through static and dynamic methods in the finite element software (ABAQUS), in which all kinds of nonlinearities are considered. In addition, a test study on the restraint of pipe whipping is conducted. The results show that the wall and the restraint service can prevent pipe whipping effectively under the design load, and anchor plates arranged around the wall opening can improve the local concrete compression performance of concrete to reduce the damage of concrete. Meanwhile, the study also provides the valuable reference for wall designing to prevent from pipe whipping.
KeywordsAP1000 conventional island high-energy pipe restraint of pipe whip ABAQUS test study
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- ABAQUS, Inc. (2010). ABAQUS analysis user’s manual, Version 6.10, Pawtucket, RI, USA.Google Scholar
- ANS (1988). Design basis for protection of light water nuclear power plants against the effects of postulated pipe rupture, Technical Report, ANSI/ANS-58.2, American Nuclear Society, La Grange Park, IL, USA.Google Scholar
- EJ335-88 (1998). Protective criteria for hypothetical pipe rupture accidents in PWR nuclear power plants, Ministry of Nuclear Industry of the People’s Republic of China, Beijing, China.Google Scholar
- Hua, Y. L. and Yu, T. X. (1988). “Analytical and numerical methods of pipe whip problems in nuclear power plants.” Computational Structural Mechanics and its Applications, China, Vol. 5, No. 1, pp. 105–112.Google Scholar
- Li, H. R., Wang, P., Li, D. R., and Wang, Y. F. (2011). “Analysis on high-energy pipe rupture in conventional island of AP1000 nuclear power plant.” Power Construction, China, Vol. 32, No. 3, pp. 88–91.Google Scholar
- Sun, J. L. (2014). Numerical simulation and simplified analysis on whipping of the main pipe-restraint system in nuclear power plant, MSc Thesis Harbin Institute of Technology, Haerbin, China.Google Scholar
- Wang, C. L. and Yu, J. C. (2011). “Simulation and analysis of main steam pipe whip based on LS-DYNA.” Nuclear Power Engineering, China, Vol. 32, No. 1, pp. 93–97.Google Scholar
- Yu, R. H. (1986). “An analysis of primary reactor coolant loop system for the protective design against pipe break effects.” Nuclear Power Engineering, China, Vol. 7, No. 6, pp. 49–56.Google Scholar
- Yu, T. X. and Hua, Y. L. (1986), “Wiping and protection of pipe rupture in nuclear power plant.” Pressure Vessel, China, Vol. 3, No. 1, pp. 70–76.Google Scholar
- Zhang, X. T., Cao, F. Y., and Ding, Y. (2011). “Load analysis of hypothetical rupture and optimum design of H-type anti-whip restraint devices for high energy pipes based on bilinearity methods.” Nuclear power engineering, China, Vol. 32, No. 5, pp. 64–68.Google Scholar