Structural Engineering and Mechanics

  • 제2권2호
  • /
  • Pages.157-171
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  • 1994
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  • 1225-4568(pISSN)
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  • 1598-6217(eISSN)
테크노프레스 (Techno-Press)
권호 표지
DOI QR코드

DOI QR Code

Seismic behavior of fuel assembly for pressurized water reactor

  • Jhung, Myung J. (Power Reactor Mechanical Engineering, Korea Atomic Energy Research Institute) ;
  • Hwang, Won G. (Department of Mechanical Engineering, Chonnam National University)
  • 발행 : 1994.06.25
⟨ 이전 논문 다음 논문 ⟩

초록

A general approach to the dynamic time-history analysis of the reactor core is presented in this paper as a part of the fuel assembly qualification program. Several detailed core models are set up to reflect the placement of the fuel assemblies within the core shroud. Peak horizontal responses are obtained for each model for the motions induced form earthquake. The dynamic responses such as fuel assembly deflected shapes and spacer grid impact loads are carefully investigated. Also, the sensitivity responses are obtained for the earthquake motions and the fuel assembly non-linear response characteristics are discussed.

키워드

참고문헌

  1. ASCE (1986), Standard for Seismic Analysis of Safety-Related Nuclear Structures. American Society of Civil Engineers, New York.
  2. Chen, S. S. (1975), "Vibrations of nuclear fuel bundles". Nuclear Engineering and Design, 35, 399-422. https://doi.org/10.1016/0029-5493(75)90071-0
  3. Gabrielson, V. K. (1966), "SHOCK-A computer code for solving lumped-mass dynamic systems", Technical Report SCL-DR-65-34. Sandia Laboratories. Livermore. CA.
  4. Jhung, M.J., Song, H. G. and Park, K. B. (1992a), "Dynamic characteristics of spacer grid impact loads for SSE", Journal of the Korean Nuclear Society. 24(2). 111-120.
  5. Jhung, M.J., Park, K. B. and Sohn, G. H. (1992b), "Dynamic analysis of the reactor core for pipe break and seismic excitations", Proceedings of the 7th International Conference on Pressure Vessel Technology, Dusseldorf, Germany, June.
  6. Jhung, M.J. and Hwang, W. G. (1993), "Seismic design criteria for the reactor vessel internals of the Korean Standard Nuclear Power Plant", Proceedings of the Seminar on Pressure Vessel and Piping Technology. Singapore, May.
  7. Kuo, S. S. (1972), Computer Applications of Numerical Methods. Addison-Wesley, New York.
  8. Queval, J. C., Gantenbein, F. and Rigaudeau, J. (1991). "Experimental studies on seismic behavior of PWR fuel assembly rows", Seismic Engineering-1991, ASME PVP 220, 255-260.
  9. Stokes, F. E. and King, R. A. (1978), "PWR fuel assembly dynamic characteristics", BNES, Vibration in Nuclear Plants, Keswick, UK.
  10. USNRC, (1980), "Methodology for combining dynamic responses", NUREG-0484, Rev. 1, US Nuclear Regulatory Commission, New York.

피인용 문헌

  1. Integrity evaluation of fuel assembly for earthquake vol.185, pp.1, 1998, https://doi.org/10.1016/S0029-5493(98)00230-1
  2. Dynamic characteristics of rectangular twisted beam with fins surrounded with fluid vol.237, pp.1, 2007, https://doi.org/10.1016/j.nucengdes.2006.03.021
  3. DYNAMIC CHARACTERISTICS OF CYLINDRICAL SHELLS CONSIDERING FLUID-STRUCTURE INTERACTION vol.41, pp.10, 2009, https://doi.org/10.5516/NET.2009.41.10.1333